An analysis of decommissioning costs for the AFRRI TRIGA reactor facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Forsbacka, Matt

1990-07-01

A decommissioning cost analysis for the AFRRI TRIGA Reactor Facility was made. AFRRI is not at this time suggesting that the AFRRI TRIGA Reactor Facility be decommissioned. This report was prepared to be in compliance with paragraph 50.33 of Title 10, Code of Federal Regulations which requires the assurance of availability of future decommissioning funding. The planned method of decommissioning is the immediate decontamination of the AFRRI TRIGA Reactor site to allow for restoration of the site to full public access - this is called DECON. The cost of DECON for the AFRRI TRIGA Reactor Facility in 1990 dollars ismore » estimated to be $3,200,000. The anticipated ancillary costs of facility site demobilization and spent fuel shipment is an additional $600,000. Thus the total cost of terminating reactor operations at AFRRI will be about $3,800,000. The primary basis for this cost estimate is a study of the decommissioning costs of a similar reactor facility that was performed by Battelle Pacific Northwest Laboratory (PNL) as provided in USNRC publication NUREG/CR-1756. The data in this study were adapted to reflect the decommissioning requirements of the AFRRI TRIGA. (author)« less

Analysis of decommissioning costs for the AFRRI TRIGA reactor facility. Technical report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Forsbacka, M.; Moore, M.

1989-12-01

This report provides a cost analysis for decommissioning the Armed Forces Radiobiology Research Institute (AFRRI) TRIGA reactor facility. AFRRI is not suggesting that the AFRRI TRIGA reactor facility be decommissioned. This report was prepared in compliance with paragraph 50.33 of Title 10, Code of Federal Regulations, which requires that funding for the decommissioning of reactor facilities be available when licensed activities cease. The planned method of decommissioning is complete decontamination (DECON) of the AFRRI TRIGA reactor site to allow for restoration of the site to full public access. The cost of DECON in 1990 dollars is estimated to be $3,200,000.more » The anticipated ancillary costs of facility site demobilization and spent fuel shipment will be an additional $600,000. Thus, the total cost of terminating reactor operations at AFRRI will be about $3,800,000. The primary basis for developing this cost estimate was a study of the decommissioning costs of similar reactor facility performed by Battelle Pacific Northwest Laboratory, as provided in U.S. Nuclear Regulatory Commission publication NUREG/CR-1756. The data in this study were adapted to reflect the decommissioning requirements of the AFRRI TRIGA reactor facility.« less

Decommissioning of the High Flux Beam Reactor at Brookhaven National Laboratory.

PubMed

Hu, Jih-Perng; Reciniello, Richard N; Holden, Norman E

2012-08-01

The High Flux Beam Reactor (HFBR) at the Brookhaven National Laboratory was a heavy-water cooled and moderated reactor that achieved criticality on 31 October 1965. It operated at a power level of 40 mega-watts. An equipment upgrade in 1982 allowed operations at 60 mega-watts. After a 1989 reactor shutdown to reanalyze safety impact of a hypothetical loss of coolant accident, the reactor was restarted in 1991 at 30 mega-watts. The HFBR was shut down in December 1996 for routine maintenance and refueling. At that time, a leak of tritiated water was identified by routine sampling of ground water from wells located adjacent to the reactor's spent fuel pool. The reactor remained shut down for almost 3 y for safety and environmental reviews. In November 1999, the United States Department of Energy decided to permanently shut down the HFBR. The decontamination and decommissioning of the HFBR complex, consisting of multiple structures and systems to operate and maintain the reactor, were complete in 2009 after removing and shipping off all the control rod blades. The emptied and cleaned HFBR dome, which still contains the irradiated reactor vessel is presently under 24/7 surveillance for safety. Details of the HFBR's cleanup performed during 1999-2009, to allow the BNL facilities to be re-accessed by the public, will be described in the paper.

Status of the NRC Decommissioning Program

DOE Office of Scientific and Technical Information (OSTI.GOV)

Orlando, D. A.; Camper, L.; Buckley, J.

2003-02-24

On July 21, 1997, the U.S. Nuclear Regulatory Commission (NRC) published the final rule on Radiological Criteria for License Termination (the License Termination Rule or LTR) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submitmore » Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program that was presented during WM'02. It discusses the staff's current efforts to streamline the decommissioning process, current issues being faced in the decommissioning program, such as partial site release and restricted release of sites, as well as the status of the decommissioning of complex sites and those listed in the Site Decommissioning Management Plan. The paper discusses the status of permanently shut-down commercial power reactors and the transfer of complex decommissioning sites and sites listed on the SDMP to Agreement States. Finally the paper provides an update of the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including an effort to consolidate and risk-inform decommissioning guidance.« less

International Research Reactor Decommissioning Project

DOE Office of Scientific and Technical Information (OSTI.GOV)

Leopando, Leonardo; Warnecke, Ernst

2008-01-15

Many research reactors have been or will be shut down and are candidates for decommissioning. Most of the respective countries neither have a decommissioning policy nor the required expertise and funds to effectively implement a decommissioning project. The IAEA established the Research Reactor Decommissioning Demonstration Project (R{sup 2}D{sup 2}P) to help answer this need. It was agreed to involve the Philippine Research Reactor (PRR-1) as model reactor to demonstrate 'hands-on' experience as it is just starting the decommissioning process. Other facilities may be included in the project as they fit into the scope of R{sup 2}D{sup 2}P and complement tomore » the PRR-1 decommissioning activities. The key outcome of the R{sup 2}D{sup 2}P will be the decommissioning of the PRR-1 reactor. On the way to this final goal the preparation of safety related documents (i.e., decommissioning plan, environmental impact assessment, safety analysis report, health and safety plan, cost estimate, etc.) and the licensing process as well as the actual dismantling activities could provide a model to other countries involved in the project. It is expected that the R{sup 2}D{sup 2}P would initiate activities related to planning and funding of decommissioning activities in the participating countries if that has not yet been done.« less

[Cytokine-mediated regulation of expression of Gfi1 and U2afll4 genes activated by T-cells with different differentiation status in vitro].

PubMed

Yurova, K A; Sokhonevich, N A; Khaziakhmatova, O G; Litvinova, L S

2016-01-01

The dose-dependent effects of cytokines (IL-2, IL-7, and IL-15), which have a common g-chain, on mRNA expression of U2afll4 and GFi1 genes involved in regulation of alternative splicing of the Ptprc gene, have been investigated in vitro using T-lymphocyte cultures with different degrees of differentiation. IL-2, IL-7, and IL-15 caused a similar unidirectional inhibitory effect of various severity on restimulated CD45RO+ T-cells exposed to an antigen-independent activation; they caused a dose-dependent decrease of the U2af1l4 gene expression, and an increase of Gfi1 gene expression. This may suggest formation of active forms of the CD45 receptor, and also limitation of the formation of low-molecular short splice variants of the CD45RO receptor. Under conditions of antigen-independent stimulation of naive CD45RA+-cells rIL-7 and IL-15 exhibited opposite effects on U2af1l4 and Gfi1 gene expression. The increase of IL-7 concentrations in the incubation medium of naive cells was accompanied by a decrease in expression of both genes. IL-15 IL-7 exhibited opposite effects. Cytokines possessing a common g-chain (IL-2, IL-7, and IL-15) prevented antigen-independent differentiation of naive T-cells, by preventing the formation of polyclonal "surrogate" cells. In general, the study of the molecular mechanisms of genetic control determining homeostatic processes of T-cells in response to exposure to antigenic or non-antigenic treatments may be important for construction of a general model of self-maintenance and differentiation of immune cells.

Decontamination and decommissioning of the Mayaguez (Puerto Rico) facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Jackson, P.K.; Freemerman, R.L.

1989-11-01

On February 6, 1987 the US Department of Energy (DOE) awarded the final phase of the decontamination and decommissioning of the nuclear and reactor facilities at the Center for Energy and Environmental Research (CEER), in Mayaguez, Puerto Rico. Bechtel National, Inc., was made the decontamination and decommissioning (D and D) contractor. The goal of the project was to enable DOE to proceed with release of the CEER facility for use by the University of Puerto Rico, who was the operator. This presentation describes that project and lesson learned during its progress. The CEER facility was established in 1957 as themore » Puerto Rico Nuclear Center, a part of the Atoms for Peace Program. It was a nuclear training and research institution with emphasis on the needs of Latin America. It originally consisted of a 1-megawatt Materials Testing Reactor (MTR), support facilities and research laboratories. After eleven years of operation the MTR was shutdown and defueled. A 2-megawatt TRIGA reactor was installed in 1972 and operated until 1976, when it woo was shutdown. Other radioactive facilities at the center included a 10-watt homogeneous L-77 training reactor, a natural uranium graphite-moderated subcritical assembly, a 200KV particle accelerator, and a 15,000 Ci Co-60 irradiation facility. Support facilities included radiochemistry laboratories, counting rooms and two hot cells. As the emphasis shifted to non-nuclear energy technology a name change resulted in the CEER designation, and plans were started for the decontamination and decommissioning effort.« less

75 FR 80697 - Nuclear Decommissioning Funds

Federal Register 2010, 2011, 2012, 2013, 2014

2010-12-23

... Nuclear Decommissioning Funds AGENCY: Internal Revenue Service (IRS), Treasury. ACTION: Final regulations... decommissioning nuclear power plants. These final regulations affect taxpayers that own an interest in a nuclear... preamble. 1. Definitional Matters A. Definition of Nuclear Decommissioning Costs One commentator on the...

Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

DOE Office of Scientific and Technical Information (OSTI.GOV)

Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi

2013-07-01

Decommissioning Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)« less

PREVALENCE OF MUTATIONS IN ELANE, GFI1, HAX1, SBDS, WAS, AND G6PC3 IN PATIENTS WITH SEVERE CONGENITAL NEUTROPENIA

PubMed Central

Xia, Jun; Bolyard, Audrey Anna; Rodger, Elin; Stein, Steve; Aprikyan, Andrew A.; Dale, David C.; Link, Daniel C.

2009-01-01

SUMMARY Severe congenital neutropenia (SCN) is a genetically heterogeneous syndrome associated with mutations of ELANE (ELA2), HAX1, GFI1, WAS, CSF3R or G6PC3. We investigated the prevalence of mutations of ELANE in a cohort of 162 SCN patients for whom blood or bone marrow samples were submitted to the North American Severe Chronic Neutropenia Tissue Repository. Mutations of ELANE were found in 90 of 162 patients (55.6%). Subsequently, we conducted an analysis of a subset of 73 of these cases utilizing a high throughput sequencing approach to determine the prevalence of other mutations associated with SCN. Among the 73 patients, mutations of ELANE were detected in 28. In the remaining 45 patients with wild type ELANE alleles, 5 patients had mutations: GFI1 (1), SBDS (1), WAS (1) and G6PC3 (2); no mutations of HAX1 were detected. In approximately 40% of our cases, the genetic basis of SCN remains unknown. These data suggest that for genetic diagnosis of SCN, ELANE genotyping should first be performed. In patients without ELANE mutations, other known SCN-associated gene mutations will be found rarely and genotyping can be guided by the clinical features of each patient. PMID:19775295

Education in nuclear decommissioning in the north of Scotland

DOE Office of Scientific and Technical Information (OSTI.GOV)

Catlow, F.; Reeves, G.M.

2007-07-01

This paper describes the work covered and experience gained in the first two years of operation of DERC, a Centre for Decommissioning and Environmental Remediation in the Highlands of Scotland. The Centre is a unique development which was set up to teach nuclear decommissioning as a separate discipline, address the problem of a declining skills base in the field of nuclear technologies and to take advantage of the unique and exceptional innovative, technical and research opportunities offered through the decommissioning of Britain's fast reactor site at Dounreay. The Centre is an offshoot from North Highland College which is a membermore » of UHI, the University in embryo of the Highlands and Islands. The Centre currently supports ten PhD students completing various diverse projects mainly in the field of nuclear environmental remediation. In addition there area number of full and part time MSc students who participate in NTEC (Nuclear Technology Education Consortium) a consortium of British Universities set up specifically to engender interest and skills in nuclear technology at postgraduate level. At undergraduate level, courses are offered in Nuclear Decommissioning and related subjects as part of Electrical and Mechanical degree courses. In addition to our relationship with the United Kingdom Atomic Energy Authority (UKAEA) the Dounreay site licensee, we have links with Rolls-Royce and the Ministry of Defence who also share the Dounreay site and with other stakeholders such as, the UK regulator (HSE/NII), the Scottish Environmental Protection Agency (SEPA), local and international contractors and we liaise with the newly formed Nuclear Decommissioning Authority (NDA), who provide some sponsorship and support. We possess our own equipment and laboratories for taking and analysing soil samples and for conducting environmental surveys. Recently we commissioned an aerial survey of contamination in the locality from natural sources, other background levels such as

76 FR 77431 - Decommissioning Planning During Operations

Federal Register 2010, 2011, 2012, 2013, 2014

2011-12-13

... (DG) DG-4014, ``Decommissioning Planning During Operations.'' This guide describes a method that the.... The draft regulatory guide entitled, ``Decommissioning Planning During Operations,'' is temporarily..., 40, 50, 70, and 72 RIN 3150-AI55 [NRC-2011-0286; NRC-2008-0030] Decommissioning Planning During...

78 FR 663 - Decommissioning Planning During Operations

Federal Register 2010, 2011, 2012, 2013, 2014

2013-01-04

...] Decommissioning Planning During Operations AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide..., ``Decommissioning Planning During Operations.'' The guide describes a method that the NRC staff considers acceptable for use by holders of licenses in complying with the NRC's Decommissioning Planning Rule (DPR) (76 FR...

77 FR 41107 - Decommissioning Planning During Operations

Federal Register 2010, 2011, 2012, 2013, 2014

2012-07-12

..., 40, 50, 70, and 72 [NRC-2011-0162] Decommissioning Planning During Operations AGENCY: Nuclear... (DG) 4014, ``Decommissioning Planning During Operations.'' This guide describes a method that the NRC staff considers acceptable for use in complying with the NRC's Decommissioning Planning Rule. The NRC...

75 FR 8147 - Notice of Consideration of Amendment Request for Decommissioning of Analytical Bio-Chemistry...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-02-23

... NUCLEAR REGULATORY COMMISSION [Docket No. 030-05154; NRC-2010-0056] Notice of Consideration of Amendment Request for Decommissioning of Analytical Bio-Chemistry Laboratories, Inc. Sanitary Lagoon... license amendment to Byproduct Material License No. 24- 13365-01 issued to Analytical Bio-Chemistry...

78 FR 64028 - Decommissioning of Nuclear Power Reactors

Federal Register 2010, 2011, 2012, 2013, 2014

2013-10-25

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0035] Decommissioning of Nuclear Power Reactors AGENCY... Commission (NRC) is issuing Revision 1 of regulatory guide (RG) 1.184 ``Decommissioning of Nuclear Power... the NRC's regulations relating to the decommissioning process for nuclear power reactors. The revision...

76 FR 23339 - Notice of Issuance of License Amendment Regarding Decommission Plan Approval; University of...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-04-26

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-113; NRC-2009-0549] Notice of Issuance of License Amendment Regarding Decommission Plan Approval; University of Arizona Research Reactor The U.S. Nuclear... located within the University of Arizona Nuclear Reactor Laboratory (NRL) on the 325-acre campus of the...

26 CFR 1.88-1 - Nuclear decommissioning costs.

Code of Federal Regulations, 2011 CFR

2011-04-01

... 26 Internal Revenue 2 2011-04-01 2011-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning costs...

26 CFR 1.88-1 - Nuclear decommissioning costs.

Code of Federal Regulations, 2013 CFR

2013-04-01

... 26 Internal Revenue 2 2013-04-01 2013-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning costs...

26 CFR 1.88-1 - Nuclear decommissioning costs.

Code of Federal Regulations, 2012 CFR

2012-04-01

... 26 Internal Revenue 2 2012-04-01 2012-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning costs...

26 CFR 1.88-1 - Nuclear decommissioning costs.

Code of Federal Regulations, 2010 CFR

2010-04-01

... 26 Internal Revenue 2 2010-04-01 2010-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning costs...

26 CFR 1.88-1 - Nuclear decommissioning costs.

Code of Federal Regulations, 2014 CFR

2014-04-01

... 26 Internal Revenue 2 2014-04-01 2014-04-01 false Nuclear decommissioning costs. 1.88-1 Section 1... (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.88-1 Nuclear decommissioning costs. (a) In general. Section 88 provides that the amount of nuclear decommissioning costs...

Progress in Decommissioning of Ignalina NPP Unit 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ancius, Darius; Krenevicius, Rimantas; Kutas, Saulius

2002-07-01

The aim of the paper is to present the Lithuanian legal framework regarding the nuclear safety in Decommissioning and Waste Management, and the progress in the Decommissioning Programme of the unit 1 of Ignalina Nuclear Power Plant (INPP). INPP is the only nuclear plant in Lithuania. It comprises two RBMK-1500 reactors. After Lithuania has restored its independence, responsibility for Ignalina NPP was transferred to the Republic of Lithuania. To ensure the control of the Nuclear Safety in Lithuania, The State Nuclear Power Safety Inspectorate (VATESI) was created on 18 October 1991, by a resolution of the Lithuanian Government. Significant workmore » has been performed over the last decade, aiming at upgrading the safety level of the Ignalina NPP with reference to the International standards. On 5 October 1999 the Seimas (Parliament) adopted the National Energy Strategy: It has been decided that unit 1 of Ignalina NPP will be closed down before 2005, The conditions and precise final date of the decommissioning of Unit 2 will be stated in the updated National Energy strategy in 2004. On 20-21 June 2000, the International Donors' Conference for the Decommissioning of Ignalina NPP took place in Vilnius. More than 200 Millions Euro were pledged of which 165 M funded directly from the European Union's budget, as financial support to the Decommissioning projects. The Decommissioning Program encompasses legal, organizational, financial and technical means including the social and economical impacts in the region of Ignalina. The Program is financed from International Support Fund, State budget, National Decommissioning Fund of Ignalina NPP and other funds. Decommissioning of Ignalina NPP is subject to VATESI license according to the Law on Nuclear Energy. The Government established the licensing procedure in the so-called 'Procedure for licensing of Nuclear Activities'; and the document 'General Requirements for Decommissioning of the Ignalina NPP' has been issued by

77 FR 8751 - Guidance for Decommissioning Planning During Operations

Federal Register 2010, 2011, 2012, 2013, 2014

2012-02-15

..., 40, 50, 70, and 72 [NRC-2011-0286] Guidance for Decommissioning Planning During Operations AGENCY... Guide, DG-4014, ``Decommissioning Planning During Operations'' in the Federal Register with a public... Guide DG-4014, ``Decommissioning Planning During Operations.'' This DG refers to NUREG-1757 Volume 3...

30 CFR 585.907 - How will BOEM process my decommissioning application?

Code of Federal Regulations, 2012 CFR

2012-07-01

..., COPs and GAPs Decommissioning Applications § 585.907 How will BOEM process my decommissioning... your decommissioning application with the decommissioning general concept in your approved SAP, COP, or... revise your SAP, COP, or GAP, and BOEM will begin the appropriate NEPA analysis and other regulatory...

Risk-based Prioritization of Facility Decommissioning and Environmental Restoration Projects in the National Nuclear Legacy Liabilities Program at the Chalk River Laboratory - 13564

DOE Office of Scientific and Technical Information (OSTI.GOV)

Nelson, Jerel G.; Kruzic, Michael; Castillo, Carlos

2013-07-01

Chalk River Laboratory (CRL), located in Ontario Canada, has a large number of remediation projects currently in the Nuclear Legacy Liabilities Program (NLLP), including hundreds of facility decommissioning projects and over one hundred environmental remediation projects, all to be executed over the next 70 years. Atomic Energy of Canada Limited (AECL) utilized WorleyParsons to prioritize the NLLP projects at the CRL through a risk-based prioritization and ranking process, using the WorleyParsons Sequencing Unit Prioritization and Estimating Risk Model (SUPERmodel). The prioritization project made use of the SUPERmodel which has been previously used for other large-scale site prioritization and sequencing ofmore » facilities at nuclear laboratories in the United States. The process included development and vetting of risk parameter matrices as well as confirmation/validation of project risks. Detailed sensitivity studies were also conducted to understand the impacts that risk parameter weighting and scoring had on prioritization. The repeatable prioritization process yielded an objective, risk-based and technically defendable process for prioritization that gained concurrence from all stakeholders, including Natural Resources Canada (NRCan) who is responsible for the oversight of the NLLP. (authors)« less

26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

Code of Federal Regulations, 2013 CFR

2013-04-01

... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of this...

26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

Code of Federal Regulations, 2011 CFR

2011-04-01

... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of this...

26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

Code of Federal Regulations, 2014 CFR

2014-04-01

... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of this...

26 CFR 1.468A-4 - Treatment of nuclear decommissioning fund.

Code of Federal Regulations, 2012 CFR

2012-04-01

... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Treatment of nuclear decommissioning fund. 1...-4 Treatment of nuclear decommissioning fund. (a) In general. A nuclear decommissioning fund is... by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes of this...

The Regulatory Challenges of Decommissioning Nuclear Power Plants in Korea - 13101

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lee, Jungjoon; Ahn, Sangmyeon; Choi, Kyungwoo

As of 2012, 23 units of nuclear power plants are in operation, but there is no experience of permanent shutdown and decommissioning of nuclear power plant in Korea. It is realized that, since late 1990's, improvement of the regulatory framework for decommissioning has been emphasized constantly from the point of view of International Atomic Energy Agency (IAEA)'s safety standards. And it is known that now IAEA prepare the safety requirement on decommissioning of facilities, its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA's Integrated Regulatory Review Service (IRRS) mission tomore » Korea in 2011, it was recommended that the regulatory framework for decommissioning should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became also important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we identify the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA's safety standards in order to achieve our goal. And then the plan is to be established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. After dealing with it, it is expected that the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards. (authors)« less

When a plant shuts down: The psychology of decommissioning

DOE Office of Scientific and Technical Information (OSTI.GOV)

Schulz, J.; Crawford, A.C.

Within the next decade, 10 to 25 nuclear plants in the United States may be taken off line. Many will have reached the end of their 40-year life cycles, but others will be retired because the cost of operating them has begun to outweigh their economic benefit. Such was the case at Fort St. Vrain, the first decommissioning of a US commercial plant under new Nuclear Regulatory Commission (NRC) regulations. Two major problems associated with decommissioning plants have been obvious: (1) the technical challenges and costs of decommissioning, and (2) the cost of maintaining and finally decommissioning a plant aftermore » a safe storage (SAFSTOR) period of approximately 60 years. What has received little attention is the challenge that affects not only the people who make a plant work, but the quality of the solutions to these problems: how to maintain effective organizational performance during the process of downsizing and decommissioning and/or SAFSTOR. The quality of technical solutions for closing a plant, as well as how successfully the decommissioning process is held within or below budget, will depend largely on how effectively the nuclear organization functions as a social unit. Technical and people issues are bound together. The difficulty is how to operate a plant effectively when plant personnel have no sense of long-term security. As the nuclear power industry matures and the pace for closing operating plants accelerates, the time has come to prepare for the widespread decommissioning of plants. The industry would be well served by conducting a selective, industry-wide evaluation of plants to assess its overall readiness for the decommissioning process. A decommissioning is not likely to be trouble free, but with a healthy appreciation for the human side of the process, it will undoubtedly go more smoothly than if approached as a matter of dismantling a machine.« less

Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

DOE Office of Scientific and Technical Information (OSTI.GOV)

Zull, Lawrence M.; Yeniscavich, William

2008-01-15

The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive materialmore » contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites.« less

Decommissioning of the Iraq former nuclear complex

DOE Office of Scientific and Technical Information (OSTI.GOV)

Abbas, Mohammed; Helou, Tuama; Ahmead, Bushra

2007-07-01

Available in abstract form only. Full text of publication follows: A number of sites in Iraq have some degree of radiological contamination and require decommissioning and remediation in order to ensure radiological safety. Many of these sites in Iraq are located at the nuclear research centre at Al Tuwaitha. The International Atomic Energy Agency (IAEA) Board of Governors has approved a project to assist the Government of Iraq in the evaluation and decommissioning of former facilities that used radioactive materials. The project is divided into three phases: Phase 1: collect and analyze all available data and conduct training of themore » Iraqi staff, Phase 2: develop a decommissioning and remediation plan, and Phase 3: implement field activities relating to decommissioning, remediation and site selection suitable for final disposal of waste. Four working groups have been established to complete the Phase 1 work and significant progress has been made in drafting a new nuclear law which will provide the legal basis for the licensing of the decommissioning of the former nuclear complex. Work is also underway to collect and analysis existing date, to prioritize future activities and to develop a waste management strategy. This will be a long-term and costly project. (authors)« less

Progress in Decommissioning the Humboldt Bay Power Plant - 13604

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rod, Kerry; Shelanskey, Steven K.; Kristofzski, John

Decommissioning of the Pacific Gas and Electric (PG and E) Company Humboldt Bay Power Plant (HBPP) Unit 3 nuclear facility has now, after more than three decades of SAFSTOR and initial decommissioning work, transitioned to full-scale decommissioning. Decommissioning activities to date have been well orchestrated and executed in spite of an extremely small work site with space constricted even more by other concurrent on-site major construction projects including the demolition of four fossil units, construction of a new generating station and 60 KV switchyard upgrade. Full-scale decommissioning activities - now transitioning from Plant Systems Removal (PG and E self-perform) tomore » Civil Works Projects (contractor performed) - are proceeding in a safe, timely, and cost effective manner. As a result of the successful decommissioning work to date (approximately fifty percent completed) and the intense planning and preparations for the remaining work, there is a high level of confidence for completion of all HBPP Unit 3 decommissions activities in 2018. Strategic planning and preparations to transition into full-scale decommissioning was carried out in 2008 by a small, highly focused project team. This planning was conducted concurrent with other critical planning requirements such as the loading of spent nuclear fuel into dry storage at the Independent Spent Fuel Storage Installation (ISFSI) finishing December 2008. Over the past four years, 2009 through 2012, the majority of decommissioning work has been installation of site infrastructure and removal of systems and components, known as the Plant System Removal Phase, where work scope was dynamic with significant uncertainty, and it was self-performed by PG and E. As HBPP Decommissioning transitions from the Plant System Removal Phase to the Civil Works Projects Phase, where work scope is well defined, a contracting plan similar to that used for Fossil Decommissioning will be implemented. Award of five major

10 CFR 70.25 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2013 CFR

2013-01-01

... this section shall submit a decommissioning funding plan as described in paragraph (e) of this section... quantities set forth in appendix B to part 30. A decommissioning funding plan must also be submitted when a... quantities specified in paragraph (d) of this section shall either— (1) Submit a decommissioning funding plan...

10 CFR 70.25 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2014 CFR

2014-01-01

... this section shall submit a decommissioning funding plan as described in paragraph (e) of this section... quantities set forth in appendix B to part 30. A decommissioning funding plan must also be submitted when a... quantities specified in paragraph (d) of this section shall either— (1) Submit a decommissioning funding plan...

10 CFR 30.35 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2013 CFR

2013-01-01

... set forth in appendix B to part 30 shall submit a decommissioning funding plan as described in paragraph (e) of this section. The decommissioning funding plan must also be submitted when a combination of... funding plan as described in paragraph (e) of this section. The decommissioning funding plan must be...

10 CFR 30.35 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2014 CFR

2014-01-01

... set forth in appendix B to part 30 shall submit a decommissioning funding plan as described in paragraph (e) of this section. The decommissioning funding plan must also be submitted when a combination of... funding plan as described in paragraph (e) of this section. The decommissioning funding plan must be...

10 CFR 30.35 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2011 CFR

2011-01-01

... set forth in appendix B to part 30 shall submit a decommissioning funding plan as described in paragraph (e) of this section. The decommissioning funding plan must also be submitted when a combination of... funding plan as described in paragraph (e) of this section. The decommissioning funding plan must be...

10 CFR 70.25 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2011 CFR

2011-01-01

... this section shall submit a decommissioning funding plan as described in paragraph (e) of this section... quantities set forth in appendix B to part 30. A decommissioning funding plan must also be submitted when a... quantities specified in paragraph (d) of this section shall either— (1) Submit a decommissioning funding plan...

10 CFR 70.25 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2012 CFR

2012-01-01

... this section shall submit a decommissioning funding plan as described in paragraph (e) of this section... quantities set forth in appendix B to part 30. A decommissioning funding plan must also be submitted when a... quantities specified in paragraph (d) of this section shall either— (1) Submit a decommissioning funding plan...

Shippingport station decommissioning project ALARA Program

DOE Office of Scientific and Technical Information (OSTI.GOV)

Crimi, F.P.

1995-03-01

Properly planned and implemented ALARA programs help to maintain nuclear worker radiation exposures {open_quotes}As Low As Reasonably Achievable.{close_quotes}. This paper describes the ALARA program developed and implemented for the decontamination and decommissioning (D&D) of the Shippingport Atomic Power Station. The elements required for a successful ALARA program are discussed along with examples of good ALARA practices. The Shippingport Atomic Power Station (SAPS) was the first commercial nuclear power plant to be built in the United States. It was located 35 miles northwest of Pittsburgh, PA on the south bank of the Ohio river. The reactor plant achieved initial criticality inmore » December 1959. During its 25-year life, it produced 7.5 billion kilowatts of electricity. The SAPS was shut down in October 1982 and was the first large-scale U.S. nuclear power plant to be totally decommissioned and the site released for unrestricted use. The Decommission Project was estimated to take 1,007 man-rem of radiation exposure and $.98.3 million to complete. Physical decommissioning commenced in September 1985 and was completed in September 1989. The actual man-rem of exposure was 155. The project was completed 6 months ahead of schedule at a cost of $91.3 million.« less

Modelling of nuclear power plant decommissioning financing.

PubMed

Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

2015-06-01

Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Optimal policies for aggregate recycling from decommissioned forest roads.

PubMed

Thompson, Matthew; Sessions, John

2008-08-01

To mitigate the adverse environmental impact of forest roads, especially degradation of endangered salmonid habitat, many public and private land managers in the western United States are actively decommissioning roads where practical and affordable. Road decommissioning is associated with reduced long-term environmental impact. When decommissioning a road, it may be possible to recover some aggregate (crushed rock) from the road surface. Aggregate is used on many low volume forest roads to reduce wheel stresses transferred to the subgrade, reduce erosion, reduce maintenance costs, and improve driver comfort. Previous studies have demonstrated the potential for aggregate to be recovered and used elsewhere on the road network, at a reduced cost compared to purchasing aggregate from a quarry. This article investigates the potential for aggregate recycling to provide an economic incentive to decommission additional roads by reducing transport distance and aggregate procurement costs for other actively used roads. Decommissioning additional roads may, in turn, result in improved aquatic habitat. We present real-world examples of aggregate recycling and discuss the advantages of doing so. Further, we present mixed integer formulations to determine optimal levels of aggregate recycling under economic and environmental objectives. Tested on an example road network, incorporation of aggregate recycling demonstrates substantial cost-savings relative to a baseline scenario without recycling, increasing the likelihood of road decommissioning and reduced habitat degradation. We find that aggregate recycling can result in up to 24% in cost savings (economic objective) and up to 890% in additional length of roads decommissioned (environmental objective).

The regulatory framework for safe decommissioning of nuclear power plants in Korea

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sangmyeon Ahn; Jungjoon Lee; Chanwoo Jeong

We are having 23 units of nuclear power plants in operation and 5 units of nuclear power plants under construction in Korea as of September 2012. However, we don't have any experience on shutdown permanently and decommissioning of nuclear power plants. There are only two research reactors being decommissioned since 1997. It is realized that improvement of the regulatory framework for decommissioning of nuclear facilities has been emphasized constantly from the point of view of IAEA's safety standards. It is also known that IAEA will prepare the safety requirement on decommissioning of facilities; its title is the Safe Decommissioning ofmore » Facilities, General Safety Requirement Part 6. According to the result of IAEA's Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we focus on identifying the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA's safety standards in order to achieve our goal. And then the plan is established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. It is expected that if the things will go forward as planned, the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards. (authors)« less

Decommissioning of the TRIGA mark II and III and radioactive waste management

DOE Office of Scientific and Technical Information (OSTI.GOV)

Doo Seong Hwang; Yoon Ji Lee; Gyeong Hwan Chung

2013-07-01

KAERI has carried out decommissioning projects for two research reactors (KRR-1 and 2). The decommissioning project of KRR-1 (TRIGA Mark II) and 2 (TRIGA Mark III) was launched in 1997 with a total budget of 23.25 million US dollars. KRR-2 and all auxiliary facilities were already decommissioned, and KRR-1 is being decommissioned now. Much more dismantled waste is generated than in any other operations of nuclear facilities. Thus, the waste needs to be reduced and stabilized through decontamination or treatment before disposal. This paper introduces the current status of the decommissioning projects and describes the volume reduction and conditioning ofmore » decommissioning waste for final disposal. (authors)« less

Sandia, California Tritium Research Laboratory transition and reutilization project

DOE Office of Scientific and Technical Information (OSTI.GOV)

Garcia, T.B.

1997-02-01

This paper describes a project within Sandia National Laboratory to convert the shut down Tritium Research Laboratory into a facility which could be reused within the laboratory complex. In the process of decommissioning and decontaminating the facility, the laboratory was able to save substantial financial resources by transferring much existing equipment to other DOE facilities, and then expeditiously implementing a decontamination program which has resulted in the building being converted into laboratory space for new lab programs. This project of facility reuse has been a significant financial benefit to the laboratory.

26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

Code of Federal Regulations, 2012 CFR

2012-04-01

... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In general...

26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

Code of Federal Regulations, 2013 CFR

2013-04-01

... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In general...

26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

Code of Federal Regulations, 2014 CFR

2014-04-01

... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In general...

26 CFR 1.468A-1 - Nuclear decommissioning costs; general rules.

Code of Federal Regulations, 2011 CFR

2011-04-01

... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Nuclear decommissioning costs; general rules. 1...-1 Nuclear decommissioning costs; general rules. (a) Introduction. Section 468A provides an elective method for taking into account nuclear decommissioning costs for Federal income tax purposes. In general...

26 CFR 1.468A-4T - Treatment of nuclear decommissioning fund (temporary).

Code of Federal Regulations, 2010 CFR

2010-04-01

... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Treatment of nuclear decommissioning fund...-4T Treatment of nuclear decommissioning fund (temporary). (a) In general. A nuclear decommissioning... income earned by the assets of the nuclear decommissioning fund. (b) Modified gross income. For purposes...

77 FR 14047 - Guidance for Decommissioning Planning During Operations

Federal Register 2010, 2011, 2012, 2013, 2014

2012-03-08

...)-4014, ``Decommissioning Planning During Operations.'' This action is necessary to correct the NRC's... NUCLEAR REGULATORY COMMISSION [NRC-2011-0286] Guidance for Decommissioning Planning During Operations AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; correction. SUMMARY: The U...

Decommissioning: Nuclear Power's Missing Link. Worldwatch Paper 69.

ERIC Educational Resources Information Center

Pollock, Cynthia

The processes and associated dilemmas of nuclear power plant decommissioning are reviewed in this publication. Decommissioning involves the clearing up and disposal of a retired nuclear plant and its equipment of such a way as to safeguard the public from the dangers of radioactivity. Related problem areas are identified and include: (1) closure…

Technology, safety, and costs of decommissioning reference nuclear research and test reactors: sensitivity of decommissioning radiation exposure and costs to selected parameters

DOE Office of Scientific and Technical Information (OSTI.GOV)

Konzek, G.J.

1983-07-01

Additional analyses of decommissioning at the reference research and test (R and T) reactors and analyses of five recent reactor decommissionings are made that examine some parameters not covered in the initial study report (NUREG/CR-1756). The parameters examined for decommissioning are: (1) the effect on costs and radiation exposure of plant size and/or type; (2) the effects on costs of increasing disposal charges and of unavailability of waste disposal capacity at licensed waste disposal facilities; and (3) the costs of and the available alternatives for the disposal of nuclear R and T reactor fuel assemblies.

The Optimized Integration of the Decontamination Plan and the Radwaste Management Plan into Decommissioning Plan to the VVR-S Research Reactor from Romania

DOE Office of Scientific and Technical Information (OSTI.GOV)

Barariu, G.

2008-07-01

The paper presents the progress of the Decontamination Plan and Radioactive Waste Management Plan which accompanies the Decommissioning Plan for research reactor VVR-S located in Magurele, Ilfov, near Bucharest, Romania. The new variant of the Decommissioning Plan was elaborated taking into account the IAEA recommendation concerning radioactive waste management. A new feasibility study for VVR-S decommissioning was also elaborated. The preferred safe management strategy for radioactive wastes produced by reactor decommissioning is outlined. The strategy must account for reactor decommissioning, as well as rehabilitation of the existing Radioactive Waste Treatment Plant and the upgrade of the Radioactive Waste Disposal Facilitymore » at Baita-Bihor. Furthermore, the final rehabilitation of the laboratories and reusing of cleaned reactor building is envisaged. An inventory of each type of radioactive waste is presented. The proposed waste management strategy is selected in accordance with the IAEA assistance. Environmental concerns are a part of the radioactive waste management strategy. In conclusion: The current version 8 of the Draft Decommissioning Plan which include the Integrated concept of Decontamination and Decommissioning and Radwaste Management, reflects the substantial work that has been incorporated by IFIN-HH in collaboration with SITON, which has resulted in substantial improvement in document The decommissioning strategy must take into account costs for VVR-S Reactor decommissioning, as well as costs for much needed refurbishments to the radioactive waste treatment plant and the Baita-Bihor waste disposal repository. Several improvements to the Baita-Bihor repository and IFIN-HH waste treatment facility were proposed. The quantities and composition of the radioactive waste generated by VVR-S Reactor dismantling were again estimated by streams and the best demonstrated practicable processing solution was proposed. The estimated quantities of

TES Instrument Decommissioning

Atmospheric Science Data Center

2018-03-20

TES Instrument Decommissioning Tuesday, March 20, 2018 ... PST during a scheduled real time satellite contact the TES IOT along with the Aura FOT commanded the TES instrument to its ... generated from an algorithm update to the base Ground Data System software and will be made available to the scientific community in the ...

76 FR 3540 - Proposed Generic Communications Reporting for Decommissioning Funding Status Reports

Federal Register 2010, 2011, 2012, 2013, 2014

2011-01-20

...-2010-0366] Proposed Generic Communications Reporting for Decommissioning Funding Status Reports AGENCY... and present to the NRC in the Decommissioning Funding Status reports to ensure that the NRC staff... Regulatory Issue Summary 2010-XXX, ``10 CFR 50-75, Reporting for Decommissioning Funding Status Reports'' is...

Radiochemistry Lab Decommissioning and Dismantlement. AECL, Chalk River Labs, Ontario, Canada

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kenny, Stephen

2008-01-15

Atomic Energy of Canada (AECL) was originally founded in the mid 1940's to perform research in radiation and nuclear areas under the Canadian Defense Department. In the mid 50's The Canadian government embarked on several research and development programs for the development of the Candu Reactor. AECL was initially built as a temporary site and is now faced with many redundant buildings. Prior to 2004 small amounts of Decommissioning work was in progress. Many reasons for deferring decommissioning activities were used with the predominant ones being: 1. Reduction in radiation doses to workers during the final dismantlement, 2. Development ofmore » a long-term solution for the management of radioactive wastes in Canada, 3. Financial constraints presented by the number of facilities shutdown that would require decommissioning funds and the absence of an approved funding strategy. This has led to the development of a comprehensive decommissioning plan that is all inclusive of AECL's current and legacy liabilities. Canada does not have a long-term disposal site; therefore waste minimization becomes the driving factor behind decontamination for decommissioning before and during dismantlement. This decommissioning job was a great learning experience for decommissioning and the associated contractors who worked on this project. Throughout the life of the project there was a constant focus on waste minimization. This focus was constantly in conflict with regulatory compliance primarily with respect to fire regulations and protecting the facility along with adjacent facilities during the decommissioning activities. Discrepancies in historical documents forced the project to treat every space as a contaminated space until proven differently. Decommissioning and dismantlement within an operating site adds to the complexity of the tasks especially when it is being conducted in the heart of the plant. This project was very successful with no lost time accidents in over one

Development of Safety Assessment Code for Decommissioning of Nuclear Facilities

NASA Astrophysics Data System (ADS)

Shimada, Taro; Ohshima, Soichiro; Sukegawa, Takenori

A safety assessment code, DecDose, for decommissioning of nuclear facilities has been developed, based on the experiences of the decommissioning project of Japan Power Demonstration Reactor (JPDR) at Japan Atomic Energy Research Institute (currently JAEA). DecDose evaluates the annual exposure dose of the public and workers according to the progress of decommissioning, and also evaluates the public dose at accidental situations including fire and explosion. As for the public, both the internal and the external doses are calculated by considering inhalation, ingestion, direct radiation from radioactive aerosols and radioactive depositions, and skyshine radiation from waste containers. For external dose for workers, the dose rate from contaminated components and structures to be dismantled is calculated. Internal dose for workers is calculated by considering dismantling conditions, e.g. cutting speed, cutting length of the components and exhaust velocity. Estimation models for dose rate and staying time were verified by comparison with the actual external dose of workers which were acquired during JPDR decommissioning project. DecDose code is expected to contribute the safety assessment for decommissioning of nuclear facilities.

Northrop Triga facility decommissioning plan versus actual results

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gardner, F.W.

1986-01-01

This paper compares the Triga facility decontamination and decommissioning plan to the actual results and discusses key areas where operational activities were impacted upon by the final US Nuclear Regulatory Commission (NRC)-approved decontamination and decommissioning plan. Total exposures for fuel transfer were a factor of 4 less than planned. The design of the Triga reactor components allowed the majority of the components to be unconditionally released.

Asset Decommissioning Risk Metrics for Floating Structures in the Gulf of Mexico.

PubMed

Kaiser, Mark J

2015-08-01

Public companies in the United States are required to report standardized values of their proved reserves and asset retirement obligations on an annual basis. When compared, these two measures provide an aggregate indicator of corporate decommissioning risk but, because of their consolidated nature, cannot readily be decomposed at a more granular level. The purpose of this article is to introduce a decommissioning risk metric defined in terms of the ratio of the expected value of an asset's reserves to its expected cost of decommissioning. Asset decommissioning risk (ADR) is more difficult to compute than a consolidated corporate risk measure, but can be used to quantify the decommissioning risk of structures and to perform regional comparisons, and also provides market signals of future decommissioning activity. We formalize two risk metrics for decommissioning and apply the ADR metric to the deepwater Gulf of Mexico (GOM) floater inventory. Deepwater oil and gas structures are expensive to construct, and at the end of their useful life, will be expensive to decommission. The value of proved reserves for the 42 floating structures in the GOM circa January 2013 is estimated to range between $37 and $80 billion for future oil prices between 60 and 120 $/bbl, which is about 10 to 20 times greater than the estimated $4.3 billion to decommission the inventory. Eni's Allegheny and MC Offshore's Jolliet tension leg platforms have ADR metrics less than one and are approaching the end of their useful life. Application of the proposed metrics in the regulatory review of supplemental bonding requirements in the U.S. Outer Continental Shelf is suggested to complement the current suite of financial metrics employed. © 2015 Society for Risk Analysis.

77 FR 8902 - Draft Regulatory Guide: Issuance, Availability Decommissioning of Nuclear Power Reactors

Federal Register 2010, 2011, 2012, 2013, 2014

2012-02-15

... Decommissioning of Nuclear Power Reactors AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide... draft regulatory guide (DG) DG-1271 ``Decommissioning of Nuclear Power Reactors.'' This guide describes... Regulatory Guide 1.184, ``Decommissioning of Nuclear Power Reactors,'' dated July 2000. This proposed...

Sensor Network Demonstration for In Situ Decommissioning - 13332

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lagos, L.; Varona, J.; Awwad, A.

2013-07-01

Florida International University's (FIU's) Applied Research Center is currently supporting the Department of Energy's (DOE) Environmental Management Office of D and D and Facility Engineering program. FIU is supporting DOE's initiative to improve safety, reduce technical risks, and limit uncertainty within D and D operations by identifying technologies suitable to meet specific facility D and D requirements, assessing the readiness of those technologies for field deployment, and conducting feasibility studies and large scale demonstrations of promising technologies. During FY11, FIU collaborated with Savannah River National Laboratory in the development of an experimental test site for the demonstration of multiple sensormore » systems for potential use in the in situ decommissioning process. In situ decommissioning is a process in which the above ground portion of a facility is dismantled and removed, and the underground portion is filled with a cementious material such as grout. In such a scenario, the question remains on how to effectively monitor the structural health of the grout (cracking, flexing, and sinking), as well as track possible migration of contaminants within and out of the grouted monolith. The right types of sensors can aid personnel in better understanding the conditions within the entombed structure. Without sensors embedded in and around the monolith, it will be very difficult to estimate structural integrity and contaminant transport. Yet, to fully utilize the appropriate sensors and the provided data, their performance and reliability must be evaluated outside a laboratory setting. To this end, a large scale experimental setup and demonstration was conducted at FIU. In order to evaluate a large suite of sensor systems, FIU personnel designed and purchased a pre-cast concrete open-top cube, which served as a mock-up of an in situ DOE decommissioned facility. The inside of the cube measures 10 ft x 10 ft x 8 ft. In order to ensure that the

Research reactor decommissioning experience - concrete removal and disposal -

DOE Office of Scientific and Technical Information (OSTI.GOV)

Manning, Mark R.; Gardner, Frederick W.

1990-07-01

Removal and disposal of neutron activated concrete from biological shields is the most significant operational task associated with research reactor decommissioning. During the period of 1985 thru 1989 Chem-Nuclear Systems, Inc. was the prime contractor for complete dismantlement and decommissioning of the Northrop TRIGA Mark F, the Virginia Tech Argonaut, and the Michigan State University TRIGA Mark I Reactor Facilities. This paper discusses operational requirements, methods employed, and results of the concrete removal, packaging, transport and disposal operations for these (3) research reactor decommissioning projects. Methods employed for each are compared. Disposal of concrete above and below regulatory release limitsmore » for unrestricted use are discussed. This study concludes that activated reactor biological shield concrete can be safely removed and buried under current regulations.« less

Decontamination, decommissioning, and vendor advertorial issue, 2006

DOE Office of Scientific and Technical Information (OSTI.GOV)

Agnihotri, Newal

2006-07-15

The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: NPP Krsko revised decommissioning program, by Vladimir Lokner and Ivica Levanat, APO d.o.o., Croatia, and Nadja Zeleznik and Irena Mele, ARAO, Slovenia; Supporting the renaissance, by Marilyn C. Kray, Exelon Nuclear; Outage world an engineer's delight, by Tom Chrisopher, Areva, NP Inc.; Optimizing refueling outages with R and D, by Ross Marcoot, GE Energy; and, A successful project, by Jim Lash, FirstEnergy.

Decommissioning the Romanian Water-Cooled Water-Moderated Research Reactor: New Environmental Perspective on the Management of Radioactive Waste

DOE Office of Scientific and Technical Information (OSTI.GOV)

Barariu, G.; Giumanca, R.

2006-07-01

Pre-feasibility and feasibility studies were performed for decommissioning of the water-cooled water-moderated research reactor (WWER) located in Bucharest - Magurele, Romania. Using these studies as a starting point, the preferred safe management strategy for radioactive wastes produced by reactor decommissioning is outlined. The strategy must account for reactor decommissioning, as well as for the rehabilitation of the existing Radioactive Waste Treatment Plant and for the upgrade of the Radioactive Waste Disposal Facility at Baita-Bihor. Furthermore, the final rehabilitation of the laboratories and ecological reconstruction of the grounds need to be provided for, in accordance with national and international regulations. Inmore » accordance with IAEA recommendations at the time, the pre-feasibility study proposed three stages of decommissioning. However, since then new ideas have surfaced with regard to decommissioning. Thus, taking into account the current IAEA ideology, the feasibility study proposes that decommissioning of the WWER be done in one stage to an unrestricted clearance level of the reactor building in an Immediate Dismantling option. Different options and the corresponding derived preferred option for waste management are discussed taking into account safety measures, but also considering technical, logistical and economic factors. For this purpose, possible types of waste created during each decommissioning stage are reviewed. An approximate inventory of each type of radioactive waste is presented. The proposed waste management strategy is selected in accordance with the recommended international basic safety standards identified in the previous phase of the project. The existing Radioactive Waste Treatment Plant (RWTP) from the Horia Hulubei Institute for Nuclear Physics and Engineering (IFIN-HH), which has been in service with no significant upgrade since 1974, will need refurbishing due to deterioration, as well as upgrading in order to

10 CFR 30.35 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2010 CFR

2010-01-01

... shall include a decommissioning funding plan in any application for license renewal. (3) Each holder of... not to exceed 3 years. The decommissioning funding plan must also contain a certification by the... until the Commission has terminated the license. (3) An external sinking fund in which deposits are made...

Decontamination and decommissioning of the BORAX-V leach pond. Final report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Smith, D.L.

1985-01-01

This report describes the decontamination and decommissioning (D and D) of the BORAX-V leach pond located at the Idaho National Engineering Laboratory (INEL). The leach pond became radioactively contaminated from the periodic discharge of low-level liquid waste during operation of the Boiling Water Reactor Experiments (BORAX) from 1954 to 1964. This report describes work performed to accomplish the D and D objectives of stabilizing the leach pond and preventing the spread of contamination. D and D of the BORAX-V leach pond consisted to backfilling the pond with clean soil, grading and seeding the area, and erecting a permanent marker tomore » identify very low-level subsurface contamination.« less

10 CFR 40.36 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2014 CFR

2014-01-01

... funding plan as described in paragraph (d) of this section. (b) Each applicant for a specific license... 100 mCi in a readily dispersible form shall either— (1) Submit a decommissioning funding plan as... this section shall submit a decommissioning funding plan as described in paragraph (d) of this section...

10 CFR 40.36 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2011 CFR

2011-01-01

... funding plan as described in paragraph (d) of this section. (b) Each applicant for a specific license... 100 mCi in a readily dispersible form shall either— (1) Submit a decommissioning funding plan as... this section shall submit a decommissioning funding plan as described in paragraph (d) of this section...

10 CFR 40.36 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2013 CFR

2013-01-01

... funding plan as described in paragraph (d) of this section. (b) Each applicant for a specific license... 100 mCi in a readily dispersible form shall either— (1) Submit a decommissioning funding plan as... this section shall submit a decommissioning funding plan as described in paragraph (d) of this section...

10 CFR 40.36 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2012 CFR

2012-01-01

... readily dispersible form shall submit a decommissioning funding plan as described in paragraph (d) of this...— (1) Submit a decommissioning funding plan as described in paragraph (d) of this section; or (2... funding plan as described in paragraph (d) of this section or a certification of financial assurance for...

Waste management strategy for cost effective and environmentally friendly NPP decommissioning

DOE Office of Scientific and Technical Information (OSTI.GOV)

Per Lidar; Arne Larsson; Niklas Bergh

2013-07-01

Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the designmore » basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named ndcon to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions

30 CFR 285.907 - How will MMS process my decommissioning application?

Code of Federal Regulations, 2011 CFR

2011-07-01

... application? 285.907 Section 285.907 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, REGULATION, AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE... compare your decommissioning application with the decommissioning general concept in your approved SAP...

2014 Idaho National Laboratory Water Use Report and Comprehensive Well Inventory (Revision 23)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lewis, Mike

This 2014 Idaho National Laboratory Water Use Report and Comprehensive Well Inventory (Revision 23) provides water use information for production and potable water wells at the Idaho National Laboratory for Calendar Year 2014. It also provides detailed information for new, modified, and decommissioned wells and holes. One new well was drilled and completed in Calendar Year 2014. No modifications were performed on any wells. No wells were decommissioned in Calendar Year 2014. Detailed construction information and a location map for the new well is provided. This report is being submitted in accordance with the Water Rights Agreement between the Statemore » of Idaho and the United States, for the United States Department of Energy (dated 1990), the subsequent Partial Decree for Water Right 34-10901 issued June 20, 2003, and the Final Unified Decree issued August 26, 2014.« less

30 CFR 585.907 - How will BOEM process my decommissioning application?

Code of Federal Regulations, 2014 CFR

2014-07-01

... decommissioning application with the decommissioning general concept in your approved SAP, COP, or GAP to..., COP, or GAP, and BOEM will begin the appropriate NEPA analysis and other regulatory reviews as... change in the impacts previously identified and evaluated in your SAP, COP, or GAP; (2) Require any...

30 CFR 585.907 - How will BOEM process my decommissioning application?

Code of Federal Regulations, 2013 CFR

2013-07-01

... decommissioning application with the decommissioning general concept in your approved SAP, COP, or GAP to..., COP, or GAP, and BOEM will begin the appropriate NEPA analysis and other regulatory reviews as... change in the impacts previously identified and evaluated in your SAP, COP, or GAP; (2) Require any...

Radioactive waste from decommissioning of fast reactors (through the example of BN-800)

NASA Astrophysics Data System (ADS)

Rybin, A. A.; Momot, O. A.

2017-01-01

Estimation of volume of radioactive waste from operating and decommissioning of fast reactors is introduced. Preliminary estimation has shown that the volume of RW from decommissioning of BN-800 is amounted to 63,000 cu. m. Comparison of the amount of liquid radioactive waste derived from operation of different reactor types is performed. Approximate costs of all wastes disposal for complete decommissioning of BN-800 reactor are estimated amounting up to approx. 145 million.

Comparative Evaluation of Cutting Methods of Activated Concrete from Nuclear Power Plant Decommissioning - 13548

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kim, HakSoo; Chung, SungHwan; Maeng, SungJun

2013-07-01

The amount of radioactive wastes from decommissioning of a nuclear power plant varies greatly depending on factors such as type and size of the plant, operation history, decommissioning options, and waste treatment and volume reduction methods. There are many methods to decrease the amount of decommissioning radioactive wastes including minimization of waste generation, waste reclassification through decontamination and cutting methods to remove the contaminated areas. According to OECD/NEA, it is known that the radioactive waste treatment and disposal cost accounts for about 40 percentage of the total decommissioning cost. In Korea, it is needed to reduce amount of decommissioning radioactivemore » waste due to high disposal cost, about $7,000 (as of 2010) per a 200 liter drum for the low- and intermediate-level radioactive waste (LILW). In this paper, cutting methods to minimize the radioactive waste of activated concrete were investigated and associated decommissioning cost impact was assessed. The cutting methods considered are cylindrical and volume reductive cuttings. The study showed that the volume reductive cutting is more cost-effective than the cylindrical cutting. Therefore, the volume reductive cutting method can be effectively applied to the activated bio-shield concrete. (authors)« less

30 CFR 285.913 - What happens if I fail to comply with my approved decommissioning application?

Code of Federal Regulations, 2010 CFR

2010-07-01

... approved decommissioning application? 285.913 Section 285.913 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF Decommissioning Compliance with An Approved Decommissioning Application § 285.913 What...

26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

Code of Federal Regulations, 2011 CFR

2011-04-01

... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. § 1.468A...

26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

Code of Federal Regulations, 2012 CFR

2012-04-01

... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. § 1.468A...

26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

Code of Federal Regulations, 2014 CFR

2014-04-01

... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. § 1.468A...

26 CFR 1.468A-0 - Nuclear decommissioning costs; table of contents.

Code of Federal Regulations, 2013 CFR

2013-04-01

... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Nuclear decommissioning costs; table of contents...-0 Nuclear decommissioning costs; table of contents. This section lists the paragraphs contained in.... (b) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. § 1.468A...

Reactor Decommissioning - Balancing Remote and Manual Activities - 12159

DOE Office of Scientific and Technical Information (OSTI.GOV)

Cole, Matt

2012-07-01

Nuclear reactors come in a wide variety of styles, size, and ages. However, during decommissioned one issue they all share is the balancing of remotely and manually activities. For the majority of tasks there is a desire to use manual methods because remote working can be slower, more expensive, and less reliable. However, because of the unique hazards of nuclear reactors some level of remote activity will be necessary to provide adequate safety to workers and properly managed and designed it does not need to be difficult nor expensive. The balance of remote versus manual work can also affect themore » amount and types of waste that is generated. S.A.Technology (SAT) has worked on a number of reactor decommissioning projects over the last two decades and has a range of experience with projects using remote methods to those relying primarily on manual activities. This has created a set of lessons learned and best practices on how to balance the need for remote handling and manual operations. Finding a balance between remote and manual operations on reactor decommissioning can be difficult but by following certain broad guidelines it is possible to have a very successfully decommissioning. It is important to have an integrated team that includes remote handling experts and that this team plans the work using characterization efforts that are efficient and realistic. The equipment need to be simple, robust and flexible and supported by an on-site team committed to adapting to day-to-day challenges. Also, the waste strategy needs to incorporate the challenges of remote activities in its planning. (authors)« less

30 CFR 585.908 - What must I include in my decommissioning notice?

Code of Federal Regulations, 2012 CFR

2012-07-01

... 30 Mineral Resources 2 2012-07-01 2012-07-01 false What must I include in my decommissioning notice? 585.908 Section 585.908 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, DEPARTMENT OF THE... determines that your decommissioning activities would: (1) Result in a significant change in the impacts...

Ecological and political issues surrounding decommissioning of offshore oil facilities in the Southern California Bight

USGS Publications Warehouse

Schroeder, Donna M.; Love, Milton S.

2004-01-01

To aid legislators, resource managers, and the general public, this paper summarizes and clarifies some of the issues and options that the federal government and the state of California face in decommissioning offshore oil and gas production platforms, particularly as these relate to platform ecology. Both local marine ecology and political climate play a role in decommissioning offshore oil production platforms. Compared to the relatively supportive political climate in the Gulf of Mexico for “rigs-to-reefs” programs, conflicting social values among stakeholders in Southern California increases the need for understanding ecological impacts of various decommissioning alternatives (which range from total removal to allowing some or all of platform structure to remain in the ocean). Additional scientific needs in the decommissioning process include further assessment of platform habitat quality, estimation of regional impacts of decommissioning alternatives to marine populations, and determination of biological effects of any residual contaminants. The principal management need is a ranking of environmental priorities (e.g. species-of-interest and marine habitats). Because considerable numbers of economically important species reside near oil platforms, National Oceanic and Atmospheric Administration Fisheries should consider the consequences of decommissioning alternatives in their overall management plans. Management strategies could include designating reefed platforms as marine protected areas. The overarching conclusion from both ecological and political perspectives is that decommissioning decisions should be made on a case-by-case basis.

Imp and Syp RNA-binding proteins govern decommissioning of Drosophila neural stem cells

PubMed Central

Yang, Ching-Po; Samuels, Tamsin J.; Huang, Yaling; Yang, Lu; Ish-Horowicz, David; Davis, Ilan

2017-01-01

The termination of the proliferation of Drosophila neural stem cells, also known as neuroblasts (NBs), requires a ‘decommissioning’ phase that is controlled in a lineage-specific manner. Most NBs, with the exception of those of the mushroom body (MB), are decommissioned by the ecdysone receptor and mediator complex, causing them to shrink during metamorphosis, followed by nuclear accumulation of Prospero and cell cycle exit. Here, we demonstrate that the levels of Imp and Syp RNA-binding proteins regulate NB decommissioning. Descending Imp and ascending Syp expression have been shown to regulate neuronal temporal fate. We show that Imp levels decline slower in the MB than in other central brain NBs. MB NBs continue to express Imp into pupation, and the presence of Imp prevents decommissioning partly by inhibiting the mediator complex. Late-larval induction of transgenic Imp prevents many non-MB NBs from decommissioning in early pupae. Moreover, the presence of abundant Syp in aged NBs permits Prospero accumulation that, in turn, promotes cell cycle exit. Together, our results reveal that progeny temporal fate and progenitor decommissioning are co-regulated in protracted neuronal lineages. PMID:28851709

Evaluation of short-rotation woody crops to stabilize a decommissioned swine lagoon

Treesearch

K.C. Dipesh; Rodney E. Will; Thomas C. Hennessey; Chad J. Penn

2012-01-01

Fast growing tree stands represent an environmentally friendly, less expensive method for stabilization of decommissioned animal production lagoons than traditional lagoon closure. We tested the feasibility of using short-rotation woody crops (SRWCs) in central Oklahoma to close a decommissioned swine lagoon by evaluating the growth performance and nutrient uptake of...

Decommissioning of the Northrop TRIGA reactor

DOE Office of Scientific and Technical Information (OSTI.GOV)

Cozens, George B.; Woo, Harry; Benveniste, Jack

1986-07-01

An overview of the administrative and operational aspects of decommissioning and dismantling the Northrop Mark F TRIGA Reactor, including: planning and preparation, personnel requirements, government interfacing, costs, contractor negotiations, fuel shipments, demolition, disposal of low level waste, final survey and disposition of the concrete biological shielding. (author)

30 CFR 285.913 - What happens if I fail to comply with my approved decommissioning application?

Code of Federal Regulations, 2011 CFR

2011-07-01

... 30 Mineral Resources 2 2011-07-01 2011-07-01 false What happens if I fail to comply with my... Decommissioning Application § 285.913 What happens if I fail to comply with my approved decommissioning application? If you fail to comply with your approved decommissioning plan or application: (a) The MMS may...

Alternatives evaluation and decommissioning study on shielded transfer tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

DOE Office of Scientific and Technical Information (OSTI.GOV)

DeVore, J.R.; Hinton, R.R.

1994-08-01

The shielded transfer tanks (STTs) are five obsolete cylindrical shipping casks which were used to transport high specific activity radioactive solutions by rail during the 1960s and early 1970s. The STTs are currently stored at the Oak Ridge National Laboratory under a shed roof. This report is an evaluation to determine the preferred alternative for the final disposition of the five STTs. The decommissioning alternatives assessed include: (1) the no action alternative to leave the STTs in their present location with continued surveillance and maintenance; (2) solidification of contents within the tanks and holding the STTs in long term retrievablemore » storage; (3) sale of one or more of the used STTs to private industry for use at their treatment facility with the remaining STTs processed as in Alternative 4; and (4) removal of tank contents for de-watering/retrievable storage, limited decontamination to meet acceptance criteria, smelting the STTs to recycle the metal through the DOE contaminated scrap metal program, and returning the shielding lead to the ORNL lead recovery program because the smelting contractor cannot reprocess the lead. To completely evaluate the alternatives for the disposition of the STTs, the contents of the tanks must be characterized. Shielding and handling requirements, risk considerations, and waste acceptance criteria all require that the radioactive inventory and free liquids residual in the STTs be known. Because characterization of the STT contents in the field was not input into a computer model to predict the probable inventory and amount of free liquid. The four alternatives considered were subjected to a numerical scoring procedure. Alternative 4, smelting the STTs to recycle the metal after removal/de-watering of the tank contents, had the highest score and is, therefore, recommended as the preferred alternative. However, if a buyer for one or more STT could be found, it is recommended that Alternative 3 be reconsidered.« less

Residual strength and stiffness of lumber from decommissioned chromated copper arsenate-treated southern pine utility poles

Treesearch

Cheng Piao; Leslie Groom

2010-01-01

The reusability of decommissioned treated wood is primarily dependent on the residual strength of the wood after service. Determining the residual strength can provide useful information for structural design and reuse of the decommissioned treated wood. This study evaluated the residual strength of decommissioned chromated copper arsenate–treated utility pole wood....

78 FR 49553 - Three Mile Island, Unit 2; Post Shutdown Decommissioning Activities Report

Federal Register 2010, 2011, 2012, 2013, 2014

2013-08-14

...On June 28, 2013, the GPU Nuclear Inc. (GPUN) submitted its Post Shutdown Decommissioning Activity Report (PSDAR) for Three Mile Island, Unit 2 (TMI-2). The PSDAR provides an overview of GPUN's proposed decommissioning activities, schedule, and costs for TMI-2. The NRC is requesting public comments on the PSDAR.

Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

DOE Office of Scientific and Technical Information (OSTI.GOV)

Larsson, Arne; Lidar, Per; Bergh, Niklas

2013-07-01

Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the designmore » basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions

Carbon-14 Bioassay for Decommissioning of Hanford Reactors

DOE Office of Scientific and Technical Information (OSTI.GOV)

Carbaugh, Eugene H.; Watson, David J.

2012-05-01

The old production reactors at the US Department of Energy Hanford Site used large graphite piles as the moderator. As part of long-term decommissioning plans, the potential need for 14C radiobioassay of workers was identified. Technical issues associated with 14C bioassay and worker monitoring were investigated, including anticipated graphite characterization, potential intake scenarios, and the bioassay capabilities that may be required to support the decommissioning of the graphite piles. A combination of urine and feces sampling would likely be required for the absorption type S 14C anticipated to be encountered. However the concentrations in the graphite piles appear to bemore » sufficiently low that dosimetrically significant intakes of 14C are not credible, thus rendering moot the need for such bioassay.« less

Carbon-14 bioassay for decommissioning of Hanford reactors.

PubMed

Carbaugh, Eugene H; Watson, David J

2012-05-01

The production reactors at the U.S. Department of Energy Hanford Site used large graphite piles as the moderator. As part of long-term decommissioning plans, the potential need for ¹⁴C radiobioassay of workers was identified. Technical issues associated with ¹⁴C bioassay and worker monitoring were investigated, including anticipated graphite characterization, potential intake scenarios, and the bioassay capabilities that may be required to support the decommissioning of the graphite piles. A combination of urine and feces sampling would likely be required for the absorption type S ¹⁴C anticipated to be encountered. However, the concentrations in the graphite piles appear to be sufficiently low that dosimetrically significant intakes of ¹⁴C are not credible, thus rendering moot the need for such bioassay.

78 FR 38739 - Standard Format and Content for Post-Shutdown Decommissioning Activities Report

Federal Register 2010, 2011, 2012, 2013, 2014

2013-06-27

...The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 of Regulatory Guide (RG) 1.185, ``Standard Format and Content for Post-shutdown Decommissioning Activities Report.'' This guide describes a method that the NRC staff considers acceptable for use in complying with the Commission's requirements regarding the submission of a post-shutdown decommissioning activities report (PSDAR).

77 FR 75198 - Standard Format and Content for Post-Shutdown Decommissioning Activities Report

Federal Register 2010, 2011, 2012, 2013, 2014

2012-12-19

...The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1272, ``Standard Format and Content for Post-shutdown Decommissioning Activities Report.'' This guide describes a method that the NRC staff considers acceptable for use in complying with the Commission's requirements regarding the submission of a post-shutdown decommissioning activities report (PSDAR).

Engineering Evaluation/Cost Analysis (EE/CA) for Decommissioning of TAN-607 Hot Shop Area

DOE Office of Scientific and Technical Information (OSTI.GOV)

J. P. Floerke

Test Area North (TAN) -607, the Technical Support Facility, is located at the north end of the Idaho National Laboratory (INL) Site. U.S. Department of Energy Idaho Operations Office (DOE-ID) is proposing to decommission the northern section of the TAN-607 facility, hereinafter referred to as TAN-607 Hot Shop Area, under a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) non-time-critical removal action (NTCRA). Despite significant efforts by the United States (U.S.) Department of Energy (DOE) to secure new business, no future mission has been identified for the TAN-607 Hot Shop Area. Its disposition has been agreed to by the Idahomore » State Historical Preservation Office documented in the Memorandum of Agreement signed October 2005 and it is therefore considered a surplus facility. A key element in DOE's strategy for surplus facilities is decommissioning to the maximum extent possible to ensure risk and building footprint reduction and thereby eliminating operations and maintenance cost. In addition, the DOE's 2006 Strategic Plan is ''complete cleanup of the contaminated nuclear weapons manufacturing and testing sites across the United States. DOE is responsible for the risk reduction and cleanup of the environmental legacy of the Nation's nuclear weapons program, one of the largest, most diverse, and technically complex environmental programs in the world. The Department will successfully achieve this strategic goal by ensuring the safety of the DOE employees and U.S. citizens, acquiring the best resources to complete the complex tasks, and managing projects throughout the United States in the most efficient and effective manner.'' TAN-607 is designated as a historical Signature Property by DOE Headquarters Advisory Council on Historic Preservation and, as such, public participation is required to determine the final disposition of the facility. The decommissioning action will place the TAN-607 Hot Shop Area in a final

The conceptual solutions concerning decommissioning and dismantling of Russian civil nuclear powered ships

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kulikov, Konstantin N.; Nizamutdinov, Rinat A.; Abramov, Andrey N.

From 1959 up to 1991 nine civil nuclear powered ships were built in Russia: eight ice-breakers and one lash lighter carrier (cargo ship). At the present time three of them were taking out of service: ice-breaker 'Lenin' is decommissioned as a museum and is set for storage in the port of Murmansk, nuclear ice-breakers 'Arktika' and 'Sibir' are berthing. The ice-breakers carrying rad-wastes appear to be a possible source of radiation contamination of Murmansk region and Kola Bay because the ship long-term storage afloat has the negative effect on hull's structures. As the result of this under the auspices ofmore » the Federal Targeted Program 'Nuclear and Radiation Safety of Russia for 2008 and the period until 2015' the conception and projects of decommissioning of nuclear-powered ships are developed by the State corporation Rosatom with the involvement of companies of United Shipbuilding Corporation. In developing the principal provisions of conception of decommissioning and dismantling of icebreakers the technical and economic assessment of dismantling options in ship-repairing enterprises of North-West of Russia was performed. The paper contains description of options, research procedure, analysis of options of decommissioning and dismantling of nuclear ice-breakers, taking into account the principle of optimization of potential radioactive effect to personnel, human population and environment. The report's conclusions contain the recommendations for selection of option for development of nuclear icebreaker decommissioning and dismantling projects. (authors)« less

76 FR 3837 - Nuclear Decommissioning Funds; Correction

Federal Register 2010, 2011, 2012, 2013, 2014

2011-01-21

... DEPARTMENT OF THE TREASURY Internal Revenue Service 26 CFR Part 1 [TD 9512] RIN 1545-BF08 Nuclear... trusts maintained for decommissioning nuclear power plants. DATES: This correction is effective on...: Sec. 1.468A-6 Disposition of an interest in a nuclear power plant. * * * * * (e) * * * (3...

30 CFR 585.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

Code of Federal Regulations, 2013 CFR

2013-07-01

... decommissioning for facilities authorized under my SAP, COP, or GAP? 585.902 Section 585.902 Mineral Resources... authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by BOEM under § 585.909, within 2... decommissioning the facilities under your SAP, COP, or GAP, you must submit a decommissioning application and...

30 CFR 585.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

Code of Federal Regulations, 2014 CFR

2014-07-01

... decommissioning for facilities authorized under my SAP, COP, or GAP? 585.902 Section 585.902 Mineral Resources... authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by BOEM under § 585.909, within 2... decommissioning the facilities under your SAP, COP, or GAP, you must submit a decommissioning application and...

Evaluation of Nuclear Facility Decommissioning Projects program: a reference test reactor. Project summary report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Boing, L.E.; Miller, R.L.

1983-10-01

This document presents, in summary form, generic conceptual information relevant to the decommissioning of a reference test reactor (RTR). All of the data presented were extracted from NUREG/CR-1756 and arranged in a form that will provide a basis for future comparison studies for the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program. During the data extraction process no attempt was made to challenge any of the assumptions used in the original studies nor was any attempt made to update assumed methods or processes to state-of-the-art decommissioning techniques. In a few instances obvious errors were corrected after consultation with the studymore » author.« less

Technical Aspects Regarding the Management of Radioactive Waste from Decommissioning of Nuclear Facilities

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dragolici, F.; Turcanu, C. N.; Rotarescu, G.

2003-02-25

The proper application of the nuclear techniques and technologies in Romania started in 1957, once with the commissioning of the Research Reactor VVR-S from IFIN-HH-Magurele. During the last 45 years, appear thousands of nuclear application units with extremely diverse profiles (research, biology, medicine, education, agriculture, transport, all types of industry) which used different nuclear facilities containing radioactive sources and generating a great variety of radioactive waste during the decommissioning after the operation lifetime is accomplished. A new aspect appears by the planning of VVR-S Research Reactor decommissioning which will be a new source of radioactive waste generated by decontamination, disassemblingmore » and demolition activities. By construction and exploitation of the Radioactive Waste Treatment Plant (STDR)--Magurele and the National Repository for Low and Intermediate Radioactive Waste (DNDR)--Baita, Bihor county, in Romania was solved the management of radioactive wastes arising from operation and decommissioning of small nuclear facilities, being assured the protection of the people and environment. The present paper makes a review of the present technical status of the Romanian waste management facilities, especially raising on treatment capabilities of ''problem'' wastes such as Ra-266, Pu-238, Am-241 Co-60, Co-57, Sr-90, Cs-137 sealed sources from industrial, research and medical applications. Also, contain a preliminary estimation of quantities and types of wastes, which would result during the decommissioning project of the VVR-S Research Reactor from IFIN-HH giving attention to some special category of wastes like aluminum, graphite and equipment, components and structures that became radioactive through neutron activation. After analyzing the technical and scientific potential of STDR and DNDR to handle big amounts of wastes resulting from the decommissioning of VVR-S Research Reactor and small nuclear facilities, the

Plant security during decommissioning; challenges and lessons learned from German phase out decision

DOE Office of Scientific and Technical Information (OSTI.GOV)

Renner, Andrea; Esch, Markus

2013-07-01

Purpose of this paper is to point out the security challenges that may occur during the decommissioning, based on the issues and lessons learned from the German phase out decision. Though national regulations may be different in other countries the basic problems and issues will be the same. Therefore presented solutions will be applicable in other countries as well. The radioactive material remaining at the NPP during decommissioning has the most influence on how the security measures have to be designed. The radioactive material defines the risk potential of the plant and this determines the needed security level. The followingmore » aspects have been challenging in Germany: - Scenarios varying from those, used for plants in operation, due to changed operating conditions - Spent fuel will stay in the spent fuel pool for a quite long period before it can be removed from the plant. Risk potential of the plant stays high and requires a high level of security measures - Security measures according to the existing operating license have to stay in place as they are, unless the first license for decommissioning is given respective the spent fuel is removed from the plant site. This even led to the question if improvements of security measures, planned and announced with focus on a plant remaining in operation for another couple of years, need to be done although they will not be required after removing the spent fuel from the plant. A further important aspect for the security design is the fact that a plant under decommissioning has completely different and strongly varying operating procedures, compared to the stable ones of an operating plant. This leads to different needs concerning workspace, infrastructure on plant site, access to buildings etc. An optimized and highly flexible security concept is needed to ensure an adequate level of security as well as an efficient decommissioning. A deep analysis of the vital plant functions, depending on the different

Evaluation of Nuclear Facility Decommissioning Projects program: a reference research reactor. Project summary report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Baumann, B.L.; Miller, R.L.

1983-10-01

This document presents, in summary form, generic conceptual information relevant to the decommissioning of a reference research reactor (RRR). All of the data presented were extracted from NUREG/CR-1756 and arranged in a form that will provide a basis for future comparison studies for the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program.

Renewables-to-reefs? - Decommissioning options for the offshore wind power industry.

PubMed

Smyth, Katie; Christie, Nikki; Burdon, Daryl; Atkins, Jonathan P; Barnes, Richard; Elliott, Michael

2015-01-15

The offshore wind power industry is relatively new but increasing globally, hence it is important that the whole life-cycle is managed. The construction-operation-decommissioning cycle is likely to take 20-30 years and whilst decommissioning may not be undertaken for many years, its management needs to be addressed in both current and future marine management regimes. This can be defined within a Drivers-Activities-Pressures-State Changes-Impacts (on human Welfare)-Responses framework. This paper considers the main decommissioning options - partial or complete removal of all components. A SWOT analysis shows environmental and economic benefits in partial as opposed to complete removal, especially if habitat created on the structures has conservation or commercial value. Benefits (and repercussions) are defined in terms of losses and gains of ecosystem services and societal benefits. The legal precedents and repercussions of both options are considered in terms of the 10-tenets of sustainable marine management. Finally a 'renewables-to-reefs' programme is proposed. Copyright © 2014 Elsevier Ltd. All rights reserved.

Action Memorandum for Decommissioning of TAN-607 Hot Shop Area

DOE Office of Scientific and Technical Information (OSTI.GOV)

M. A. Pinzel

The Department of Energy is documenting the selection of an alternative for the TAN-607 Hot Shop Area using a Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA). The scope of the removal action is limited to TAN-607 Hot Shop Area. An engineering evaluation/cost analysis (EE/CA) has assisted the Department of Energy Idaho Operations Office in identifuomg the most effective method for performing the decommissioning of this structure whose mission has ended. TAN-607 Hot Shop Area is located at Test Area North Technical Support Facility within the Idaho National Laboratory Site. The selected alternative consists of demolishing themore » TAN-607 aboveground structures and components, removing belowground noninert components (e.g. wood products), and removing the radiologically contaminated debris that does not meet remedial action objectives (RAOs), as defined in the Record of Decision Amendment for the V-Tanks and Explanation of Significant Differences for the PM-2A Tanks at Test Area North, Operable Unit 1-10.« less

Applying and adapting the Swedish regulatory system for decommissioning to nuclear power reactors - The regulator's perspective.

PubMed

Amft, Martin; Leisvik, Mathias; Carroll, Simon

2017-03-16

Half of the original 13 Swedish nuclear power reactors will be shut down by 2020. The decommissioning of these reactors is a challenge for all parties involved, including the licensees, the waste management system, the financing system, and the Swedish Radiation Safety Authority (SSM). This paper presents an overview of the Swedish regulations for decommissioning of nuclear facilities. It describes some of the experiences that SSM has gained from the application of these regulations. The focus of the present paper is on administrative aspects of decommissioning, such as SSM's guidelines, the definition of fundamental concepts in the regulatory framework, and a proposed revision of the licensing process according to the Environmental Act. These improvements will help to streamline the administration of the commercial nuclear power plant decommissioning projects that are anticipated to commence in Sweden in the near future. Copyright © 2017 Elsevier Ltd. All rights reserved.

18 CFR 2.24 - Project decommissioning at relicensing.

Code of Federal Regulations, 2010 CFR

2010-04-01

... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of General...

18 CFR 2.24 - Project decommissioning at relicensing.

Code of Federal Regulations, 2014 CFR

2014-04-01

... 18 Conservation of Power and Water Resources 1 2014-04-01 2014-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of General...

18 CFR 2.24 - Project decommissioning at relicensing.

Code of Federal Regulations, 2013 CFR

2013-04-01

... 18 Conservation of Power and Water Resources 1 2013-04-01 2013-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of General...

18 CFR 2.24 - Project decommissioning at relicensing.

Code of Federal Regulations, 2012 CFR

2012-04-01

... 18 Conservation of Power and Water Resources 1 2012-04-01 2012-04-01 false Project decommissioning at relicensing. 2.24 Section 2.24 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY GENERAL RULES GENERAL POLICY AND INTERPRETATIONS Statements of General...

78 FR 78338 - Japan-U.S. Decommissioning and Remediation Fukushima Recovery Forum Tokyo, Japan February 18-19...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-12-26

... nuclear energy research and development, the decommissioning of the Fukushima Dai-ichi Nuclear Power Station, environmental management, emergency management, nuclear security, and safety and regulatory issues. The Decommissioning and Environmental Management Working Group (DEMWG) under the Bilateral...

Decommissioning of magnox Ltd fuel cooling pond facilities in the UK

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bertoncini, Carlo

2013-07-01

Magnox reactors were the first generation of nuclear power stations built in the UK; ten sites in total, of which, nine had wet fuel routes with cooling ponds. Five ponds are currently in a decommissioning phase; this paper will focus primarily on Hunterston-A (HNA) Site and the central programme of work which governs its management. During its operation, the Cartridge Cooling Pond at HNA was used to receive the spent fuel discharged from the Site's two reactors, it was then stored for cooling purposes prior to dispatch off site. The current decommissioning phase focusses on draining the 6500 m{sup 3}more » pond. Due to the Site's limited caesium removal facilities, a stand-alone effluent treatment plant was constructed to improve abatement and reduce the pond activity from 200 to 0.7 Bq/ml (β). This was necessary due to increased environmental standards introduced since the site had ceased generation ten years previously. Early characterisation and experience from other sites concluded that if the pond were to be drained without any treatment to the walls, doses to the Operators, during subsequent decommissioning works, would routinely be in excess of 1 mSv.hr{sup -1}(γ). An opportunity was realised within the Ponds Programme that if the surface layer of the pond walls were to be removed during drain-down, ambient dose rates would be reduced by a factor of 10; this would allow for more cost-effective decommissioning options in the future. Ultrahigh pressure water jetting was tested and proved to yield a ∼95% total-activity reduction on treated surfaces. Challenges were overcome in providing safe and secure access to Decommissioning Operators to perform this operation by means of floating platforms on the surface of the pond. As strategies to clear facilities to exemption levels are becoming both cost prohibitive and not reasonably practicable, work is now underway in the Programme to determine the optimum condition for entry into long-term quiescent storage

Reactor Design and Decommissioning - An Overview of International Activities in Post Fukushima Era1 - 12396

DOE Office of Scientific and Technical Information (OSTI.GOV)

Devgun, Jas S.; Laraia, Michele; Pescatore, Claudio

Accidents at the Fukushima Dai-ichi reactors as a result of the devastating earthquake and tsunami of March 11, 2011 have not only dampened the nuclear renaissance but have also initiated a re-examination of the design and safety features for the existing and planned nuclear reactors. Even though failures of some of the key site features at Fukushima can be attributed to events that in the past would have been considered as beyond the design basis, the industry as well as the regulatory authorities are analyzing what features, especially passive features, should be designed into the new reactor designs to minimizemore » the potential for catastrophic failures. It is also recognized that since the design of the Fukushima BWR reactors which were commissioned in 1971, many advanced safety features are now a part of the newer reactor designs. As the recovery efforts at the Fukushima site are still underway, decisions with respect to the dismantlement and decommissioning of the damaged reactors and structures have not yet been finalized. As it was with Three Mile Island, it could take several decades for dismantlement, decommissioning and clean up, and the project poses especially tough challenges. Near-term assessments have been issued by several organizations, including the IAEA, the USNRC and others. Results of such investigations will lead to additional improvements in system and site design measures including strengthening of the anti-tsunami defenses, more defense-in-depth features in reactor design, and better response planning and preparation involving reactor sites. The question also arises what would the effect be on the decommissioning scene worldwide, and what would the effect be on the new reactors when they are eventually retired and dismantled. This paper provides an overview of the US and international activities related to recovery and decommissioning including the decommissioning features in the reactor design process and examines these from a new

Metrology for decommissioning nuclear facilities: Partial outcomes of joint research project within the European Metrology Research Program.

PubMed

Suran, Jiri; Kovar, Petr; Smoldasova, Jana; Solc, Jaroslav; Van Ammel, Raf; Garcia Miranda, Maria; Russell, Ben; Arnold, Dirk; Zapata-García, Daniel; Boden, Sven; Rogiers, Bart; Sand, Johan; Peräjärvi, Kari; Holm, Philip; Hay, Bruno; Failleau, Guillaume; Plumeri, Stephane; Laurent Beck, Yves; Grisa, Tomas

2018-04-01

Decommissioning of nuclear facilities incurs high costs regarding the accurate characterisation and correct disposal of the decommissioned materials. Therefore, there is a need for the implementation of new and traceable measurement technologies to select the appropriate release or disposal route of radioactive wastes. This paper addresses some of the innovative outcomes of the project "Metrology for Decommissioning Nuclear Facilities" related to mapping of contamination inside nuclear facilities, waste clearance measurement, Raman distributed temperature sensing for long term repository integrity monitoring and validation of radiochemical procedures. Copyright © 2017 Elsevier Ltd. All rights reserved.

Northrop TRIGA facility decommissioning plan versus actual results

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gardner, F.W.

1986-01-01

This paper compares the TRIGA facility decontamination and decommissioning (D and D) plan to the actual results and discusses key areas where operational activities were impacted by the final US Nuclear Regulatory Commission approved D and D plan. A discussion of fuel transport, release criteria, and release survey plans is included.

Laboratory activities involving transmissible spongiform encephalopathy causing agents

PubMed Central

Leunda, Amaya; Van Vaerenbergh, Bernadette; Baldo, Aline; Roels, Stefan; Herman, Philippe

2013-01-01

Since the appearance in 1986 of epidemic of bovine spongiform encephalopathy (BSE), a new form of neurological disease in cattle which also affected human beings, many diagnostic and research activities have been performed to develop detection and therapeutic tools. A lot of progress was made in better identifying, understanding and controlling the spread of the disease by appropriate monitoring and control programs in European countries. This paper reviews the recent knowledge on pathogenesis, transmission and persistence outside the host of prion, the causative agent of transmissible spongiform encephalopathies (TSE) in mammals with a particular focus on risk (re)assessment and management of biosafety measures to be implemented in diagnostic and research laboratories in Belgium. Also, in response to the need of an increasing number of European diagnostic laboratories stopping TSE diagnosis due to a decreasing number of TSE cases reported in the last years, decontamination procedures and a protocol for decommissioning TSE diagnostic laboratories is proposed. PMID:24055928

30 CFR 585.913 - What happens if I fail to comply with my approved decommissioning application?

Code of Federal Regulations, 2013 CFR

2013-07-01

... 30 Mineral Resources 2 2013-07-01 2013-07-01 false What happens if I fail to comply with my approved decommissioning application? 585.913 Section 585.913 Mineral Resources BUREAU OF OCEAN ENERGY... § 585.913 What happens if I fail to comply with my approved decommissioning application? If you fail to...

30 CFR 585.913 - What happens if I fail to comply with my approved decommissioning application?

Code of Federal Regulations, 2014 CFR

2014-07-01

... 30 Mineral Resources 2 2014-07-01 2014-07-01 false What happens if I fail to comply with my approved decommissioning application? 585.913 Section 585.913 Mineral Resources BUREAU OF OCEAN ENERGY... § 585.913 What happens if I fail to comply with my approved decommissioning application? If you fail to...

77 FR 64361 - Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-10-19

... Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities AGENCY: Nuclear Regulatory Commission... 15, ``Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level... for low-level waste. DATES: Submit comments by November 15, 2012. Comments received after this date...

30 CFR 585.913 - What happens if I fail to comply with my approved decommissioning application?

Code of Federal Regulations, 2012 CFR

2012-07-01

... 30 Mineral Resources 2 2012-07-01 2012-07-01 false What happens if I fail to comply with my... Application § 585.913 What happens if I fail to comply with my approved decommissioning application? If you fail to comply with your approved decommissioning plan or application: (a) BOEM may call for the...

Challenges with Final Status Surveys at a Large Decommissioning Site - 13417

DOE Office of Scientific and Technical Information (OSTI.GOV)

Downey, Heath; Collopy, Peter; Shephard, Eugene

2013-07-01

As part of decommissioning a former nuclear fuel manufacturing site, one of the crucial final steps is to conduct Final Status Surveys (FSS) in order to demonstrate compliance with the release criteria. At this decommissioning site, the area for FSS was about 100 hectares (248 acres) and included varying terrain, wooded areas, ponds, excavations, buildings and a brook. The challenges in performing the FSS included determining location, identifying FSS units, logging gamma walkover survey data, determining sample locations, managing water in excavations, and diverting water in the brook. The approaches taken to overcome these challenges will be presented in themore » paper. The paper will present and discuss lessons learned that will aid others in the FSS process. (authors)« less

Lessons Learned from the NASA Plum Brook Reactor Facility Decommissioning

NASA Technical Reports Server (NTRS)

2010-01-01

NASA has been conducting decommissioning activities at its PBRF for the last decade. As a result of all this work there have been several lessons learned both good and bad. This paper presents some of the more exportable lessons.

A Multidisciplinary Approach to Decommissioning Offshore Wells Using Stakeholder Engagement, Risk Identification, and the United Nations Sustainable Development Goals

NASA Astrophysics Data System (ADS)

Battalora, L.; Prasad, M.

2017-12-01

Context/PurposeThe typical oil and gas project lifecycle includes acquisition, exploration, drilling, production, and decommissioning phases. The oil and gas industry (Industry) has become proactive in identifying and mitigating health, safety, security, environment, and social responsibility risks during these phases as well as designing for sustainable development. With many fields reaching the end stages of the lifecycle, Industry is faced with the challenge of identifying and evaluating risks in the decommissioning phase. The level of challenge is increased when planning for the decommissioning of offshore wells. This paper describes tools that can be applied in the multidisciplinary design of the decommissioning program including use of the United Nations Sustainable Development Goals (SDGs). MethodsStakeholder engagement is key to a successful project. Typical stakeholders in an oil and gas project include the community, regulatory agencies, federal, state, and local governments, private investors, academia, and non-governmental organizations. Before engagement begins, stakeholders must be identified as well as their level of influence in the project. Relationships between stakeholders are "mapped" providing a better understanding of priorities and areas of concentration. Project risks are identified and ranked according to likelihood and impact. Mitigations are matched to risks. Sustainable development is implemented through acknowledgement of societal, economic, and environmental impacts in engineering design. InterpretationRecently, the United Nations Development Programme (UNDP), the International Finance Corporation (IFC) and IPIECA, the global oil and gas industry association for environmental and social issues, partnered to develop the publication, Mapping the oil and gas industry to the Sustainable Development Goals: An Atlas. SDGs have been linked to Industry operations and can serve as a guide for the offshore decommissioning phase Conclusion

Experience of the nuclear reactors (environmental impact assessment for decommissioning) regulations 1999, as amended, in Great Britain

DOE Office of Scientific and Technical Information (OSTI.GOV)

Brown, Sarah; Mattress, Elaine; Nettleton, Jo

2007-07-01

Available in abstract form only. Full text of publication follows: In Great Britain, the Nuclear Reactors (Environmental Impact Assessment for Decommissioning) Regulations 1999 as amended 2006 (EIADR) requires assessment of the potential environmental impacts of projects to decommission nuclear power stations and reactors. The Health and Safety Executive (HSE) is the competent authority for EIADR. The EIADR implement European Council Directive 85/337/EEC (the EIA Directive) as amended by Council Directive 97/11/EC and Council Directive 2003/35/EC the (Public Participation Directive). The purpose of the EIADR is to assess environmental effects of nuclear reactor decommissioning projects, involve the public through consultation, andmore » make the decision-making process open and transparent. Under the regulations, any licensee wishing to begin to decommission or dismantle a nuclear power station, or other civil nuclear reactor, must apply to HSE for consent to carry out the decommissioning project, undertake an environmental impact assessment and prepare an environmental statement that summarises the environmental effects of the project. HSE will consult on the environmental statement. So far under the EIADR there have been six consents granted for decommissioning projects for Magnox Power Stations. These stations have been required as a condition of consent to submit an Environmental Management Plan on an annual basis. This allows the project to be continually reviewed and assessed to ensure that the licensee can provide detail as agreed during the review of the environmental statement and that any changes to mitigation measures are detailed. This paper summarises the EIADR process, giving particular emphasis to public participation and the decision making process, and discusses HSE's experience of EIADR with reference to specific environmental issues raised by stakeholders and current developments. (authors)« less

Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure, Volume 1, Final report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Konzek, G.J.; Smith, R.I.; Bierschbach, M.C.

1995-11-01

With the issuance of the final Decommissioning Rule (July 27, 1988), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to provide some of the needed bases documentation. This report contains the results of a review andmore » reevaluation of the {prime}978 PNL decommissioning study of the Trojan nuclear power plant (NUREG/CR-0130), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the nuclear power plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5--7 year period during which time the spent fuel is stored in the spent fuel pool, prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a ``green field`` condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities.« less

Overview of Remote Handling Equipment Used for the NPP A1 Decommissioning - 12141

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kravarik, K.; Medved, J.; Pekar, A.

The first Czechoslovak NPP A1 was in operation from 1972 to 1977 and it was finally shutdown due to an accident (level 4 according to the INES). The presence of radioactive, toxic or hazardous materials limits personnel access to facilities and therefore it is necessary to use remote handling technologies for some most difficult characterization, retrieval, decontamination and dismantling tasks. The history of remote handling technologies utilization started in nineties when the spent nuclear fuel, including those fuel assemblies damaged during the accident, was prepared for the transport to Russia. Subsequent significant development of remote handling equipment continued during implementationmore » of the NPP A1 decommissioning project - Stage I and ongoing Stage II. Company VUJE, Inc. is the general contractor for both mentioned stages of the decommissioning project. Various remote handling manipulators and robotics arms were developed and used. It includes remotely controlled vehicle manipulator MT-15 used for characterisation tasks in hostile and radioactive environment, special robust manipulator DENAR-41 used for the decontamination of underground storage tanks and multi-purposes robotics arms MT-80 and MT-80A developed for variety of decontamination and dismantling tasks. The heavy water evaporator facility dismantling is the current task performed remotely by robotics arm MT-80. The heavy water evaporator is located inside the main production building in the room No. 220 where loose surface contamination varies from 10 Bq/cm{sup 2} to 1x10{sup 3} Bq/cm{sup 2}, dose rate is up to 1.5 mGy/h and the feeding pipeline contained liquid RAW with high tritium content. Presented manipulators have been designed for broad range of decommissioning tasks. They are used for recognition, sampling, waste retrieval from large underground tanks, decontamination and dismantling of technological equipments. Each of the mentioned fields claims specific requirements on design

Achieving Effective Risk Management Reduction Throughout Decommissioning at the Columbus Closure Project

DOE Office of Scientific and Technical Information (OSTI.GOV)

Anderson, K.D.

2006-07-01

Nuclear facility decontamination, dismantlement, and demolition activities provide a myriad of challenges along the path to reaching a safe, effective, and compliant decommissioning. Among the challenges faced during decommissioning, is the constant management and technical effort to eliminate, mitigate, or minimize the potential of risks of radiation exposures and other hazards to the worker, the surrounding community, and the environment. Management strategies to eliminate, mitigate, or minimize risks include incorporating strong safety and As Low As Reasonably Achievable (ALARA) principles into an integrated work planning process. Technical and operational strategies may include utilizing predictive risk analysis tools to establish contaminationmore » limits for demolition and using remote handling equipment to reduce occupational and radiation exposures to workers. ECC and E2 Closure Services, LLC (Closure Services) have effectively utilized these management and technical tools to eliminate, mitigate, and reduce radiation exposures under contract to the U.S. Department of Energy (DOE) for the decontamination and decommissioning Columbus Closure Project (CCP). In particular, Closure Services achieved significant dose reduction during the dismantling, decontamination, and demolition activities for Building JN-1. Management strategies during the interior dismantlement, decontamination, and demolition of the facility demanded an integrated work planning processes that involved project disciplines. Integrated planning processes identified multiple opportunities to incorporate the use of remote handling equipment during the interior dismantling and demolition activities within areas of high radiation. Technical strategies employed predictive risk analysis tools to set upper bounding contamination limits, allowed for the radiological demolition of the building without exceeding administrative dose limits to the worker, general public, and the environment. Adhering

HLRW management during MR reactor decommissioning in NRC 'Kurchatov Institute'

DOE Office of Scientific and Technical Information (OSTI.GOV)

Chesnokov, Alexander; Ivanov, Oleg; Kolyadin, Vyacheslav

2013-07-01

A program of decommissioning of MR research reactor in the Kurchatov institute started in 2008. The decommissioning work presumed a preliminary stage, which included: removal of spent fuel from near reactor storage; removal of spent fuel assemble of metal liquid loop channel from a core; identification, sorting and disposal of radioactive objects from gateway of the reactor; identification, sorting and disposal of radioactive objects from cells of HLRW storage of the Kurchatov institute for radwaste creating form the decommissioning of MR. All these works were performed by a remote controlled means with use of a remote identification methods of highmore » radioactive objects. A distribution of activity along high radiated objects was measured by a collimated radiometer installed on the robot Brokk-90, a gamma image of the object was registered by gamma-visor. Spectrum of gamma radiation was measured by a gamma locator and semiconductor detector system. For identification of a presence of uranium isotopes in the HLRW a technique, based on the registration of characteristic radiation of U, was developed. For fragmentation of high radiated objects was used a cold cutting technique and dust suppression system was applied for reduction of volume activity of aerosols in air. The management of HLRW was performed by remote controlled robots Brokk-180 and Brokk-330. They executed sorting, cutting and parking of high radiated part of contaminated equipment. The use of these techniques allowed to reduce individual and collective doses of personal performed the decommissioning. The average individual dose of the personnel was 1,9 mSv/year in 2011, and the collective dose is estimated by 0,0605 man x Sv/year. Use of the remote control machines enables reducing the number of working personal (20 men) and doses. X-ray spectrometric methods enable determination of a presence of the U in high radiated objects and special cans and separation of them for further spent fuel

15 CFR 946.5 - Change in operations-commissioning and decommissioning.

Code of Federal Regulations, 2013 CFR

2013-01-01

... NATIONAL WEATHER SERVICE MODERNIZATION OF THE NATIONAL WEATHER SERVICE § 946.5 Change in operations—commissioning and decommissioning. (a) Before commissioning any new NEXRAD or ASOS weather observation system...; technical coordination with weather service users has been completed; and the system satisfactorily supports...

15 CFR 946.5 - Change in operations-commissioning and decommissioning.

Code of Federal Regulations, 2011 CFR

2011-01-01

... NATIONAL WEATHER SERVICE MODERNIZATION OF THE NATIONAL WEATHER SERVICE § 946.5 Change in operations—commissioning and decommissioning. (a) Before commissioning any new NEXRAD or ASOS weather observation system...; technical coordination with weather service users has been completed; and the system satisfactorily supports...

15 CFR 946.5 - Change in operations-commissioning and decommissioning.

Code of Federal Regulations, 2012 CFR

2012-01-01

... NATIONAL WEATHER SERVICE MODERNIZATION OF THE NATIONAL WEATHER SERVICE § 946.5 Change in operations—commissioning and decommissioning. (a) Before commissioning any new NEXRAD or ASOS weather observation system...; technical coordination with weather service users has been completed; and the system satisfactorily supports...

15 CFR 946.5 - Change in operations-commissioning and decommissioning.

Code of Federal Regulations, 2014 CFR

2014-01-01

... NATIONAL WEATHER SERVICE MODERNIZATION OF THE NATIONAL WEATHER SERVICE § 946.5 Change in operations—commissioning and decommissioning. (a) Before commissioning any new NEXRAD or ASOS weather observation system...; technical coordination with weather service users has been completed; and the system satisfactorily supports...

15 CFR 946.5 - Change in operations-commissioning and decommissioning.

Code of Federal Regulations, 2010 CFR

2010-01-01

... NATIONAL WEATHER SERVICE MODERNIZATION OF THE NATIONAL WEATHER SERVICE § 946.5 Change in operations—commissioning and decommissioning. (a) Before commissioning any new NEXRAD or ASOS weather observation system...; technical coordination with weather service users has been completed; and the system satisfactorily supports...

Estimates of low-level waste volumes and classifications at 2-Unit 1100 MWe reference plants for decommissioning scenarios

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hauf, M.J.; Vance, J.N.; James, D.

1991-01-01

A number of nuclear utilities and industry organizations in the United States have evaluated the requirements for reactor decommissioning. These broad scope studies have addressed the major issues of technology, methodology, safety and costs of decommissioning and have produced substantial volumes of data to describe, in detail, the issues and impacts which result. The objective of this paper to provide CECo a reasonable basis for discussion low-level waste burial volumes for the most likely decommissioning options and to show how various decontamination and VR technologies can be applied to provide additional reduction of the volumes required to be buried atmore » low-level waste burial grounds.« less

30 CFR 585.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

Code of Federal Regulations, 2012 CFR

2012-07-01

... decommissioning for facilities authorized under my SAP, COP, or GAP? 585.902 Section 585.902 Mineral Resources..., Inspections, and Facility Assessments for Activities Conducted Under SAPs, COPs and GAPs Decommissioning... authorized under my SAP, COP, or GAP? (a) Except as otherwise authorized by BOEM under § 585.909, within 2...

Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Volume 2, Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, Final report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Konzek, G.J.; Smith, R.I.; Bierschbach, M.C.

1995-11-01

With the issuance of the final Decommissioning Rule (July 27, 1998), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to provide some of the needed bases documentation. This report contains the results of a review andmore » reevaluation of the 1978 PNL decommissioning study of the Trojan nuclear power plant (NUREG/CR-0130), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the nuclear power plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5--7 year period during which time the spent fuel is stored in the spent fuel pool, prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a ``green field`` condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities.« less

10 CFR 72.30 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Financial assurance and recordkeeping for decommissioning. 72.30 Section 72.30 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN...

30 CFR 285.906 - What must my decommissioning application include?

Code of Federal Regulations, 2010 CFR

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What must my decommissioning application include? 285.906 Section 285.906 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF...

30 CFR 285.529 - Can I use a lease- or grant-specific decommissioning account to meet the financial assurance...

Code of Federal Regulations, 2010 CFR

2010-07-01

... ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF Payments and Financial Assurance Requirements Requirements for Financial Assurance Instruments § 285.529 Can I use a lease- or... decommissioning account to meet the financial assurance requirements related to decommissioning? 285.529 Section...

30 CFR 285.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

Code of Federal Regulations, 2010 CFR

2010-07-01

... decommissioning for facilities authorized under my SAP, COP, or GAP? 285.902 Section 285.902 Mineral Resources... SAP, COP, or GAP? (a) Except as otherwise authorized by MMS under § 285.909, within 2 years following... under your SAP, COP, or GAP, you must submit a decommissioning application and receive approval from the...

Nuclear facility decommissioning and site remedial actions

DOE Office of Scientific and Technical Information (OSTI.GOV)

Knox, N.P.; Webb, J.R.; Ferguson, S.D.

1990-09-01

The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3)more » Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.« less

Development of a reliable estimation procedure of radioactivity inventory in a BWR plant due to neutron irradiation for decommissioning

NASA Astrophysics Data System (ADS)

Tanaka, Ken-ichi; Ueno, Jun

2017-09-01

Reliable information of radioactivity inventory resulted from the radiological characterization is important in order to plan decommissioning planning and is also crucial in order to promote decommissioning in effectiveness and in safe. The information is referred to by planning of decommissioning strategy and by an application to regulator. Reliable information of radioactivity inventory can be used to optimize the decommissioning processes. In order to perform the radiological characterization reliably, we improved a procedure of an evaluation of neutron-activated materials for a Boiling Water Reactor (BWR). Neutron-activated materials are calculated with calculation codes and their validity should be verified with measurements. The evaluation of neutron-activated materials can be divided into two processes. One is a distribution calculation of neutron-flux. Another is an activation calculation of materials. The distribution calculation of neutron-flux is performed with neutron transport calculation codes with appropriate cross section library to simulate neutron transport phenomena well. Using the distribution of neutron-flux, we perform distribution calculations of radioactivity concentration. We also estimate a time dependent distribution of radioactivity classification and a radioactive-waste classification. The information obtained from the evaluation is utilized by other tasks in the preparatory tasks to make the decommissioning plan and the activity safe and rational.

Final report of the decontamination and decommissioning of the BORAX-V facility turbine building

DOE Office of Scientific and Technical Information (OSTI.GOV)

Arave, A.E.; Rodman, G.R.

1992-12-01

The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D&D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D&D plans for the turbine building were prepared from 1979 through 1990. D&D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and the absence of loosemore » contamination, the D&D activities were completed with no radiation exposure to the workers. The D&D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.« less

Final report of the decontamination and decommissioning of the BORAX-V facility turbine building

DOE Office of Scientific and Technical Information (OSTI.GOV)

Arave, A.E.; Rodman, G.R.

1992-12-01

The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D D plans for the turbine building were prepared from 1979 through 1990. D D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and themore » absence of loose contamination, the D D activities were completed with no radiation exposure to the workers. The D D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.« less

10 CFR 40.36 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Financial assurance and recordkeeping for decommissioning. 40.36 Section 40.36 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF SOURCE MATERIAL... licenses authorizing the receipt, possession, and use of source material for uranium or thorium milling, or...

10 CFR 50.75 - Reporting and recordkeeping for decommissioning planning.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 1 2011-01-01 2011-01-01 false Reporting and recordkeeping for decommissioning planning. 50.75 Section 50.75 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND..., Office of Nuclear Material Safety and Safeguards, as applicable, at least 30 working days before the date...

FROM CONCEPT TO REALITY, IN-SITU DECOMMISSIONING OF THE P AND R REACTORS AT THE SAVANNAH RIVER SITE

DOE Office of Scientific and Technical Information (OSTI.GOV)

Musall, J.; Blankenship, J.; Griffin, W.

2012-01-09

SRS recently completed an approximately three year effort to decommission two SRS reactors: P-Reactor (Building 105-P) and R-Reactor (Building 105-R). Completed in December 2011, the concurrent decommissionings marked the completion of two relatively complex and difficult facility disposition projects at the SRS. Buildings 105-P and 105-R began operating as production reactors in the early 1950s with the mission of producing weapons material (e.g., tritium and plutonium-239). The 'P' Reactor and was shutdown in 1991 while the 'R' Reactor and was shutdown in 1964. In the intervening period between shutdown and deactivation & decommissioning (D&D), Buildings 105-P and 105-R saw limitedmore » use (e.g., storage of excess heavy water and depleted uranium oxide). For Building 105-P, deactivation was initiated in April 2007 and was essentially complete by June 2010. For Building 105-R, deactivation was initiated in August 2008 and was essentially complete by September 2010. For both buildings, the primary objective of deactivation was to remove/mitigate hazards associated with the remaining hazardous materials, and thus prepare the buildings for in-situ decommissioning. Deactivation removed the following hazardous materials to the extent practical: combustibles/flammables, residual heavy water, acids, friable asbestos (as needed to protect workers performing deactivation and decommissioning), miscellaneous chemicals, lead/brass components, Freon(reg sign), oils, mercury/PCB containing components, mold and some radiologically-contaminated equipment. In addition to the removal of hazardous materials, deactivation included the removal of hazardous energy, exterior metallic components (representing an immediate fall hazard), and historical artifacts along with the evaporation of water from the two Disassembly Basins. Finally, so as to facilitate occupancy during the subsequent in-situ decommissioning, deactivation implemented repairs to the buildings and provided temporary

Decontamination, decommissioning, and vendor advertorial issue, 2007

DOE Office of Scientific and Technical Information (OSTI.GOV)

Agnihotri, Newal

The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: An interesting year ahead of us, by Tom Christopher, AREVA NP Inc.; U.S.-India Civil Nuclear Cooperation; Decontamination and recycling of retired components, by Sean P. Brushart, Electric Power Research Institute; and, ANO is 33 and going strong, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The industry innovation article is: Continuous improvement process, by ReNae Kowalewski, Arkansas Nuclear One.

30 CFR 250.1750 - When may I decommission a pipeline in place?

Code of Federal Regulations, 2010 CFR

2010-07-01

... OFFSHORE OIL AND GAS AND SULPHUR OPERATIONS IN THE OUTER CONTINENTAL SHELF Decommissioning Activities... (obstruction) to navigation and commercial fishing operations, unduly interfere with other uses of the OCS, or...

Decontamination & decommissioning focus area

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1996-08-01

In January 1994, the US Department of Energy Office of Environmental Management (DOE EM) formally introduced its new approach to managing DOE`s environmental research and technology development activities. The goal of the new approach is to conduct research and development in critical areas of interest to DOE, utilizing the best talent in the Department and in the national science community. To facilitate this solutions-oriented approach, the Office of Science and Technology (EM-50, formerly the Office of Technology Development) formed five Focus AReas to stimulate the required basic research, development, and demonstration efforts to seek new, innovative cleanup methods. In Februarymore » 1995, EM-50 selected the DOE Morgantown Energy Technology Center (METC) to lead implementation of one of these Focus Areas: the Decontamination and Decommissioning (D & D) Focus Area.« less

Removal design report for the 108-F Biological Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1997-09-01

Most of the 100-F facilities were deactivated with the reactor and have since been demolished. Of the dozen or so reactor-related structures, only the 105-F Reactor Building and the 108-F Biology Laboratory remain standing today. The 108-F Biology Laboratory was intended to be used as a facility for the mixing and addition of chemicals used in the treatment of the reactor cooling water. Shortly after F Reactor began operation, it was determined that the facility was not needed for this purpose. In 1949, the building was converted for use as a biological laboratory. In 1962, the lab was expanded bymore » adding a three-story annex to the original four-story structure. The resulting lab had a floor area of approximately 2,883 m{sup 2} (main building and annex) that operated until 1973. The building contained 47 laboratories, a number of small offices, a conference room, administrative section, lunch and locker rooms, and a heavily shielded, high-energy exposure cell. The purpose of this removal design report is to establish the methods of decontamination and decommissioning and the supporting functions associated with facility removal and disposal.« less

30 CFR 250.1751 - How do I decommission a pipeline in place?

Code of Federal Regulations, 2014 CFR

2014-07-01

... to be decommissioned; and (4) Length (feet) of segment remaining. (b) Pig the pipeline, unless the Regional Supervisor determines that pigging is not practical; (c) Flush the pipeline; (d) Fill the pipeline...

30 CFR 250.1751 - How do I decommission a pipeline in place?

Code of Federal Regulations, 2012 CFR

2012-07-01

... to be decommissioned; and (4) Length (feet) of segment remaining. (b) Pig the pipeline, unless the Regional Supervisor determines that pigging is not practical; (c) Flush the pipeline; (d) Fill the pipeline...

30 CFR 250.1751 - How do I decommission a pipeline in place?

Code of Federal Regulations, 2011 CFR

2011-07-01

... to be decommissioned; and (4) Length (feet) of segment remaining. (b) Pig the pipeline, unless the Regional Supervisor determines that pigging is not practical; (c) Flush the pipeline; (d) Fill the pipeline...

30 CFR 250.1751 - How do I decommission a pipeline in place?

Code of Federal Regulations, 2013 CFR

2013-07-01

... to be decommissioned; and (4) Length (feet) of segment remaining. (b) Pig the pipeline, unless the Regional Supervisor determines that pigging is not practical; (c) Flush the pipeline; (d) Fill the pipeline...

10 CFR 72.30 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2013 CFR

2013-01-01

... CLASS C WASTE License Application, Form, and Contents § 72.30 Financial assurance and recordkeeping for... review and approval a decommissioning funding plan that must contain: (1) Information on how reasonable... previous cost estimate. (d) If, in surveys made under 10 CFR 20.1501(a), residual radioactivity in soils or...

10 CFR 72.30 - Financial assurance and recordkeeping for decommissioning.

Code of Federal Regulations, 2014 CFR

2014-01-01

... CLASS C WASTE License Application, Form, and Contents § 72.30 Financial assurance and recordkeeping for... review and approval a decommissioning funding plan that must contain: (1) Information on how reasonable... previous cost estimate. (d) If, in surveys made under 10 CFR 20.1501(a), residual radioactivity in soils or...

Revised guidelines for good practice in IVF laboratories (2015).

PubMed

De los Santos, Maria José; Apter, Susanna; Coticchio, Giovanni; Debrock, Sophie; Lundin, Kersti; Plancha, Carlos E; Prados, Fernando; Rienzi, Laura; Verheyen, Greta; Woodward, Bryan; Vermeulen, Nathalie

2016-04-01

group is confident that this document will be helpful to directors and managers involved in the management and organization of IVF laboratories, but also to embryologists and laboratory technicians performing daily tasks. The guideline was developed and funded by ESHRE, covering expenses associated with the guideline meetings. The guideline group members did not receive payment. Dr Coticchio reports speaker's fees from IBSA and Cook, outside the submitted work; Dr Lundin reports grants from Vitrolife, personal fees from Merck Serono, non-financial support from Unisense, outside the submitted work; Dr. Rienzi reports personal fees from Merck Serono, personal fees from MSD, grants from GFI, outside the submitted work; the other authors had nothing to disclose. NA. © The Author 2016. Published by Oxford University Press on behalf of the European Society of Human Reproduction and Embryology. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

DEACTIVATION AND DECOMMISSIONING ENVIRONMENTAL STRATEGY FOR THE PLUTONIUM FINISHING PLANT COMPLEX, HANFORD NUCLEAR RESERVATION

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hopkins, A.M.; Heineman, R.; Norton, S.

Maintaining compliance with environmental regulatory requirements is a significant priority in successful completion of the Plutonium Finishing Plant (PFP) Nuclear Material Stabilization (NMS) Project. To ensure regulatory compliance throughout the deactivation and decommissioning of the PFP complex, an environmental regulatory strategy was developed. The overall goal of this strategy is to comply with all applicable environmental laws and regulations and/or compliance agreements during PFP stabilization, deactivation, and eventual dismantlement. Significant environmental drivers for the PFP Nuclear Material Stabilization Project include the Tri-Party Agreement; the Resource Conservation and Recovery Act of 1976 (RCRA); the Comprehensive Environmental Response, Compensation and Liability Actmore » of 1980 (CERCLA); the National Environmental Policy Act of 1969 (NEPA); the National Historic Preservation Act (NHPA); the Clean Air Act (CAA), and the Clean Water Act (CWA). Recent TPA negotiation s with Ecology and EPA have resulted in milestones that support the use of CERCLA as the primary statutory framework for decommissioning PFP. Milestones have been negotiated to support the preparation of Engineering Evaluations/Cost Analyses for decommissioning major PFP buildings. Specifically, CERCLA EE/CA(s) are anticipated for the following scopes of work: Settling Tank 241-Z-361, the 232-Z Incinerator, , the process facilities (eg, 234-5Z, 242, 236) and the process facility support buildings. These CERCLA EE/CA(s) are for the purpose of analyzing the appropriateness of the slab-on-grade endpoint Additionally, agreement was reached on performing an evaluation of actions necessary to address below-grade structures or other structures remaining after completion of the decommissioning of PFP. Remaining CERCLA actions will be integrated with other Central Plateau activities at the Hanford site.« less

10 CFR 50.75 - Reporting and recordkeeping for decommissioning planning.

Code of Federal Regulations, 2012 CFR

2012-01-01

... up to a 2 percent annual real rate of return from the time of future funds' collection through the... annual real rate of return from the time of future funds' collection through the decommissioning period... investment manager for the funds or from giving day-to-day management direction of the funds' investments or...

30 CFR 285.907 - How will MMS process my decommissioning application?

Code of Federal Regulations, 2010 CFR

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false How will MMS process my decommissioning application? 285.907 Section 285.907 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF...

30 CFR 285.905 - When must I submit my decommissioning application?

Code of Federal Regulations, 2010 CFR

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false When must I submit my decommissioning application? 285.905 Section 285.905 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF...

Radiation dose optimization in the decommissioning plan for Loviisa NPP

DOE Office of Scientific and Technical Information (OSTI.GOV)

Holmberg, R.; Eurajoki, T.

1995-03-01

Finnish rules for nuclear power require a detailed decommissioning plan to be made and kept up to date already during plant operation. The main reasons for this {open_quotes}premature{close_quotes} plan, is, firstly, the need to demonstrate the feasibility of decommissioning, and, secondly, to make realistic cost estimates in order to fund money for this future operation. The decomissioning for Lovissa Nuclear Power Plant (NPP) (2{times}445 MW, PWR) was issued in 1987. It must be updated about every five years. One important aspect of the plant is an estimate of radiation doses to the decomissioning workers. The doses were recently re-estimated becausemore » of a need to decrease the total collective dose estimate in the original plan, 23 manSv. In the update, the dose was reduced by one-third. Part of the reduction was due to changes in the protection and procedures, in which ALARA considerations were taken into account, and partly because of re-estimation of the doses.« less

Estimation and characterization of decontamination and decommissioning solid waste expected from the Plutonium Finishing Plant

DOE Office of Scientific and Technical Information (OSTI.GOV)

Millar, J.S.; Pottmeyer, J.A.; Stratton, T.J.

1995-01-01

Purpose of the study was to estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the Hanford Plutonium Finishing Plant is decontaminated and decommissioned. (Building structure and soil are not covered.) Results indicate that {approximately}5,500 m{sup 3} of solid waste is expected to result from the decontamination and decommissioning of the Pu Finishing Plant. The breakdown of the volumes and percentages of waste by category is 1% dangerous solid waste, 71% low-level waste, 21% transuranic waste, 7% transuranic mixed waste.

76 FR 65541 - Assuring the Availability of Funds for Decommissioning Nuclear Reactors

Federal Register 2010, 2011, 2012, 2013, 2014

2011-10-21

... NUCLEAR REGULATORY COMMISSION [NRC-2009-0263] Assuring the Availability of Funds for Decommissioning Nuclear Reactors AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or Commission) is issuing a revision to Regulatory...

Environmental problems associated with decommissioning the Chernobyl Nuclear Power Plant Cooling Pond.

PubMed

Oskolkov, B Ya; Bondarkov, M D; Gaschak, S P; Maksymenko, A M; Maksymenko, V M; Martynenko, V I; Farfán, E B; Jannik, G T; Marra, J C

2010-11-01

Decommissioning of nuclear power plants and other nuclear fuel cycle facilities associated with residual radioactive contamination of their territories is an imperative issue. Significant problems may result from decommissioning of cooling ponds with residual radioactive contamination. The Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond is one of the largest self-contained water reservoirs in the Chernobyl region and Ukrainian and Belorussian Polesye region. The 1986 ChNPP Reactor Unit Number Four significantly contaminated the ChNPP Cooling Pond. The total radionuclide inventory in the ChNPP Cooling Pond bottom deposits are as follows: ¹³⁷Cs: 16.28 ± 2.59 TBq; ⁹⁰Sr: 2.4 ± 0.48 TBq; and ²³⁹+²⁴⁰Pu: 0.00518 ± 0.00148 TBq. The ChNPP Cooling Pond is inhabited by over 500 algae species and subspecies, over 200 invertebrate species, and 36 fish species. The total mass of the living organisms in the ChNPP Cooling Pond is estimated to range from about 60,000 to 100,000 tons. The territory adjacent to the ChNPP Cooling Pond attracts many birds and mammals (178 bird species and 47 mammal species were recorded in the Chernobyl Exclusion Zone). This article describes several options for the ChNPP Cooling Pond decommissioning and environmental problems associated with its decommissioning. The article also provides assessments of the existing and potential exposure doses for the shoreline biota. For the 2008 conditions, the estimated total dose rate values were 11.4 40 μGy h⁻¹ for amphibians, 6.3 μGy h⁻¹ for birds, 15.1 μGy h⁻¹ for mammals, and 10.3 μGy h⁻¹ for reptiles, with the recommended maximum dose rate being equal to 40 μGy h⁻¹. However, drying the ChNPP Cooling Pond may increase the exposure doses to 94.5 μGy h⁻¹ for amphibians, 95.2 μGy h⁻¹ for birds, 284.0 μGy h⁻¹ for mammals, and 847.0 μGy h⁻¹ for reptiles. All of these anticipated dose rates exceed the recommended values.

30 CFR 250.1703 - What are the general requirements for decommissioning?

Code of Federal Regulations, 2011 CFR

2011-07-01

... 30 Mineral Resources 2 2011-07-01 2011-07-01 false What are the general requirements for decommissioning? 250.1703 Section 250.1703 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, REGULATION, AND..., marine, or coastal environment. [67 FR 35406, May 17, 2002, as amended at 74 FR 19807, Apr. 29, 2009] ...

Societal constraints related to environmental remediation and decommissioning programmes.

PubMed

Perko, Tanja; Monken-Fernandes, Horst; Martell, Meritxell; Zeleznik, Nadja; O'Sullivan, Patrick

2017-06-20

The decisions related to decommissioning or environmental remediation projects (D/ER) cannot be isolated from the socio-political and cultural environment. Experiences of the IAEA Member States point out the importance of giving due attention to the societal aspects in project planning and implementation. The purpose of this paper is threefold: i) to systematically review societal constraints that some organisations in different IAEA Member States encounter when implementing D/ER programmes, ii) to identify different approaches to overcome these constraints and iii) to collect examples of existing practices related to the integration of societal aspects in D/ER programmes worldwide. The research was conducted in the context of the IAEA project Constraints to Decommissioning and Environmental Remediation (CIDER). The research results show that societal constraints arise mostly as a result of the different perceptions, attitudes, opinions and concerns of stakeholders towards the risks and benefits of D/ER programmes and due to the lack of stakeholder involvement in planning. There are different approaches to address these constraints, however all approaches have common points: early involvement, respect for different views, mutual understanding and learning. These results are relevant for all on-going and planned D/ER programmes. Copyright © 2017 Elsevier Ltd. All rights reserved.

Potential for recycling of slightly radioactive metals arising from decommissioning within nuclear sector in Slovakia.

PubMed

Hrncir, Tomas; Strazovec, Roman; Zachar, Matej

2017-09-07

The decommissioning of nuclear installations represents a complex process resulting in the generation of large amounts of waste materials containing various concentrations of radionuclides. Selection of an appropriate strategy of management of the mentioned materials strongly influences the effectiveness of decommissioning process keeping in mind safety, financial and other relevant aspects. In line with international incentives for optimization of radioactive material management, concepts of recycling and reuse of materials are widely discussed and applications of these concepts are analysed. Recycling of some portion of these materials within nuclear sector (e.g. scrap metals or concrete rubble) seems to be highly desirable from economical point of view and may lead to conserve some disposal capacity. However, detailed safety assessment along with cost/benefit calculations and feasibility study should be developed in order to prove the safety, practicality and cost effectiveness of possible recycling scenarios. Paper discussed the potential for recycling of slightly radioactive metals arising from decommissioning of NPPs within nuclear sector in Slovakia. Various available recycling scenarios are introduced and method for overall assessment of various recycling scenarios is outlined including the preliminary assessment of safety and financial aspects. Copyright © 2017 Elsevier Ltd. All rights reserved.

Environmental Problems Associated With Decommissioning The Chernobyl Nuclear Power Plant Cooling Pond

DOE Office of Scientific and Technical Information (OSTI.GOV)

Farfan, E. B.; Jannik, G. T.; Marra, J. C.

2009-11-09

Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. Inmore » addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.« less

ENVIRONMENTAL PROBLEMS ASSOCIATED WITH DECOMMISSIONING THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND

DOE Office of Scientific and Technical Information (OSTI.GOV)

Farfan, E.

2009-09-30

Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. Inmore » addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.« less

An analytical approach to γ-ray self-shielding effects for radioactive bodies encountered nuclear decommissioning scenarios.

PubMed

Gamage, K A A; Joyce, M J

2011-10-01

A novel analytical approach is described that accounts for self-shielding of γ radiation in decommissioning scenarios. The approach is developed with plutonium-239, cobalt-60 and caesium-137 as examples; stainless steel and concrete have been chosen as the media for cobalt-60 and caesium-137, respectively. The analytical methods have been compared MCNPX 2.6.0 simulations. A simple, linear correction factor relates the analytical results and the simulated estimates. This has the potential to greatly simplify the estimation of self-shielding effects in decommissioning activities. Copyright © 2011 Elsevier Ltd. All rights reserved.

A gas flow indicator for portable life support systems

NASA Technical Reports Server (NTRS)

Bass, R. L., III; Schroeder, E. C.

1975-01-01

A three-part program was conducted to develop a gas flow indicator (GFI) to monitor ventilation flow in a portable life support system. The first program phase identified concepts which could potentially meet the GFI requirements. In the second phase, a working breadboard GFI, based on the concept of a pressure sensing diaphragm-aneroid assembly connected to a venturi, was constructed and tested. Extensive testing of the breadboard GFI indicated that the design would meet all NASA requirements including eliminating problems experienced with the ventilation flow sensor used in the Apollo program. In the third program phase, an optimized GFI was designed by utilizing test data obtained on the breadboard unit. A prototype unit was constructed using prototype materials and fabrication techniques, and performance tests indicated that the prototype GFI met or exceeded all requirements.

Evaluation of Dam Decommissioning in an Ice-Affected River: Case Study

DTIC Science & Technology

2007-09-01

Abdul-Mohsen 2005 and Kuby et al. 2005). Conyngham et al. (2006) provide an overview of the ecological and engi- neering aspects of dam decommissioning...2007) CRREL Ice Jam Database (http://www.crrel.usace.army.mil/ierd/ijdb/), accessed March 2007. Kuby , M.J., W.F. Fagan, C.S. ReVelle, W.L. Graf (2005

30 CFR 285.908 - What must I include in my decommissioning notice?

Code of Federal Regulations, 2010 CFR

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What must I include in my decommissioning notice? 285.908 Section 285.908 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF...

30 CFR 285.908 - What must I include in my decommissioning notice?

Code of Federal Regulations, 2011 CFR

2011-07-01

... 30 Mineral Resources 2 2011-07-01 2011-07-01 false What must I include in my decommissioning notice? 285.908 Section 285.908 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT, REGULATION, AND... the impacts previously identified and evaluated; (2) Require any additional Federal permits; or (3...

Enhancing Efficiency of Safeguards at Facilities that are Shutdown or Closed-Down, including those being Decommissioned

DOE Office of Scientific and Technical Information (OSTI.GOV)

Moran, B.; Stern, W.; Colley, J.

International Atomic Energy Agency (IAEA) safeguards involves verification activities at a wide range of facilities in a variety of operational phases (e.g., under construction, start-up, operating, shutdown, closed-down, and decommissioned). Safeguards optimization for each different facility type and operational phase is essential for the effectiveness of safeguards implementation. The IAEA’s current guidance regarding safeguards for the different facility types in the various lifecycle phases is provided in its Design Information Examination (DIE) and Verification (DIV) procedure. 1 Greater efficiency in safeguarding facilities that are shut down or closed down, including those being decommissioned, could allow the IAEA to use amore » greater portion of its effort to conduct other verification activities. Consequently, the National Nuclear Security Administration’s Office of International Nuclear Safeguards sponsored this study to evaluate whether there is an opportunity to optimize safeguards approaches for facilities that are shutdown or closed-down. The purpose of this paper is to examine existing safeguards approaches for shutdown and closed-down facilities, including facilities being decommissioned, and to seek to identify whether they may be optimized.« less

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text

DOE Office of Scientific and Technical Information (OSTI.GOV)

Goins, L.F.; Webb, J.R.; Cravens, C.D.

1992-09-01

This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedialmore » Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.« less

Technology, safety and costs of decommissioning reference independent spent fuel storage installations. [Contains glossary

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ludwick, J D; Moore, E B

1984-01-01

Safety and cost information is developed for the conceptual decommissioning of five different types of reference independent spent fuel storage installations (ISFSIs), each of which is being given consideration for interim storage of spent nuclear fuel in the United States. These include one water basin-type ISFSI (wet) and four dry ISFSIs (drywell, silo, vault, and cask). The reference ISFSIs include all component parts necessary for the receipt, handling and storage of spent fuel in a safe and efficient manner. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, and potential radiation doses tomore » the public. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment followed by long-term surveillance).« less

30 CFR 250.255 - What decommissioning information must accompany the DPP or DOCD?

Code of Federal Regulations, 2010 CFR

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What decommissioning information must accompany the DPP or DOCD? 250.255 Section 250.255 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF... Information Contents of Development and Production Plans (dpp) and Development Operations Coordination...

Revegetation Plan for Areas of the Fitzner-Eberhardt Arid Lands Ecology Reserve Affected by Decommissioning of Buildings and Infrastructure and Debris Clean-up Actions

DOE Office of Scientific and Technical Information (OSTI.GOV)

Downs, Janelle L.; Durham, Robin E.; Larson, Kyle B.

The U.S. Department of Energy (DOE), Richland Operations Office is working to remove a number of facilities on the Fitzner Eberhardt Arid Lands Ecology Reserve (ALE), which is part of the Hanford Reach National Monument. Decommissioning and removal of buildings and debris on ALE will leave bare soils and excavated areas that need to be revegetated to prevent erosion and weed invasion. Four main areas within ALE are affected by these activities (DOE 2009;DOE/EA-1660F): 1) facilities along the ridgeline of Rattlesnake Mountain, 2) the former Nike missile base and ALE HQ laboratory buildings, 3) the aquatic research laboratory at Rattlesnakemore » Springs area, and 4) a number of small sites across ALE where various types of debris remain from previous uses. This revegetation plan addresses the revegetation and restoration of those land areas disturbed by decommissioning and removal of buildings, facilities and associated infrastructure or debris removal. The primary objective of the revegetation efforts on ALE is to establish native vegetation at each of the sites that will enhance and accelerate the recovery of the native plant community that naturally persists at that location. Revegetation is intended to meet the direction specified by the Environmental Assessment (DOE 2009; DOE/EA-1660F) and by Stipulation C.7 of the Memorandum of Agreement (MOA) for the Rattlesnake Mountain Combined Community Communication Facility and InfrastructureCleanup on the Fitzner/Eberhardt Arid Lands Ecology Reserve, Hanford Site, Richland Washington(DOE 2009; Appendix B). Pacific Northwest National Laboratory (PNNL) under contract with CH2M Hill Plateau Remediation Company (CPRC) and in consultation with the tribes and DOE-RL developed a site-specific strategy for each of the revegetation units identified within this document. The strategy and implementation approach for each revegetation unit identifies an appropriate native species mix and outlines the necessary site preparation

Decontamination, decommissioning, and vendor advertorial issue, 2008

DOE Office of Scientific and Technical Information (OSTI.GOV)

Agnihotri, Newal

The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Articles and reports in this issue include: D and D technical paper summaries; The role of nuclear power in turbulent times, by Tom Chrisopher, AREVA, NP, Inc.; Enthusiastic about new technologies, by Jack Fuller, GE Hitachi Nuclear Energy; It's important to be good citizens, by Steve Rus, Black and Veatch Corporation; Creating Jobs in the U.S., by Guy E. Chardon, ALSTOM Power; and, and, An enviroment and a community champion, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovations article is titled Best of the bestmore » TIP achievement 2008, by Edward Conaway, STP Nuclear Operating Company.« less

Alpha Particle Detection Using Alpha-Induced Air Radioluminescence: A Review and Future Prospects for Preliminary Radiological Characterisation for Nuclear Facilities Decommissioning

PubMed Central

Crompton, Anita J.; Jenkins, Alex

2018-01-01

The United Kingdom (UK) has a significant legacy of nuclear installations to be decommissioned over the next 100 years and a thorough characterisation is required prior to the development of a detailed decommissioning plan. Alpha radiation detection is notoriously time consuming and difficult to carry out due to the short range of alpha particles in air. Long-range detection of alpha particles is therefore highly desirable and this has been attempted through the detection of secondary effects from alpha radiation, most notably the air-radioluminescence caused by ionisation. This paper evaluates alpha induced air radioluminescence detectors developed to date and looks at their potential to develop a stand-off, alpha radiation detector which can be used in the nuclear decommissioning field in daylight conditions to detect alpha contaminated materials. PMID:29597340

Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

DOE Office of Scientific and Technical Information (OSTI.GOV)

Saleh, Lydia Ilaiza, E-mail: lydiailaiza@gmail.com; Ryong, Kim Tae

The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of thismore » paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.« less

30 CFR 250.255 - What decommissioning information must accompany the DPP or DOCD?

Code of Federal Regulations, 2011 CFR

2011-07-01

... 30 Mineral Resources 2 2011-07-01 2011-07-01 false What decommissioning information must accompany the DPP or DOCD? 250.255 Section 250.255 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... OUTER CONTINENTAL SHELF Plans and Information Contents of Development and Production Plans (dpp) and...

How Does Decommissioning Forest Roads Effect Hydrologic and Geomorphic Risk?

NASA Astrophysics Data System (ADS)

Black, T.; Luce, C.; Cissel, R. M.; Nelson, N.; Staab, B.

2010-12-01

The US Forest Service is investigating road decommissioning projects to understand how treatments change hydrologic and geomorphic risks. Road treatment effect was measured using a before after control impact design (BACI), using the Geomorphic Road Analysis and Inventory Package (http://www.fs.fed.us/GRAIP). This suite of inventory and analysis tools evaluates: road-stream hydrologic connectivity, fine sediment production and delivery, shallow landslide risk, gully initiation risk, and risks associated with stream crossing failures. The Skokomish River study site is steep and wet and received a high intensity treatment including the removal of stream crossing pipes and fills, all ditch relief pipes and a full hillslope recontouring. Road to stream hydrologic connectivity was reduced by 70%. The treatments reduced fine sediment delivery by 21.8 tons or 81%. The removal of the stream crossing culverts and large associated road fills eliminated the risk of pipe plugging related failures and the eventual erosion of over 4,000 m3 of fill. The slope stability risk was assessed using a modified version of SINMAP (Pack et al, 2005). Risk below drain point locations on the original road was reduced as water was redistributed across the hillslope to waterbars and diffuse drainage. It is unclear; however, if landslide risk was reduced across the entire treated road length because treatments slightly increased risk in some areas where new concentrated drainage features were added above steep slopes. Similarly, values of a gully index ESI (Istanbulluoglu et al, 2003), were reduced at many of the original drainage points, however some new drainage was added. ESI values still exceed a predicted conservative initiation thresholds at some sites, therefore it is uncertain if gully risk will be changed. Mann Creek occupies a moderately steep mid-elevation site in Southern Idaho. The high intensity treatments removed all constructed road drainage features including stream crossing

Release and disposal of materials during decommissioning of Siemens MOX fuel fabrication plant at Hanau, Germany

DOE Office of Scientific and Technical Information (OSTI.GOV)

Koenig, Werner; Baumann, Roland

2007-07-01

In September 2006, decommissioning and dismantling of the Siemens MOX Fuel Fabrication Plant in Hanau were completed. The process equipment and the fabrication buildings were completely decommissioned and dismantled. The other buildings were emptied in whole or in part, although they were not demolished. Overall, the decommissioning process produced approximately 8500 Mg of radioactive waste (including inactive matrix material); clearance measurements were also performed for approximately 5400 Mg of material covering a wide range of types. All the equipment in which nuclear fuels had been handled was disposed of as radioactive waste. The radioactive waste was conditioned on the basismore » of the requirements specified for the projected German final disposal site 'Schachtanlage Konrad'. During the pre-conditioning, familiar processes such as incineration, compacting and melting were used. It has been shown that on account of consistently applied activity containment (barrier concept) during operation and dismantling, there has been no significant unexpected contamination of the plant. Therefore almost all the materials that were not a priori destined for radioactive waste were released without restriction on the basis of the applicable legal regulations (chap. 29 of the Radiation Protection Ordinance), along with the buildings and the plant site. (authors)« less

75 FR 4803 - Notice of Availability of the Final Environmental Impact Statement for Decommissioning and/or...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-01-29

...). The Proposed Action includes the decontamination and decommissioning of the waste storage tanks and... site facilities identified in the Final EIS would be removed; contaminated soil, sediment, and...

77 FR 64765 - Airworthiness Directives; Airbus Airplanes

Federal Register 2010, 2011, 2012, 2013, 2014

2012-10-23

... failure of any post- modification operational test of the GFI. You may obtain further information by... GFI or deactivation of the associated fuel pump following failure of any post-modification operational test of the GFI. We are proposing this AD to prevent the potential of ignition sources inside fuel...

Solid Waste from the Operation and Decommissioning of Power Plants

DOE Office of Scientific and Technical Information (OSTI.GOV)

Brown, Marilyn Ann; D'Arcy, Daniel; Lapsa, Melissa Voss

This baseline report examines the solid waste generated by the U.S. electric power industry, including both waste streams resulting from electricity generation and wastes resulting from the decommissioning of power plants. Coal and nuclear plants produce large volumes of waste during electricity generation, and this report describes the policies and procedures for handling these materials. Natural gas and oil-fired power plants face similar waste challenges. Renewables considered in this baseline report include hydropower, wind and solar.

Decommissioning and PIE of the MEGAPIE spallation target

DOE Office of Scientific and Technical Information (OSTI.GOV)

Latge, C.; Henry, J.; Wohlmuther, M.

2013-07-01

A key experiment in the Accelerated Driven Systems roadmap, the MEGAwatt PIlot Experiment (MEGAPIE) (1 MW) was initiated in 1999 in order to design and build a liquid lead-bismuth spallation target, then to operate it into the Swiss spallation neutron facility SINQ at Paul Scherrer Institute. The target has been designed, manufactured, and tested during integral tests, before irradiation carried out end of 2006. During irradiation, neutron and thermo hydraulic measurements were performed allowing deep interpretation of the experiment and validation of the models used during design phase. The decommissioning, Post Irradiation Examinations and waste management phases were defined properly.more » The phases dedicated to cutting, sampling, cleaning, waste management, samples preparation and shipping to various laboratories were performed by PSI teams: all these phases constitute a huge work, which allows now to perform post-irradiation examination (PIE) of structural material, irradiated in relevant conditions. Preliminary results are presented in the paper, they concern chemical characterization. The following radio-nuclides have been identified by γ-spectrometry: {sup 60}Co, {sup 101}Rh, {sup 102}Rh, {sup 108m}Ag, {sup 110m}Ag, {sup 133}Ba, {sup 172}Hf/Lu, {sup 173}Lu, {sup 194}Hg/Au, {sup 195}Au, {sup 207}Bi. For some of these nuclides the activities can be easily evaluated from γ-spectrometry results ({sup 207}Bi, {sup 194}Hg/Au), while other nuclides can only be determined after chemical separations ({sup 108m}Ag, {sup 110m}Ag, {sup 195}Au, {sup 129}I, {sup 36}Cl and α-emitting {sup 208-210}Po). The concentration of {sup 129}I is lower than expected. The chemical analysis already performed on spallation and corrosion products in the lead-bismuth eutectic (LBE) are very relevant for further applications of LBE as a spallation media and more generally as a coolant.« less

Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron Activated Shield Wall

DOE Office of Scientific and Technical Information (OSTI.GOV)

Michael R. Kruzic

2007-09-16

Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility was used in the early to mid-1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles in the immediate area. Identified as Corrective Action Unit 115, the TCA facility was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the ''Federal Facilitymore » Agreement and Consent Order''. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously provided technical decisions are made by an experienced decision maker within the site conceptual site model, identified in the Data Quality Objective process. Facility closure involved a seven-step decommissioning strategy. Key lessons learned from the project included: (1) Targeted preliminary investigation activities provided a more solid technical approach, reduced surprises and scope creep, and made the working environment safer for the D&D worker. (2) Early identification of risks and uncertainties provided opportunities for risk management and mitigation planning to address challenges and unanticipated conditions. (3) Team reviews provided an excellent mechanism to consider all aspects of the task, integrated safety into activity performance, increase team unity and ''buy-in'' and promoted innovative and time saving ideas. (4) Development of CED protocols ensured safety and control. (5) The same proven D&D strategy is now being employed on the larger ''sister'' facility, Test Cell C.« less

Environmental Assessment for decommissioning the Strategic Petroleum Reserve Weeks Island Facility, Iberia Parish, Louisiana

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1995-12-01

The Strategic Petroleum Reserve (SPR) Weeks Island site is one of five underground salt dome crude oils storage facilities operated by the Department of Energy (DOE). It is located in Iberia Parish, Louisiana. The purpose of the proposed action is to decommission the Weeks Island crude oil storage after the oil inventory has been transferred to other SPR facilities. Water intrusion into the salt dome storage chambers and the development of two sinkholes located near the aboveground facilities has created uncertain geophysical conditions. This Environmental Assessment describes the proposed decommissioning operation, its alternatives, and potential environmental impacts. Based on thismore » analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) and has issued the Finding of No Significant Impact (FONSI).« less

26 CFR 1.468A-1T - Nuclear decommissioning costs; general rules (temporary).

Code of Federal Regulations, 2010 CFR

2010-04-01

... an elective method for taking into account nuclear decommissioning costs for Federal income tax... accrual method of accounting that do not elect the application of section 468A are not allowed a deduction... nuclear power plant means any nuclear power reactor that is used predominantly in the trade or business of...

Radionuclide metrology research for nuclear site decommissioning

NASA Astrophysics Data System (ADS)

Judge, S. M.; Regan, P. H.

2017-11-01

The safe and cost-effective decommissioning of legacy nuclear sites relies on accurate measurement of the radioactivity content of the waste materials, so that the waste can be assigned to the most appropriate disposal route. Such measurements are a new challenge for the science of radionuclide metrology which was established largely to support routine measurements on operating nuclear sites and other applications such as nuclear medicine. In this paper, we provide a brief summary of the international measurement system that is established to enable nuclear site operators to demonstrate that measurements are accurate, independent and fit for purpose, and highlight some of the projects that are underway to adapt the measurement system to meet the changing demands from the industry.

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes

DOE Office of Scientific and Technical Information (OSTI.GOV)

Goins, L.F.; Webb, J.R.; Cravens, C.D.

1992-09-01

This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

Nuclear facility decommissioning and site remedial actions: a selected bibliography

DOE Office of Scientific and Technical Information (OSTI.GOV)

Owen, P.T.; Knox, N.P.; Fielden, J.M.

This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uraniummore » Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.« less

BLENDED CALCIUM ALUMINATE-CALCIUM SULFATE CEMENT-BASED GROUT FOR P-REACTOR VESSEL IN-SITU DECOMMISSIONING

DOE Office of Scientific and Technical Information (OSTI.GOV)

Langton, C.; Stefanko, D.

2011-03-10

The objective of this report is to document laboratory testing of blended calcium aluminate - calcium hemihydrate grouts for P-Reactor vessel in-situ decommissioning. Blended calcium aluminate - calcium hemihydrate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout which has a pH greater than 12.4. In addition, blended calcium aluminate - calcium hemihydrate cement compositions can be formulated such that the primary cementitious phase is a stable crystalline material. A less alkaline material (pH {<=} 10.5) was desired to address a potential materials compatibilitymore » issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts [Wiersma, 2009a and b, Wiersma, 2010, and Serrato and Langton, 2010]. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere [Griffin, 2010, Stefanko, 2009 and Wiersma, 2009 and 2010, Bobbitt, 2010, respectively]. Radiolysis calculations are also provided in a separate document [Reyes-Jimenez, 2010].« less

Erosion at decommissioned road-stream crossings: case studies from three northern California watersheds

Treesearch

Sam A. Flanagan; David Fuller; Leonard Job; Sam Morrison

2012-01-01

Post-treatment erosion was observed for 41 decommissioned road stream crossings in three northern California watersheds. Sites were purposefully selected in order to characterize the nature and range of post-treatment erosional responses. Sites with the highest visible erosion were selected in order to better understand the dominant process and incorporate any...

26 CFR 1.468A-0T - Nuclear decommissioning costs; table of contents.

Code of Federal Regulations, 2010 CFR

2010-04-01

... 26 Internal Revenue 6 2010-04-01 2010-04-01 false Nuclear decommissioning costs; table of contents... (CONTINUED) INCOME TAX (CONTINUED) INCOME TAXES Taxable Year for Which Deductions Taken § 1.468A-0T Nuclear...) Definitions. (c) Special rules applicable to certain experimental nuclear facilities. § 1.468A-2TTreatment of...

Growth factor independence-1 antagonizes a p53-induced DNA damage response pathway in lymphoblastic leukemia

PubMed Central

Khandanpour, Cyrus; Phelan, James D.; Vassen, Lothar; Schütte, Judith; Chen, Riyan; Horman, Shane R.; Gaudreau, Marie-Claude; Krongold, Joseph; Zhu, Jinfang; Paul, William E.; Dührsen, Ulrich; Göttgens, Bertie; Grimes, H. Leighton; Möröy, Tarik

2013-01-01

Summary Most patients with acute lymphoblastic leukemia (ALL) fail current treatments highlighting the need for better therapies. Since oncogenic signaling activates a p53-dependent DNA-damage response and apoptosis, leukemic cells must devise appropriate countermeasures. We show here that growth factor independence 1 (Gfi1) can serve such a function, since Gfi1 ablation exacerbates p53 responses, and lowers the threshold for p53-induced cell death. Specifically, Gfi1 restricts p53 activity and expression of pro-apoptotic p53 targets such as Bax, Noxa (Pmaip1) and Puma (Bbc3). Subsequently, Gfi1 ablation cures mice from leukemia and limits the expansion of primary human T-ALL xenografts in mice. This suggests that targeting Gfi1 could improve the prognosis of patients with T-ALL or other lymphoid leukemias. PMID:23410974

Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors - Volume I.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gauntt, Randall O.; Mattie, Patrick D.

Sandia National Laboratories (SNL) has conducted an uncertainty analysis (UA) on the Fukushima Daiichi unit (1F1) accident progression with the MELCOR code. The model used was developed for a previous accident reconstruction investigation jointly sponsored by the US Department of Energy (DOE) and Nuclear Regulatory Commission (NRC). That study focused on reconstructing the accident progressions, as postulated by the limited plant data. This work was focused evaluation of uncertainty in core damage progression behavior and its effect on key figures-of-merit (e.g., hydrogen production, reactor damage state, fraction of intact fuel, vessel lower head failure). The primary intent of this studymore » was to characterize the range of predicted damage states in the 1F1 reactor considering state of knowledge uncertainties associated with MELCOR modeling of core damage progression and to generate information that may be useful in informing the decommissioning activities that will be employed to defuel the damaged reactors at the Fukushima Daiichi Nuclear Power Plant. Additionally, core damage progression variability inherent in MELCOR modeling numerics is investigated.« less

The psychometric properties of three self-report screening instruments for identifying frail older people in the community

PubMed Central

2010-01-01

Background Frailty is highly prevalent in older people. Its serious adverse consequences, such as disability, are considered to be a public health problem. Therefore, disability prevention in community-dwelling frail older people is considered to be a priority for research and clinical practice in geriatric care. With regard to disability prevention, valid screening instruments are needed to identify frail older people in time. The aim of this study was to evaluate and compare the psychometric properties of three screening instruments: the Groningen Frailty Indicator (GFI), the Tilburg Frailty Indicator (TFI) and the Sherbrooke Postal Questionnaire (SPQ). For validation purposes the Groningen Activity Restriction Scale (GARS) was added. Methods A questionnaire was sent to 687 community-dwelling older people (≥ 70 years). Agreement between instruments, internal consistency, and construct validity of instruments were evaluated and compared. Results The response rate was 77%. Prevalence estimates of frailty ranged from 40% to 59%. The highest agreement was found between the GFI and the TFI (Cohen's kappa = 0.74). Cronbach's alpha for the GFI, the TFI and the SPQ was 0.73, 0.79 and 0.26, respectively. Scores on the three instruments correlated significantly with each other (GFI - TFI, r = 0.87; GFI - SPQ, r = 0.47; TFI - SPQ, r = 0.42) and with the GARS (GFI - GARS, r = 0.57; TFI - GARS, r = 0.61; SPQ - GARS, r = 0.46). The GFI and the TFI scores were, as expected, significantly related to age, sex, education and income. Conclusions The GFI and the TFI showed high internal consistency and construct validity in contrast to the SPQ. Based on these findings it is not yet possible to conclude whether the GFI or the TFI should be preferred; data on the predictive values of both instruments are needed. The SPQ seems less appropriate for postal screening of frailty among community-dwelling older people. PMID:20353611

Activation calculation for the dismantling and decommissioning of a light water reactor using MCNP™ with ADVANTG and ORIGEN-S

NASA Astrophysics Data System (ADS)

Schlömer, Luc; Phlippen, Peter-W.; Lukas, Bernard

2017-09-01

The decommissioning of a light water reactor (LWR), which is licensed under § 7 of the German Atomic Energy Act, following the post-operational phase requires a comprehensive licensing procedure including in particular radiation protection aspects and possible impacts to the environment. Decommissioning includes essential changes in requirements for the systems and components and will mainly lead to the direct dismantling. In this context, neutron induced activation calculations for the structural components have to be carried out to predict activities in structures and to estimate future costs for conditioning and packaging. To avoid an overestimation of the radioactive inventory and to calculate the expenses for decommissioning as accurate as possible, modern state-of-the-art Monte-Carlo-Techniques (MCNP™) are applied and coupled with present-day activation and decay codes (ORIGEN-S). In this context ADVANTG is used as weight window generator for MCNP™ i. e. as variance reduction tool to speed up the calculation in deep penetration problems. In this paper the calculation procedure is described and the obtained results are presented with a validation along with measured activities and photon dose rates measured in the post-operational phase. The validation shows that the applied calculation procedure is suitable for the determination of the radioactive inventory of a nuclear power plant. Even the measured gamma dose rates in the post-operational phase at different positions in the reactor building agree within a factor of 2 to 3 with the calculation results. The obtained results are accurate and suitable to support effectively the decommissioning planning process.

Decision Support for Road Decommissioning and Restoration by Using Genetic Algorithms and Dynamic Programming

Treesearch

Elizabeth A. Eschenbach; Rebecca Teasley; Carlos Diaz; Mary Ann Madej

2007-01-01

Sediment contributions from unpaved forest roads have contributed to the degradation of anadromous fisheries streams in the Pacific Northwest.Efforts to reduce this degradation have included road decommissioning and road upgrading. These expensive activities have usually been implemented on a site specific basis without considering the sediment...

78 FR 19540 - Dominion Energy Kewaunee, Inc., Kewaunee Power Station Post-Shutdown Decommissioning Activities...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-04-01

... (KPS) Post-Shutdown Decommissioning Activities Report (PSDAR), Revision 0, on Wednesday, April 24, 2013... Management System (ADAMS) Accession No. ML13058A065. In a prior communication on November 2, 2012 (ADAMS... at KPS pending completion of a grid stability review by the Midwest Independent Transmission System...

ALARA and decommissioning: The Fort St. Vrain experience

DOE Office of Scientific and Technical Information (OSTI.GOV)

Borst, T.; Niehoff, M.; Zachary, M.

1995-03-01

The Fort St. Vrain Nuclear Generating Station, the first and only commercial High Temperature Gas Cooled Reactor to operate in the United States, completed initial fuel loading in late 1973 and initial startup in early 1974. Due to a series of non-nuclear technical problems, Fort St. Vrain never operated consistently, attaining a lifetime capacity factor of slightly less than 15%. In August of 1989, the decision was made to permanently shut down the plant due to control rod drive and steam generator ring header failures. Public Service Company of Colorado elected to proceed with early dismantlement (DECON) as opposed tomore » SAFSTOR on the bases of perceived societal benefits, rad waste, and exposure considerations, regulatory uncertainties associated with SAFSTOR, and cost. The decommissioning of Fort St. Vrain began in August of 1992, and is scheduled to be completed in early 1996. Decommissioning is being conducted by a team consisting of Westinghouse, MK-Ferguson, and Scientific Ecology Group. Public Service Company of Colorado as the licensee provides contract management and oversight of contractor functions. An aggressive program to maintain project radiation exposures As Low As Reasonably Achievable (ALARA) has been established, with the following program elements: temporary and permanent shielding contamination control; mockup training; engineering controls; worker awareness; integrated work package reviews communication; special instrumentation; video camera usage; robotics application; and project committees. To date, worker exposures have been less than project estimates. from the start of the project through Februrary of 1994, total exposure has been 98.666 person-rem, compared to the project estimate of 433 person-rem and goal of 347 person-rem. The presentation will discuss the site characterization efforts, the radiological performance indicator program, and the final site release survey plans.« less

Decommissioning the Fuel Process Building, a Shift in Paradigm for Terminating Safeguards on Process Holdup

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ivan R. Thomas

INMM Abstract 51st Annual Meeting Decommissioning the Fuel Process Building, a Shift in Paradigm for Terminating Safeguards on Process Holdup The Fuel Process Building at the Idaho Nuclear Technology and Engineering Center (INTEC) is being decommissioned after nearly four decades of recovering high enriched uranium from various government owned spent nuclear fuels. The separations process began with fuel dissolution in one of multiple head-ends, followed by three cycles of uranium solvent extraction, and ending with denitration of uranyl nitrate product. The entire process was very complex, and the associated equipment formed an extensive maze of vessels, pumps, piping, and instrumentationmore » within several layers of operating corridors and process cells. Despite formal flushing and cleanout procedures, an accurate accounting for the residual uranium held up in process equipment over extended years of operation, presented a daunting safeguards challenge. Upon cessation of domestic reprocessing, the holdup remained inaccessible and was exempt from measurement during ensuing physical inventories. In decommissioning the Fuel Process Building, the Idaho Cleanup Project, which operates the INTEC, deviated from the established requirements that all nuclear material holdup be measured and credited to the accountability books and that all nuclear materials, except attractiveness level E residual holdup, be transferred to another facility. Instead, the decommissioning involved grouting the process equipment in place, rather than measuring and removing the contained holdup for subsequent transfer. The grouting made the potentially attractiveness level C and D holdup even more inaccessible, thereby effectually converting the holdup to attractiveness level E and allowing for termination of safeguards controls. Prior to grouting the facility, the residual holdup was estimated by limited sampling and destructive analysis of solutions in process lines and by acceptable

Exploring environmental and economic trade-offs associated with aggregate recycling from decommissioned forest roads

Treesearch

Matthew P. Thompson; John Sessions

2010-01-01

Forest road decommissioning is a pro-active mechanism for preventing future habitat degradation and for increasing the likelihood of endangered salmonid survival in the western U.S. High implementation costs however preclude many desirable projects from being undertaken, especially on federally owned land. Previous research and real-world applications have demonstrated...

Cloning and sequencing the genes encoding goldfish and carp ependymin.

PubMed

Adams, D S; Shashoua, V E

1994-04-20

Ependymins (EPNs) are brain glycoproteins thought to function in optic nerve regeneration and long-term memory consolidation. To date, epn genes have been characterized in two orders of teleost fish. In this study, polymerase chain reactions (PCR) were used to amplify the complete 1.6-kb epn genes, gf-I and cc-I, from genomic DNA of Cypriniformes, goldfish and carp, respectively. Amplified bands were cloned and sequenced. Each gene consists of six exons and five introns. The exon portion of gf-I encodes a predicted 215-amino-acid (aa) protein previously characterized as GF-I, while cc-I encodes a predicted 215-aa protein 95% homologous to GF-I.

Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

DOE Office of Scientific and Technical Information (OSTI.GOV)

Owen, P.T.; Michelson, D.C.; Knox, N.P.

1987-09-01

The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program,more » Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations.« less

The application of decommissioned GEO satellites to CAPS

NASA Astrophysics Data System (ADS)

Fu, S. Y.; Wang, Z. R.; Shi, H. L.; Ma, L. H.

2018-06-01

To ensure the reliable service of geostationary earth orbiting (GEO) communication satellites during the period of in-orbit, the hardware design life of each system usually has some redundancies in contrast to the limited fuel used to keep the satellite position and attitude. After the brief analysis of the life of the satellite subsystems, the feasibility of turning the decommissioned GEO communication satellites into slightly inclined geosynchronous orbiting (SIGSO) satellites is proved. In addition, the role and the actual usage of SIGSO satellites in Chinese Area Positioning System (CAPS) are analysed and discussed, including the effect on the improvement of Position Dilution of Precision (PDOP) of the navigation constellation and the application to satellite communication system, thus the potential value of satellite material and devices is exploited.

Study on Evaluation of Project Management Data for Decommissioning of Uranium Refining and Conversion Plant - 12234

DOE Office of Scientific and Technical Information (OSTI.GOV)

Usui, Hideo; Izumo, Sari; Tachibana, Mitsuo

Some of nuclear facilities that would no longer be required have been decommissioned in JAEA (Japan Atomic Energy Agency). A lot of nuclear facilities have to be decommissioned in JAEA in near future. To implement decommissioning of nuclear facilities, it was important to make a rational decommissioning plan. Therefore, project management data evaluation system for dismantling activities (PRODIA code) has been developed, and will be useful for making a detailed decommissioning plan for an object facility. Dismantling of dry conversion facility in the uranium refining and conversion plant (URCP) at Ningyo-toge began in 2008. During dismantling activities, project management datamore » such as manpower and amount of waste generation have been collected. Such collected project management data has been evaluated and used to establish a calculation formula to calculate manpower for dismantling equipment of chemical process and calculate manpower for using a green house (GH) which was a temporary structure for preventing the spread of contaminants during dismantling. In the calculation formula to calculate project management data related to dismantling of equipment, the relation of dismantling manpower to each piece of equipment was evaluated. Furthermore, the relation of dismantling manpower to each chemical process was evaluated. The results showed promise for evaluating dismantling manpower with respect to each chemical process. In the calculation formula to calculate project management data related to use of the GH, relations of GH installation manpower and removal manpower to GH footprint were evaluated. Furthermore, the calculation formula for secondary waste generation was established. In this study, project management data related to dismantling of equipment and use of the GH were evaluated and analyzed. The project management data, manpower for dismantling of equipment, manpower for installation and removal of GH, and secondary waste generation from GH were

Implementation of 10 CFR 20.1406 Through Life Cycle Planning for Decommissioning

DOE Office of Scientific and Technical Information (OSTI.GOV)

O'Donnell, E.; Ott, W.R.

2008-01-15

The focus of this paper is on a regulatory guide (draft guide DG-4012) being developed by the Office of Nuclear Regulatory Research for the implementation of 10 CFR 20.1406. The draft guide was published in the Federal Register on July 31, 2007 for a 90 day public comment period. Besides being available in the Federal Register, it is also available electronically in NRC's agency data management system (ADAMS). The accession number is ML0712100110. 10 CFR 20.1406 requires license applicants, other than renewals, after August 20, 1997, '..to describe in the application how facility design and procedures for operation will minimize,more » to the extent practicable, contamination of the facility and the environment, facilitate eventual decommissioning, and minimize to the extent practicable, the generation of radioactive waste'. The intent of the regulation is to diminish the occurrence and severity of 'legacy sites' by taking measures that will reduce and control contamination and facilitate eventual decommissioning. 10 CFR 20.1406 is significant because it applies to all new facilities and in the very near future (perhaps as soon as the fall of 2007), the U.S. Nuclear Regulatory Commission (NRC) anticipates receiving one or more license applications for new nuclear power plants. The regulatory guide is intended to facilitate that licensing by providing suggestions of things an applicant can do to minimize contamination of the facility and the environment, minimize generation of waste, and to facilitate decommissioning. Over 100 different kinds of activities are covered by license applications submitted to the NRC. They do not all reflect the same potential for contamination of a facility and the environment, or for the generation of radioactive waste. Therefore, an applicant should use sound judgment to evaluate the potential for contamination and the consequences of such contamination in deciding on the extent to which this guide applies to any given facility or

Using probabilistic criteria in an assessment of the potential radiological consequences of the decommissioning of a nuclear research reactor

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wallner, Christian; Rall, Anna-Maria; Thummerer, Severin

In order to assess the risk of radiological consequences of incidents and accidents in nuclear facilities it is important to contemplate their frequency of occurrence. It has to be shown that incidents and accidents occur sufficiently seldom according to their radiological consequences i. e. the occurrence frequency of radiological doses has to be limited. This is even demanded by the German radiation protection ordinance (StrlSchV), which says that in nuclear facilities other than nuclear power plants (NPP) in operation and for decommissioning, the occurrence frequency of incidents and accidents shall be contemplated in order to prove the design of safetymore » measures and safety installations. Based on the ideas of the ICRP64, we developed a risk based assessment concept for nuclear facilities, which fulfils the requirements of the German regulations concerning dose limits in normal operation and design basis accidents. The general use of the concept is dedicated to nuclear facilities other than nuclear power plants (NPP) in operation and for decommissioning, where the regulation of risk assessment is less sophisticated. The concept specifies occurrence frequency limits for radiation exposure dose ranges, i. e. the occurrence frequency of incidents and accidents has to be limited according to their radiological effects. To apply this concept, scenarios of incidents and accidents are grouped in exposition classes according to their resulting potential effective dose to members of the general public. The occurrence frequencies of the incidents and accidents are summarized in each exposition class whereas the sum must not exceed the frequency limits mentioned above. In the following we introduce the application of this concept in the assessment of the potential radiological consequences of the decommissioning of a nuclear research reactor. We carried out this assessment for the licensing process of the decommissioning on behalf of German authorities. (authors)« less

Genetic trend for growth and wool performance in a closed flock of Bharat Merino sheep at sub temperate region of Kodai hills, Tamil Nadu.

PubMed

Mallick, P K; Thirumaran, S M K; Pourouchottamane, R; Rajapandi, S; Venkataramanan, R; Nagarajan, G; Murali, G; Rajendiran, A S

2016-03-01

The study was conducted at Southern Regional Research Center, ICAR-Central Sheep and Wool Research Institute (CSWRI), Mannavanur, Kodaikanal, Tamil Nadu to estimate genetic trends for birth weight (BWT), weaning weight (3WT), 6 months weight (6WT), and greasy fleece weight (GFY) in a Bharat Merino (BM) flock, where selection was practiced for 6WT and GFY. The data for this study represents a total of 1652 BM lambs; progeny of 144 sires spread over 15 years starting from 2000 to 2014, obtained from the BM flock of ICAR-SRRC (CSWRI), Mannavanur, Kodaikanal, Tamil Nadu, India. The genetic trends were calculated by regression of average predicted breeding values using software WOMBAT for the traits BWT, 3WT, 6WT and GFY versus the animal's birth year. The least square means were 3.28±0.02 kg, 19.08±0.23 kg, 25.00±0.35 kg and 2.13±0.07 kg for BWT, 3WT, 6WT and GFY, respectively. Genetic trends were positive and highly significant (p<0.01) for BWT, while the values for 3WT, 6WT and GFY though positive, were not significant. The estimates of genetic trends in BWT, 3WT, 6WT and GFY were 5 g, 0.8 g, 7 g and 0.3 g/year gain and the fit of the regression shows 55%, 22%, 42% and 12% coefficient of determination with the regressed value, respectively. In this study, estimated mean predicted breeding value (kg) in BWT and 3WT, 6WT and GFY were 0.067, 0.008, 0.036 and -0.003, respectively. Estimates of genetic trends indicated that there was a positive genetic improvement in all studied traits and selection would be effective for the improvement of body weight traits and GFY of BM sheep.

Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

DOE Office of Scientific and Technical Information (OSTI.GOV)

Michael R. Kruzic

2008-06-01

Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consentmore » Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

Application of Robotics in Decommissioning and Decontamination - 12536

DOE Office of Scientific and Technical Information (OSTI.GOV)

Banford, Anthony; Kuo, Jeffrey A.; Bowen, R.A.

Decommissioning and dismantling of nuclear facilities is a significant challenge worldwide and one which is growing in size as more plants reach the end of their operational lives. The strategy chosen for individual projects varies from the hands-on approach with significant manual intervention using traditional demolition equipment at one extreme to bespoke highly engineered robotic solutions at the other. The degree of manual intervention is limited by the hazards and risks involved, and in some plants are unacceptable. Robotic remote engineering is often viewed as more expensive and less reliable than manual approaches, with significant lead times and capital expenditure.more » However, advances in robotics and automation in other industries offer potential benefits for future decommissioning activities, with the high probability of reducing worker exposure and other safety risks as well as reducing the schedule and costs required to complete these activities. Some nuclear decommissioning tasks and facility environments are so hazardous that they can only be accomplished by exclusive use of robotic and remote intervention. Less hazardous tasks can be accomplished by manual intervention and the use of PPE. However, PPE greatly decreases worker productivity and still exposes the worker to both risk and dose making remote operation preferable to achieve ALARP. Before remote operations can be widely accepted and deployed, there are some economic and technological challenges that must be addressed. These challenges will require long term investment commitments in order for technology to be: - Specifically developed for nuclear applications; - At a sufficient TRL for practical deployment; - Readily available as a COTS. Tremendous opportunities exist to reduce cost and schedule and improve safety in D and D activities through the use of robotic and/or tele-operated systems. - Increasing the level of remote intervention reduces the risk and dose to an operator. Better

2016 Annual Inspection and Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site, July 2016

DOE Office of Scientific and Technical Information (OSTI.GOV)

Zimmerman, Brian; Miller, Michele

This report presents the findings of the annual inspection and radiological survey of the Piqua, Ohio, Decommissioned Reactor Site (site). The decommissioned nuclear power demonstration facility was inspected and surveyed on April 15, 2016. The site, located on the east bank of the Great Miami River in Piqua, Ohio, was in fair physical condition. There is no requirement for a follow-up inspection, partly because City of Piqua (City) personnel participated in a March 2016 meeting to address reoccurring safety concerns. Radiological survey results from 104 locations revealed no removable contamination. One direct beta activity reading in a floor drain onmore » the 56-foot level (1674 disintegrations per minute [dpm]/100 square centimeters [cm2]) exceeded the minimum detectable activity (MDA). Beta activity has been detected in the past at this floor drain. The reading was well below the action level of 5000 dpm/100 cm2.« less

Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

DOE Office of Scientific and Technical Information (OSTI.GOV)

Owen, P.T.; Michelson, D.C.; Knox, N.P.

1985-09-01

This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Majormore » chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.« less

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program

DOE Office of Scientific and Technical Information (OSTI.GOV)

Goins, L.F.; Webb, J.R.; Cravens, C.D.

1992-09-01

This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

77 FR 58591 - Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-09-21

... NUCLEAR REGULATORY COMMISSION [NRC-2010-0362] Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities AGENCY: Nuclear Regulatory Commission... Commission) has issued for public comment a document entitled: NUREG-1307 Revision 15, ``Report on Waste...

Three-dimensional numerical simulations of methane gas migration from decommissioned hydrocarbon production wells into shallow aquifers

NASA Astrophysics Data System (ADS)

Roy, N.; Molson, J.; Lemieux, J.-M.; Van Stempvoort, D.; Nowamooz, A.

2016-07-01

Three-dimensional numerical simulations are used to provide insight into the behavior of methane as it migrates from a leaky decommissioned hydrocarbon well into a shallow aquifer. The conceptual model includes gas-phase migration from a leaky well, dissolution into groundwater, advective-dispersive transport and biodegradation of the dissolved methane plume. Gas-phase migration is simulated using the DuMux multiphase simulator, while transport and fate of the dissolved phase is simulated using the BIONAPL/3D reactive transport model. Methane behavior is simulated for two conceptual models: first in a shallow confined aquifer containing a decommissioned leaky well based on a monitored field site near Lindbergh, Alberta, Canada, and secondly on a representative unconfined aquifer based loosely on the Borden, Ontario, field site. The simulations show that the Lindbergh site confined aquifer data are generally consistent with a 2 year methane leak of 2-20 m3/d, assuming anaerobic (sulfate-reducing) methane oxidation and with maximum oxidation rates of 1 × 10-5 to 1 × 10-3 kg/m3/d. Under the highest oxidation rate, dissolved methane decreased from solubility (110 mg/L) to the threshold concentration of 10 mg/L within 5 years. In the unconfined case with the same leakage rate, including both aerobic and anaerobic methane oxidation, the methane plume was less extensive compared to the confined aquifer scenarios. Unconfined aquifers may therefore be less vulnerable to impacts from methane leaks along decommissioned wells. At other potential leakage sites, site-specific data on the natural background geochemistry would be necessary to make reliable predictions on the fate of methane in groundwater.

Decommissioning of eight surplus production reactors at the Hanford Site, Richland, Washington. Addendum (Final Environmental Impact Statement)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1992-12-01

The first section of this volume summarizes the content of the draft environmental impact statement (DEIS) and this Addendum, which together constitute the final environmental impact statement (FEIS) prepared on the decommissioning of eight surplus plutonium production reactors at Hanford. The FEIS consists of two volumes. The first volume is the DEIS as written. The second volume (this Addendum) consists of a summary; Chapter 9, which contains comments on the DEIS and provides DOE`s responses to the comments; Appendix F, which provides additional health effects information; Appendix K, which contains costs of decommissioning in 1990 dollars; Appendix L, which containsmore » additional graphite leaching data; Appendix M, which contains a discussion of accident scenarios; Appendix N, which contains errata; and Appendix 0, which contains reproductions of the letters, transcripts, and exhibits that constitute the record for the public comment period.« less

Prioritization methodology for the decommissioning of nuclear facilities: a study case on the Iraq former nuclear complex.

PubMed

Jarjies, Adnan; Abbas, Mohammed; Monken Fernandes, Horst; Wong, Melanie; Coates, Roger

2013-05-01

There are a number of sites in Iraq which have been used for nuclear activities and which contain potentially significant amounts of radioactive waste. The principal nuclear site being Al-Tuwaitha. Many of these sites suffered substantial physical damage during the Gulf Wars and have been subjected to subsequent looting. All require decommissioning in order to ensure both radiological and non-radiological safety. However, it is not possible to undertake the decommissioning of all sites and facilities at the same time. Therefore, a prioritization methodology has been developed in order to aid the decision-making process. The methodology comprises three principal stages of assessment: i) a quantitative surrogate risk assessment ii) a range of sensitivity analyses and iii) the inclusion of qualitative modifying factors. A group of Tuwaitha facilities presented the highest risk among the evaluated ones, followed by a middle ranking grouping of Tuwaitha facilities and some other sites, and a relatively large group of lower risk facilities and sites. The initial order of priority is changed when modifying factors are taken into account. It has to be considered the Iraq's isolation from the international nuclear community over the last two decades and the lack of experienced personnel. Therefore it is appropriate to initiate decommissioning operations on selected low risk facilities at Tuwaitha in order to build capacity and prepare for work to be carried out in more complex and potentially high hazard facilities. In addition it is appropriate to initiate some prudent precautionary actions relating to some of the higher risk facilities. Copyright © 2012 Elsevier Ltd. All rights reserved.

30 CFR 250.1006 - How must I decommission and take out of service a DOI pipeline?

Code of Federal Regulations, 2011 CFR

2011-07-01

... a DOI pipeline? 250.1006 Section 250.1006 Mineral Resources BUREAU OF OCEAN ENERGY MANAGEMENT... out of service a DOI pipeline? (a) The requirements for decommissioning pipelines are listed in § 250.1750 through § 250.1754. (b) The table in this section lists the requirements if you take a DOI...

CCA retention and its effects on the bonding performance of decommissioned treated wood: a preliminary study

Treesearch

Cheng Piao; Todd F. Shupe; Mark Gibson; Chung Y. Hse

2009-01-01

Chromated copper arsenate (CCA) continues to be widely used as a wood preservative for industrial uses in the U.S. Disposal of treated wood is a potential long-term environmental liability. Current practices for disposing of decommissioned preservative-treated wood include landfilling and incineration, which are increasingly impractical due to environmental...

PROCESS KNOWLEDGE DATA GATHERING AND REPORTING IN SUPPORT OF DECOMMISSIONING Health Physics Society Annual Meeting West Palm Beach, Florida June 27, 2011

DOE Office of Scientific and Technical Information (OSTI.GOV)

David A. King

2011-06-27

Summary of recent ORAU decommissioning activities at the Oak Ridge National Laboratory (ORNL) and the East Tennessee Technology Park (ETTP). Project objective was to generate approved Waste Lot Profiles for legacy facilities scheduled for demolition and shipment to the Environmental Management Waste Management Facility (EMWMF) or appropriate alternate facility. The form and content of process knowledge (PK) reports were developed with input from the EMWMF Waste Acceptance Criteria (WAC) Attainment Team and regulators. PK may be defined as the knowledge of the design and the history of operations that occurs during the life cycle of a facility (paraphrased from SRNLmore » guidance) - similar to the MARSSIM historical site assessment. Some types of PK data used to decommission ORNL and ETTP facilities include: (1) Design drawings; (2) Historical documents [e.g., History of the Oak Ridge National Laboratory by Thomas (1963) and A Brief History of the Chemical Technical Division (ORNL/M-2733)]; (3) Historical photographs; (4) Radiological survey reports; (5) Facility-specific databases - (a) Spill history, (b) Waste Information Tracking System (WITS), and (c) Hazardous Materials Management Information System (HMMIS); (6) Facility walkdown summary reports; and (7) Living memory data. Facility walkdowns are critical for worker safety planning and to assure on-the-ground-conditions match historical descriptions. For Oak Ridge operations, investigators also document the nature and number of items requiring special handling or disposition planning, such as the following: (1) Items containing polychlorinated biphenyls, asbestos, lead, or refrigerants; (2) Items with physical WAC restriction (e.g., large items, pipes, and concrete); and (3) Too 'hot' for EMWMF. Special emphasis was made to interview facility managers, scientists, technicians, or anyone with direct knowledge of process-related activities. Interviews often led to more contact names and reports but also

30 CFR 250.1006 - How must I decommission and take out of service a DOI pipeline?

Code of Federal Regulations, 2010 CFR

2010-07-01

... a DOI pipeline? 250.1006 Section 250.1006 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT... and Pipeline Rights-of-Way § 250.1006 How must I decommission and take out of service a DOI pipeline...) The table in this section lists the requirements if you take a DOI pipeline out of service: If you...

30 CFR 285.902 - What are the general requirements for decommissioning for facilities authorized under my SAP, COP...

Code of Federal Regulations, 2011 CFR

2011-07-01

... BUREAU OF OCEAN ENERGY MANAGEMENT, REGULATION, AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF Decommissioning... facilities, projects, cables, pipelines, and obstructions; (2) Clear the seafloor of all obstructions created...

Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 5

DOE Office of Scientific and Technical Information (OSTI.GOV)

Owen, P.T.; Knox, N.P.; Chilton, B.D.

1984-09-01

This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department ofmore » Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms.« less

Task 21 - Development of Systems Engineering Applications for Decontamination and Decommissioning Activities

DOE Office of Scientific and Technical Information (OSTI.GOV)

Erickson, T.A.

1998-11-01

The objectives of this task are to: Develop a model (paper) to estimate the cost and waste generation of cleanup within the Environmental Management (EM) complex; Identify technologies applicable to decontamination and decommissioning (D and D) operations within the EM complex; Develop a database of facility information as linked to project baseline summaries (PBSs). The above objectives are carried out through the following four subtasks: Subtask 1--D and D Model Development, Subtask 2--Technology List; Subtask 3--Facility Database, and Subtask 4--Incorporation into a User Model.

10 CFR 40.42 - Expiration and termination of licenses and decommissioning of sites and separate buildings or...

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas. 40.42 Section 40.42 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF SOURCE MATERIAL Licenses § 40.42 Expiration and termination of licenses and...

10 CFR 70.38 - Expiration and termination of licenses and decommissioning of sites and separate buildings or...

Code of Federal Regulations, 2010 CFR

2010-01-01

... increase potential health and safety impacts to workers or to the public, such as in any of the following... provided by Commission Order. (c) Each specific license continues in effect, beyond the expiration date if... licensee shall maintain in effect all decommissioning financial assurances established by the licensee...

10 CFR 40.42 - Expiration and termination of licenses and decommissioning of sites and separate buildings or...

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 1 2014-01-01 2014-01-01 false Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas. 40.42 Section 40.42 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF SOURCE MATERIAL Licenses § 40.42 Expiration and termination of licenses and...

10 CFR 40.42 - Expiration and termination of licenses and decommissioning of sites and separate buildings or...

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 1 2012-01-01 2012-01-01 false Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas. 40.42 Section 40.42 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF SOURCE MATERIAL Licenses § 40.42 Expiration and termination of licenses and...

10 CFR 40.42 - Expiration and termination of licenses and decommissioning of sites and separate buildings or...

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 1 2013-01-01 2013-01-01 false Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas. 40.42 Section 40.42 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF SOURCE MATERIAL Licenses § 40.42 Expiration and termination of licenses and...

10 CFR 40.42 - Expiration and termination of licenses and decommissioning of sites and separate buildings or...

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 1 2011-01-01 2011-01-01 false Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas. 40.42 Section 40.42 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF SOURCE MATERIAL Licenses § 40.42 Expiration and termination of licenses and...

10 CFR 72.54 - Expiration and termination of licenses and decommissioning of sites and separate buildings or...

Code of Federal Regulations, 2010 CFR

2010-01-01

... conduct of decommissioning operations and presents no undue risk from radiation to the public health and... final radiation survey; and (5) An updated detailed cost estimate for the chosen alternative for... accordance with the regulations in this chapter, and will not be inimical to the common defense and security...

10 CFR 30.36 - Expiration and termination of licenses and decommissioning of sites and separate buildings or...

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 1 2012-01-01 2012-01-01 false Expiration and termination of licenses and decommissioning of sites and separate buildings or outdoor areas. 30.36 Section 30.36 Energy NUCLEAR REGULATORY... section if the Commission determines that the alternative schedule is necessary to the effective conduct...

Construct validity of the Groningen Frailty Indicator established in a large sample of home-dwelling elderly persons: Evidence of stability across age and gender.

PubMed

Peters, L L; Boter, H; Burgerhof, J G M; Slaets, J P J; Buskens, E

2015-09-01

The primary objective of the present study was to evaluate the validity of the Groningen Frailty Indicator (GFI) in a sample of Dutch elderly persons participating in LifeLines, a large population-based cohort study. Additional aims were to assess differences between frail and non-frail elderly and examine which individual characteristics were associated with frailty. By December 2012, 5712 elderly persons were enrolled in LifeLines and complied with the inclusion criteria of the present study. Mann-Whitney U or Kruskal-Wallis tests were used to assess the variability of GFI-scores among elderly subgroups that differed in demographic characteristics, morbidity, obesity, and healthcare utilization. Within subgroups Kruskal-Wallis tests were also used to examine differences in GFI-scores across age groups. Multivariate logistic regression analyses were performed to assess associations between individual characteristics and frailty. The GFI discriminated between subgroups: statistically significantly higher GFI-median scores (interquartile range) were found in e.g. males (1 [0-2]), the oldest old (2 [1-3]), in elderly who were single (1 [0-2]), with lower socio economic status (1 [0-3]), with increasing co-morbidity (2 [1-3]), who were obese (2 [1-3]), and used more healthcare (2 [1-4]). Overall age had an independent and statistically significant association with GFI scores. Compared with the non-frail, frail elderly persons experienced statistically significantly more chronic stress and more social/psychological related problems. In the multivariate logistic regression model, psychological morbidity had the strongest association with frailty. The present study supports the construct validity of the GFI and provides an insight in the characteristics of (non)frail community-dwelling elderly persons participating in LifeLines. Copyright © 2015 Elsevier Inc. All rights reserved.

30 CFR 285.1018 - Who is responsible for decommissioning an OCS facility subject to an Alternate Use RUE?

Code of Federal Regulations, 2011 CFR

2011-07-01

... ENERGY MANAGEMENT, REGULATION, AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR OFFSHORE RENEWABLE ENERGY ALTERNATE USES OF EXISTING FACILITIES ON THE OUTER CONTINENTAL SHELF Rights of Use and Easement for Energy- and Marine-Related Activities Using Existing OCS Facilities Decommissioning An Alternate Use Rue § 285...

An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Boing, L.E.; Henley, D.R.; Manion, W.J.

1989-12-01

Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document inmore » their evaluation process. 73 refs., 26 figs., 69 tabs.« less

Calder Hall Cooling Tower Demolition: Landmark Milestone for Decommissioning at Sellafield

DOE Office of Scientific and Technical Information (OSTI.GOV)

Williamson, E.J.

2008-07-01

September 2007 saw a very visible change to the Sellafield site following the culmination of a major decommissioning project; the demolition of the four Calder Hall cooling towers. A key part of the UK's nuclear industrial heritage, Calder Hall, the world's first commercial nuclear power station, was opened by Her Majesty Queen Elizabeth II in October 1953 and continued to generate electricity until its closure in 2003. Following the decision to decommission the Calder Hall site, explosive demolition was identified as the safest and most cost effective route for the removal of the towers. The technique, involving the placement ofmore » explosive in 60% of the circumference of both shell and legs, is a tried and tested method which had already been used successfully in more than 200 cooling towers in the UK in the last 30 years. The location and composition of the four 88 metre high towers also created additional challenges. Situated only 40 metres away from the UK's only nuclear Fuel Handling Plant, as well as other sensitive structures on the Sellafield site, the project had to address the impact of a number of key areas, including dust, ground vibration and air over pressure, to ensure that the demolition could be carried out safely and without significant impact on other operational areas on the site. At the same time, the towers had to be prepared for demolition in a way that minimised the amounts of radioactive or hazardous waste materials arising. This paper follows the four year journey from the initial decision to demolish the towers right through to the demolition itself as well as the clean up of the site post demolition. It will also consider the massive programme of work necessary not only to carry out the physical work safely but also to gain regulatory confidence and stakeholder support to carry out the project successfully. In summary: The demolition of the four Calder Hall cooling towers was a highly visible symbol of the changes that are

76 FR 3856 - Airworthiness Directives; The Boeing Company Model 737-100, -200, -200C, -300, -400, and -500...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-01-21

... new relays having a GFI feature, performing certain bonding resistance measurements, and modifying... with new relays having a GFI feature, Doing certain bonding resistance measurements to verify certain... relay module assemblies and bond resistance measurements. In addition, we have reviewed Section 9 of...

Waste Technology Engineering Laboratory (324 building)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kammenzind, D.E.

The 324 Facility Standards/Requirements Identification Document (S/RID) is comprised of twenty functional areas. Two of the twenty functional areas (Decontamination and Decommissioning and Environmental Restoration) were determined as nonapplicable functional areas and one functional area (Research and Development and Experimental Activities) was determined applicable, however, requirements are found in other functional areas and will not be duplicated. Each functional area follows as a separate chapter, either containing the S/RID or a justification for nonapplicability. The twenty functional areas listed below follow as chapters: 1. Management Systems; 2. Quality Assurance; 3. Configuration Management; 4. Training and Qualification; 5. Emergency Management; 6.more » Safeguards and Security; 7. Engineering Program; 8. Construction; 9. Operations; 10. Maintenance; 11. Radiation Protection; 12. Fire Protection; 13. Packaging and Transportation; 14. Environmental Restoration; 15. Decontamination and Decommissioning; 16. Waste Management; 17. Research and Development and Experimental Activities; 18. Nuclear Safety; 19. Occupational Safety and Health; 20. Environmental Protection.« less

A Strategy for Skills to meet the demands of Nuclear Decommissioning and Clean-up in the UK

DOE Office of Scientific and Technical Information (OSTI.GOV)

Brownridge, M.; Ensor, B.

The NDA remit as set out within the Energy Act includes - 'to ensure the availability of skills required to deliver the overall decommissioning and nuclear clean-up mission'. The NDA approach to meeting their statutory obligation is by: - finding the best ways of re-training, re-skilling or re-deploying people in a way that encourages a more flexible workforce; - identifying and communicating the skills and workforce requirements to deliver the mission; and - developing the infrastructure and capability initiatives in line with long term needs, for example, a National Skills Academy for Nuclear, Nuclear Institute, National Graduate Scheme, and -more » developing locally specific provision. Firstly, NDA has set the requirement for nuclear sites to write down within the Life Time Plans (LTP), at a high level, their Site Skills Strategies; furthermore, a National Skills Working Group has been established to develop tactical cross sector solutions to support the NDA's Skills Strategy. In support of the short, medium and long term needs to meet demands of the NDA sites and the nuclear decommissioning sector, as well as being aware of the broader nuclear sector, investments have been made in infrastructure and skills programmes such as: - A National Skills Academy for Nuclear - including UK wide representation of the whole nuclear sector; - A Nuclear Institute in partnership with the University of Manchester focussing on world class research and skills in Radiation Sciences and Decommissioning Engineering; - Post Graduate sponsorship for decommissioning related projects; - A National Graduate Scheme partnership with nuclear related employers; - Vocational qualifications and Apprenticeship Schemes - Engaging 14-19 year old students to encourage the take up of Science related subjects; and - A sector wide 'Skills Passport'. In conclusion: The skills challenge has many dimensions but requires addressing due to the clear link to improved business performance and the

Site Environmental Report for Calendar Year 2005. DOE Operations at The Boeing Company, Santa Susana Field Laboratory, Area IV

DOE Office of Scientific and Technical Information (OSTI.GOV)

None

2006-09-30

This annual report describes the environmental monitoring programs related to the Department of Energy’s (DOE) activities at the Santa Susana Field Laboratory (SSFL) facility located in Ventura County, California during 2005. Part of the SSFL facility, known as Area IV, had been used for DOE’s activities since the 1950s. A broad range of energy related research and development (R&D) projects, including nuclear technologies projects, was conducted at the site. All the nuclear R&D operations in Area IV ceased in 1988. Current efforts are directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and closure of facilities used formore » liquid metal research.« less

78 FR 11688 - Notice of Issuance of Amendment to Facility License R-77 Incorporating a Decommissioning Plan for...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-02-19

... Reactor at the State University of New York at Buffalo AGENCY: Nuclear Regulatory Commission. ACTION... University of New York at Buffalo (UB) decommissioning plan (DP) by amendment to the Facility License R-77... in the NRC Library at http://www.nrc.gov/reading-rm/adams.html . To begin the search, select ``ADAMS...

77 FR 22327 - Draft Guidance for Industry on New Animal Drugs and New Animal Drug Combination Products...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-04-13

... or on Medicated Feed or Drinking Water of Food-Producing Animals: Recommendations for Drug Sponsors for Voluntarily Aligning Product Use Conditions With GFI 209; Availability AGENCY: Food and Drug... availability of a draft guidance for industry (draft GFI 213) entitled ``New Animal Drugs and New Animal Drug...

Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9

DOE Office of Scientific and Technical Information (OSTI.GOV)

Owen, P.T.; Knox, N.P.; Michelson, D.C.

1988-09-01

The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's remedial action programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilitiesmore » Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626

78 FR 21230 - Airworthiness Directives; Airbus Airplanes

Federal Register 2010, 2011, 2012, 2013, 2014

2013-04-10

... Failed Post-Modification Operational Test After accomplishment of the modification specified in paragraph... of the GFI or deactivation of the associated fuel pump following failure of any post-modification operational test of the GFI. We are issuing this AD to prevent the potential of ignition sources inside fuel...

77 FR 20505 - Airworthiness Directives; The Boeing Company Airplanes

Federal Register 2010, 2011, 2012, 2013, 2014

2012-04-05

... Company Model 757 airplanes. This AD requires replacing the power control relays for the fuel boost pumps and override pumps with new relays having a ground fault interrupter (GFI) feature. This AD also requires an electrical bonding resistance measurement for certain GFI relays to verify that certain bonding...

Long-lived radionuclides in residues from operation and decommissioning of nuclear power plants

NASA Astrophysics Data System (ADS)

López-Gutiérrez, J. M.; Gómez-Guzmán, J. M.; Chamizo, E.; Peruchena, J. I.; García-León, M.

2013-01-01

Radioactive residues, in order to be classified as Low-Level Waste (LLW), need to fulfil certain conditions; the limitation of the maximum activity from long-lived radionuclides is one of these requirements. In order to verify compliance to this limitation, the abundance of these radionuclides in the residue must be determined. However, performing this determination through radiometric methods constitutes a laborious task. In this work, 129I concentrations, 239+240Pu activities, and 240Pu/239Pu ratios are determined in low-level radioactive residues, including resins and dry sludge, from nuclear power plants in Spain. The use of Accelerator Mass Spectrometry (AMS) enables high sensitivities to be achieved, and hence these magnitudes can be re determined with good precision. Results present a high dispersion between the 129I and 239+240Pu activities found in various aliquots of the same sample, which suggests the existence of a mixture of resins with a variety of histories in the same container. As a conclusion, it is shown that activities and isotopic ratios can provide information on the processes that occur in power plants throughout the history of the residues. Furthermore, wipes from the monitoring of surface contamination of the José Cabrera decommissioning process have been analyzed for 129I determination. The wide range of measured activities indicates an effective dispersal of 129I throughout the various locations within a nuclear power plant. Not only could these measurements be employed in the contamination monitoring of the decommissioning process, but also in the modelling of the presence of other iodine isotopes.

Environmental Problems Associated with Decommissioning of Chernobyl Power Plant Cooling Pond

NASA Astrophysics Data System (ADS)

Foley, T. Q.; Oskolkov, B. Y.; Bondarkov, M. D.; Gashchak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.; Jannik, G. T.; Farfan, E. B.; Marra, J. C.

2009-12-01

Decommissioning of nuclear power plants and other nuclear fuel cycle facilities associated with residual radioactive contamination is a fairly pressing issue. Significant problems may result from decommissioning of cooling ponds. The Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond is one of the largest self-contained bodies of water in the Chernobyl Region and Ukrainian Polesye with a water surface area of 22.9 km2. The major hydrological feature of the ChNPP Cooling Pond is that its water level is 6-7 m higher than the water level in the Pripyat River and water losses due to seepage and evaporation are replenished by pumping water from the Pripyat River. In 1986, the accident at the ChNPP #4 Reactor Unit significantly contaminated the ChNPP Cooling Pond. According to the 2001 data, the total radionuclide inventory in the ChNPP Cooling Pond bottom deposits was as follows: 16.28 ± 2.59 TBq for 137Cs; 2.4 ± 0.48 TBq for 90Sr, and 0.00518 ± 0.00148 TBq for 239+240Pu. Since ChNPP is being decommissioned, the ChNPP Cooling Pond of such a large size will no longer be needed and cost effective to maintain. However, shutdown of the water feed to the Pond would expose the contaminated bottom deposits and change the hydrological features of the area, destabilizing the radiological and environmental situation in the entire region in 2007 - 2008, in order to assess potential consequences of draining the ChNPP Cooling Pond, the authors conducted preliminary radio-ecological studies of its shoreline ecosystems. The radioactive contamination of the ChNPP Cooling Pond shoreline is fairly variable and ranges from 75 to 7,500 kBq/m2. Three areas with different contamination levels were selected to sample soils, vegetation, small mammals, birds, amphibians, and reptilians in order to measure their 137Cs and 90Sr content. Using the ERICA software, their dose exposures were estimated. For the 2008 conditions, the estimated dose rates were found to be as follows: amphibians - 11

Effects of road decommissioning on carbon stocks, losses, and emissions in north coastal California

USGS Publications Warehouse

Madej, Mary Ann; Seney, Joseph; van Mantgem, Philip

2013-01-01

During the last 3 decades, many road removal projects have been implemented on public and private lands in the United States to reduce erosion and other impacts from abandoned or unmaintained forest roads. Although effective in decreasing sediment production from roads, such activities have a carbon (C) cost as well as representing a carbon savings for an ecosystem. We assessed the carbon budget implications of 30 years of road decommissioning in Redwood National Park in north coastal California. Road restoration techniques, which evolved during the program, were associated with various carbon costs and savings. Treatment of 425 km of logging roads from 1979 to 2009 saved 72,000 megagrams (Mg) C through on-site soil erosion prevention, revegetation, and soil development on formerly compacted roads. Carbon sequestration will increase in time as forests and soils develop more fully on the restored sites. The carbon cost for this road decommissioning work, based on heavy equipment and vehicle fuel emissions, short-term soil loss, and clearing of vegetation, was 23,000 Mg C, resulting in a net carbon savings of 49,000 Mg C to date. Nevertheless, the degree to which soil loss is a carbon sink or source in steep mountainous watersheds needs to be further examined. The ratio of carbon costs to savings will differ by ecosystem and road removal methodology, but the procedure outlined here to assess carbon budgets on restoration sites should be transferable to other systems.

Science to Support DOE Site Cleanup: The Pacific Northwest National Laboratory Environmental Management Science Program Awards-Fiscal Year 1999 Mid-Year Progress Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Peurrung, L.M.

1999-06-30

Pacific Northwest National Laboratory was awarded ten Environmental Management Science Program (EMSP) research grants in fiscal year 1996, six in fiscal year 1997, and eight in fiscal year 1998. This section summarizes how each grant addresses significant U.S. Department of Energy (DOE) cleanup issues, including those at the Hanford Site. The technical progress made to date in each of these research projects is addressed in more detail in the individual progress reports contained in this document. This research is focused primarily in five areas: Tank Waste Remediation, Decontamination and Decommissioning, Spent Nuclear Fuel and Nuclear Materials, Soil and Groundwater Cleanmore » Up, and Health Effects.« less

76 FR 28 - Airworthiness Directives; The Boeing Company Model 757 Airplanes

Federal Register 2010, 2011, 2012, 2013, 2014

2011-01-03

... relays having a ground fault interrupt (GFI) feature. That NPRM was prompted by results from fuel system..., -200CB, and -300 series airplanes. That NPRM was published in the Federal Register on October 19, 2009... pumps and override pumps with new relays having a ground fault interrupt (GFI) feature. Actions Since...

Generation of an activation map for decommissioning planning of the Berlin Experimental Reactor-II

NASA Astrophysics Data System (ADS)

Lapins, Janis; Guilliard, Nicole; Bernnat, Wolfgang

2017-09-01

The BER-II is an experimental facility with 10 MW that was operated since 1974. Its planned operation will end in 2019. To support the decommissioning planning, a map with the overall distribution of relevant radionuclides has to be created according to the state of the art. In this paper, a procedure to create these 3-d maps using a combination of MCNP and deterministic methods is presented. With this approach, an activation analysis is performed for the whole reactor geometry including the most remote parts of the concrete shielding.

Considerations in evaluating potential socioeconomic impacts of offshore platform decommissioning in California.

PubMed

Kruse, Sarah A; Bernstein, Brock; Scholz, Astrid J

2015-10-01

The 27 oil and gas platforms offshore southern California will eventually reach the end of their useful lifetimes (estimated between 2015 and 2030) and will be decommissioned. Current state and federal laws and regulations allow for alternative uses in lieu of the complete removal required in existing leases. Any decommissioning pathway will create a complex mix of costs, benefits, opportunities, and constraints for multiple user groups. To assist the California Natural Resources Agency in understanding these issues, we evaluated the potential socioeconomic impacts of the 2 most likely options: complete removal and partial removal of the structure to 85 feet below the waterline with the remaining structure left in place as an artificial reef-generally defined as a manmade structure with some properties that mimic a natural reef. We estimated impacts on commercial fishing, commercial shipping, recreational fishing, nonconsumptive boating, and nonconsumptive SCUBA diving. Available data supported quantitative estimates for some impacts, semiquantitative estimates for others, and only qualitative approximations of the direction of impact for still others. Even qualitative estimates of the direction of impacts and of user groups' likely preferred options have been useful to the public and decision makers and provided valuable input to the project's integrative decision model. Uncertainty surrounds even qualitative estimates of the likely direction of impact where interactions between multiple impacts could occur or where user groups include subsets that would experience the same option differently. In addition, we were unable to quantify effects on ecosystem value and on the larger regional ecosystem, because of data gaps on the population sizes and dynamics of key species and the uncertainty surrounding the contribution of platforms to available hard substrate and related natural populations offshore southern California. © 2015 SETAC.

The Importance of Building and Enhancing Worldwide Industry Cooperation in the Areas of Radiological Protection, Waste Management and Decommissioning

DOE Office of Scientific and Technical Information (OSTI.GOV)

Saint-Pierre, S.

2006-07-01

The slow or stagnant rate of nuclear power generation development in many developed countries over the last two decades has resulted in a significant shortage in the population of mid-career nuclear industry professionals. This shortage is even more pronounced in some specific areas of expertise such as radiological protection, waste management and decommissioning. This situation has occurred at a time when the renaissance of nuclear power and the globalization of the nuclear industry are steadily gaining momentum and when the industry's involvement in international and national debates in these three fields of expertise (and the industry's impact on these debates)more » is of vital importance. This paper presents the World Nuclear Association (WNA) approach to building and enhancing worldwide industry cooperation in radiological protection, waste management and decommissioning, which is manifested through the activities of the two WNA working groups on radiological protection (RPWG) and on waste management and decommissioning (WM and DWG). This paper also briefly describes the WNA's participatory role, as of summer 2005, in the International Atomic Energy Agency (IAEA) standard development committees on radiation safety (RASSC), waste safety (WASSC) and nuclear safety (NUSSC). This participation provides the worldwide nuclear industry with an opportunity to be part of IAEA's discussions on shaping changes to the control regime of IAEA safety standards. The review (and the prospect of a revision) of IAEA safety standards, which began in October 2005, makes this WNA participation and the industry ' s involvement at the national level timely and important. All of this excellent industry cooperation and team effort is done through 'collegial' exchanges between key industry experts, which help tackle important issues more effectively. The WNA is continuously looking to enhance its worldwide industry representation in these fields of expertise through the RPWG and WM

A comparison of three erosion control mulches on decommissioned forest road corridors in the northern Rocky Mountains, United States

Treesearch

R. B. Foltz

2012-01-01

This study tested the erosion mitigation effectiveness of agricultural straw and two wood-based mulches for four years on decommissioned forest roads. Plots were installed on the loosely consolidated, bare soil to measure sediment production, mulch cover, and plant regrowth. The experimental design was a repeated measures, randomized block on two soil types common in...

Progress on the decommissioning of Zion nuclear generating station

DOE Office of Scientific and Technical Information (OSTI.GOV)

Moloney, B. P.; Hess, J.

2013-07-01

The decommissioning of the twin 1040 MWe PWRs at Zion, near Chicago USA is a ground breaking programme. The original owner, Exelon Nuclear Corporation, transferred the full responsibility for reactor dismantling and site license termination to a subsidiary of EnergySolutions. The target end state of the Zion site for return to Exelon will be a green field with the exception of the dry fuel storage pad. In return, ZionSolutions has access to the full value of the decommissioning trust fund. There are two potential attractions of this model: lower overall cost and significant schedule acceleration. The Zion programme which commencedmore » in September 2010 is designed to return the cleared site with an Independent Spent Fuel Storage Installation (ISFSI) pad in 2020, 12 years earlier than planned by Exelon. The overall cost, at $500 M per full size power reactor is significantly below the long run trend of $750 M+ per PWR. Implementation of the accelerated programme has been underway for nearly three years and is making good progress. The programme is characterised by numerous projects proceeding in parallel. The critical path is defined by the inspection and removal of fuel from the pond and transfer into dry fuel storage casks on the ISFSI pad and completion of RPV segmentation. Fuel loading is expected to commence in mid- 2013 with completion in late 2014. In parallel, ZionSolutions is proceeding with the segmentation of the Reactor Vessel (RV) and internals in both Units. Removal of large components from Unit 1 is underway. Numerous other projects are underway or have been completed to date. They include access openings into both containments, installation of heavy lift crane capacity, rail upgrades to support waste removal from the site, radiological characterization of facilities and equipment and numerous related tasks. As at February 2013, the programme is just ahead of schedule and within the latest budget. The paper will provide a fuller update. The first

TN International and ITS operational feedback regarding the decommissioning of obsolete casks dedicated to the transport and/or storage of nuclear raw materials, fuel and used fuel

DOE Office of Scientific and Technical Information (OSTI.GOV)

Blachet, L.; Bimet, F.; Rennesson, N.

2008-07-01

Within the AREVA group, TN International is a major actor regarding the design of casks and transportation for the nuclear cycle. In the early 2005, TN International has started the project of decommissioning some of its own equipment and was hence the first company ever in the AREVA Group to implement this new approach. In order to do so, TN International has based this project by taking into account the AREVA Sustainable Development Charter, the French regulatory framework, the ANDRA (Agence Nationale pour la Gestion des Dechets Radioactifs - National Agency for the radioactive waste management) requirements and has deployedmore » a step by step methodology such as radiological characterization following a logical route. The aim was to define a standardized process with optimized solutions regarding the diversity of the cask's fleet. As a general matter, decommissioning of nuclear casks is a brand new field as the nuclear field is more familiar with the dismantling of nuclear facilities and/or nuclear power plant. Nevertheless existing workshops, maintenance facilities, measurements equipments and techniques have been exploited and adapted by TN International in order to turn an ambitious project into a permanent and cost-effective activity. The decommissioning of the nuclear casks implemented by TN International regarding its own needs and the French regulatory framework is formalized by several processes and is materialized for instance by the final disposal of casks as they are or in ISO container packed with cut-off casks and big bags filled with crushed internal cask equipments, etc. The first part of this paper aims to describe the history of the project that started with a specific environmental analysis which took into account the values of AREVA as regards the Sustainable Development principles that were at the time and are still a topic of current concern in the world. The second part will deal with the definition, the design and the implementation of

Considerations, measurements and logistics associated with low-energy cyclotron decommissioning

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sunderland, J. J.; Erdahl, C. E.; Bender, B. R.

2012-12-19

The University of Iowa's 20-year-old 17 MeV Scanditronix cyclotron underwent decommissioning in the summer of 2011. To satisfy local, state and federal regulations defining removal, transportation and long-term safe and environmentally secure disposal of the 22 ton activated cyclotron, a series of nuclear spectroscopic measurements were performed to characterize the nature and extent of proton and neutron activation of the 22-ton cyclotron, its associated targets, and the concrete wall that was demolished to remove the old cyclotron. Neutron activation of the concrete wall was minimal and below exempt concentrations resulting in standard landfill disposal. The cyclotron assessment revealed the expectedmore » array of short and medium-lived radionuclides. Subsequent calculations suggest that meaningful levels residual activity will have decayed virtually to background after 15 years, with the total residual activity of the entire cyclotron dropping below 37 MBq (1 mCi).« less

Remote Systems Experience at the Oak Ridge National Laboratory--A Summary of Lessons Learned

DOE Office of Scientific and Technical Information (OSTI.GOV)

Noakes, Mark W; Burgess, Thomas W; Rowe, John C

2011-01-01

Oak Ridge National Laboratory (ORNL) has a long history in the development of remote systems to support the nuclear environment. ORNL, working in conjunction with Central Research Laboratories, created what is believed to be the first microcomputer-based implementation of dual-arm master-slave remote manipulation. As part of the Consolidated Fuel Reprocessing Program, ORNL developed the dual-arm advanced servomanipulator focusing on remote maintainability for systems exposed to high radiation fields. ORNL also participated in almost all of the various technical areas of the U.S. Department of Energy s Robotics Technology Development Program, while leading the Decontamination and Decommissioning and Tank Waste Retrievalmore » categories. Over the course of this involvement, ORNL has developed a substantial base of working knowledge as to what works when and under what circumstances for many types of remote systems tasks as well as operator interface modes, control bandwidth, and sensing requirements to name a few. By using a select list of manipulator systems that is not meant to be exhaustive, this paper will discuss history and outcome of development, field-testing, deployment, and operations from a lessons learned perspective. The final outcome is a summary paper outlining ORNL experiences and guidelines for transition of developmental remote systems to real-world hazardous environments.« less

Nuclear Waste Management under Approaching Disaster: A Comparison of Decommissioning Strategies for the German Repository Asse II.

PubMed

Ilg, Patrick; Gabbert, Silke; Weikard, Hans-Peter

2017-07-01

This article compares different strategies for handling low- and medium-level nuclear waste buried in a retired potassium mine in Germany (Asse II) that faces significant risk of uncontrollable brine intrusion and, hence, long-term groundwater contamination. We survey the policy process that has resulted in the identification of three possible so-called decommissioning options: complete backfilling, relocation of the waste to deeper levels in the mine, and retrieval. The selection of a decommissioning strategy must compare expected investment costs with expected social damage costs (economic, environmental, and health damage costs) caused by flooding and subsequent groundwater contamination. We apply a cost minimization approach that accounts for the uncertainty regarding the stability of the rock formation and the risk of an uncontrollable brine intrusion. Since economic and health impacts stretch out into the far future, we examine the impact of different discounting methods and rates. Due to parameter uncertainty, we conduct a sensitivity analysis concerning key assumptions. We find that retrieval, the currently preferred option by policymakers, has the lowest expected social damage costs for low discount rates. However, this advantage is overcompensated by higher expected investment costs. Considering all costs, backfilling is the best option for all discounting scenarios considered. © 2016 Society for Risk Analysis.

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 18. Part 1B: Citations with abstracts, sections 10 through 16

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1997-09-01

This bibliography contains 3,638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D and D), uranium mill tailings management, and site remedial actions. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D and D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized sites Remedial Action Program; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions;more » (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluation; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues.« less

Completion of the decommissioning of a former active handling building at UKAEA Winfrith

DOE Office of Scientific and Technical Information (OSTI.GOV)

Brown, N.; Parkinson, S.J.; Cornell, R.M.

2007-07-01

Since July 2000, NUKEM Limited has been carrying out the full decommissioning of a former Active Handling Building A59 at Winfrith in Dorset under contract from the nuclear site licence holder, UKAEA. Work has generally centred upon clearance and decontamination of the two heavily shielded suites of caves originally used to carry out remote examination of irradiated nuclear fuel elements although a number of other supporting facilities are also involved. This work has proceeded successfully to completion following extensive decontamination of the caves and associated facilities and has been followed by the recent demolition of the main containment building structure.more » This has permitted a start to be made on the demolition of the two heavily shielded suites of caves which is to be followed by removal of the building slab and restoration of the site. This paper reviews some of the significant tasks undertaken during the past year in preparation for the building and cave line demolition operations. It also reviews the building structure removal and recent progress made with the demolition of the two heavily reinforced concrete cave lines. The procedure used for monitoring the concrete debris from the cave lines has had to be revised during these operations and the reasons for this and a temporary delay in the cave line demolition will be discussed in the context of the remaining sections of the programme. This decommissioning programme has been achieved throughout by the employment of a non-adversarial team working approach between client and contractor. This has been instrumental in developing cost-effective and safe solutions to a range of problems during the programme, demonstrating the worth of adopting this co-operative approach for mutual benefit. (authors)« less

Assessment, evaluation, and testing of technologies for environmental restoration, decontamination, and decommissioning and high level waste management. Progress report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Uzochukwu, G.A.

1997-12-31

Nuclear and commercial non-nuclear technologies that have the potential of meeting the environmental restoration, decontamination and decommissioning, and high-level waste management objectives are being assessed and evaluated. A detailed comparison of innovative technologies available will be performed to determine the safest and most economical technology for meeting these objectives. Information derived from this effort will be matched with the multi-objectives of the environmental restoration, decontamination and decommissioning, and high-level waste management effort to ensure that the best, most economical, and the safest technologies are used in decision making at USDOE-SRS. Technology-related variables will be developed and the resulting data formattedmore » and computerized for multimedia systems. The multimedia system will be made available to technology developers and evaluators to ensure that the best, most economical, and the safest technologies are used in decision making at USDOE-SRS. Technology-related variables will be developed and the resulting data formatted and computerized for multimedia systems. The multimedia system will be made available to technology developers and evaluators to ensure that the safest and most economical technologies are developed for use at SRS and other DOE sites.« less

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1997-09-01

This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D&D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. Citations to foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - have been included in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmentalmore » restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D&D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword.« less

Shock Prevention

NASA Technical Reports Server (NTRS)

1978-01-01

The electrician pictured is installing a General Electric Ground Fault Interrupter (GFI), a device which provides protection against electrical shock in the home or in industrial facilities. Shocks due to defective wiring in home appliances or other electrical equipment can cause severe burns, even death. As a result, the National Electrical Code now requires GFIs in all new homes constructed. This particular type of GFI employs a sensing element which derives from technology acquired in space projects by SCI Systems, Inc., Huntsville, Alabama, producer of sensors for GE and other manufacturers of GFI equipment. The sensor is based on the company's experience in developing miniaturized circuitry for space telemetry and other spacecraft electrical systems; this experience enabled SCI to package interruptor circuitry in the extremely limited space available and to produce sensory devices at practicable cost. The tiny sensor measures the strength of the electrical current and detects current differentials that indicate a fault in the functioning of an electrical system. The sensing element then triggers a signal to a disconnect mechanism in the GFI, which cuts off the current in the faulty circuit.

The Critical Mass Laboratory at Rocky Flats

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rothe, Robert E

2003-10-15

The Critical Mass Laboratory (CML) at Rocky Flats northwest of Denver, Colorado, was built in 1964 and commissioned to conduct nuclear experiments on January 28, 1965. It was built to attain more accurate and precise experimental data to ensure nuclear criticality safety at the plant than were previously possible. Prior to its construction, safety data were obtained from long extrapolations of subcritical data (called in situ experiments), calculated parameters from reactor engineering 'models', and a few other imprecise methods. About 1700 critical and critical-approach experiments involving several chemical forms of enriched uranium and plutonium were performed between then and 1988.more » These experiments included single units and arrays of fissile materials, reflected and 'bare' systems, and configurations with various degrees of moderation, as well as some containing strong neutron absorbers. In 1989, a raid by the Federal Bureau of Investigation (FBI) caused the plant as a whole to focus on 'resumption' instead of further criticality safety experiments. Though either not recognized or not admitted for a few years, that FBI raid did sound the death knell for the CML. The plant's optimistic goal of resumption evolved to one of deactivation, decommissioning, and plantwide demolition during the 1990s. The once-proud CML facility was finally demolished in April of 2002.« less

Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2

DOE Office of Scientific and Technical Information (OSTI.GOV)

Poderis, Reed J.; King, Rebecca A.

This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping,more » tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified

Final Environmental Impact Statement for Treating Transuranic (TRU)/Alpha Low-level Waste at the Oak Ridge National Laboratory Oak Ridge, Tennessee

DOE Office of Scientific and Technical Information (OSTI.GOV)

N /A

2000-06-30

The DOE proposes to construct, operate, and decontaminate/decommission a TRU Waste Treatment Facility in Oak Ridge, Tennessee. The four waste types that would be treated at the proposed facility would be remote-handled TRU mixed waste sludge, liquid low-level waste associated with the sludge, contact-handled TRU/alpha low-level waste solids, and remote-handled TRU/alpha low-level waste solids. The mixed waste sludge and some of the solid waste contain metals regulated under the Resource Conservation and Recovery Act and may be classified as mixed waste. This document analyzes the potential environmental impacts associated with five alternatives--No Action, the Low-Temperature Drying Alternative (Preferred Alternative), themore » Vitrification Alternative, the Cementation Alternative, and the Treatment and Waste Storage at Oak Ridge National Laboratory (ORNL) Alternative.« less

French Atomic Energy Commission Decommissioning Programme and Feedback Experience - 12230

DOE Office of Scientific and Technical Information (OSTI.GOV)

Guiberteau, Ph.; Nokhamzon, J.G.

Since the French Atomic and Alternatives Energy Commission (CEA) was founded in 1945 to carry out research programmes on use of nuclear, and its application France has set up and run various types of installations: research or prototypes reactors, process study or examination laboratories, pilot installations, accelerators, nuclear power plants and processing facilities. Some of these are currently being dismantled or must be dismantled soon so that the DEN, the Nuclear Energy Division, can construct new equipment and thus have available a range of R and D facilities in line with the issues of the nuclear industry of the future.more » Since the 1960's and 1970's in all its centres, the CEA has acquired experience and know-how through dismantling various nuclear facilities. The dismantling techniques are nowadays operational, even if sometimes certain specific developments are necessary to reduce the cost of operations. Thanks to availability of techniques and guarantees of dismantling programme financing now from two dedicated funds, close to euro 15,000 M for the next thirty years, for current or projected dismantling operations, the CEA's Nuclear Energy Division has been able to develop, when necessary, its immediate dismantling strategy. Currently, nearly thirty facilities are being dismantled by the CEA's Nuclear Energy Division operational units with industrial partners. Thus the next decade will see completion of the dismantling and radioactive clean-up of the Grenoble site and of the facilities on the Fontenay-aux-Roses site. By 2016, the dismantling of the UP1 plant at Marcoule, the largest dismantling work in France, will be well advanced, with all the process equipment dismantled. After an overview of the French regulatory framework, the paper will describe the DD and R (Decontamination Decommissioning and Remediation) strategy, programme and feedback experience inside the CEA's Nuclear Energy Division. A special feature of dismantling operations at the

Y-12 Plant decontamination and decommissioning technology logic diagram for Building 9201-4. Volume 2: Technology logic diagram

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1994-09-01

The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 (TLD) was developed to provide a decision-support tool that relates decontamination and decommissioning (D and D) problems at Bldg. 9201-4 to potential technologies that can remediate these problems. This TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to D and D and waste management (WM) activities. It is essential that follow-on engineering studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologiesmore » identified in the TLD and by finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk. The TLD consists of three fundamentally separate volumes: Vol. 1 (Technology Evaluation), Vol. 2 (Technology Logic Diagram), and Vol. 3 (Technology Evaluation Data Sheets). Volume 2 contains the logic linkages among environmental management goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 2 has been divided into five sections: Characterization, Decontamination, Dismantlement, Robotics/Automation, and Waste Management. Each section contains logical breakdowns of the Y-12 D and D problems by subject area and identifies technologies that can be reasonably applied to each D and D challenge.« less

Decontamination and decommissioning plan for processing contaminated NaK at the INEL

DOE Office of Scientific and Technical Information (OSTI.GOV)

LaRue, D.M.; Dolenc, M.R.

1986-09-01

This decontamination and decommissioning (D D) plan describes the work elements and project management plan for processing four containers of contaminated sodium/potassium (NaK) and returning the Army Reentry Vehicle Facility Site (ARVFS) to a reusable condition. The document reflects the management plan for this project before finalizing the conceptual design and preliminary prototype tests of the reaction kinetics. As a result, the safety, environmental, and accident analyses are addressed as preliminary assessments before completion at a later date. ARVFS contains an earth-covered bunker, a cylindrical test pit and metal shed, and a cable trench connecting the two items. The bunkermore » currently stores the four containers of NaK from the meltdown of the EBR-1 Mark II core. The D D project addressed in this plan involves processing the contaminated NaK and returning the ARVFS to potential reuse after cleanup.« less

Decontamination and decommissioning plan for processing contaminated NaK at the INEL

DOE Office of Scientific and Technical Information (OSTI.GOV)

LaRue, D.M.; Dolenc, M.R.

1986-09-01

This decontamination and decommissioning (D&D) plan describes the work elements and project management plan for processing four containers of contaminated sodium/potassium (NaK) and returning the Army Reentry Vehicle Facility Site (ARVFS) to a reusable condition. The document reflects the management plan for this project before finalizing the conceptual design and preliminary prototype tests of the reaction kinetics. As a result, the safety, environmental, and accident analyses are addressed as preliminary assessments before completion at a later date. ARVFS contains an earth-covered bunker, a cylindrical test pit and metal shed, and a cable trench connecting the two items. The bunker currentlymore » stores the four containers of NaK from the meltdown of the EBR-1 Mark II core. The D&D project addressed in this plan involves processing the contaminated NaK and returning the ARVFS to potential reuse after cleanup.« less

Decommissioning of the Dragon High Temperature Reactor (HTR) Located at the Former United Kingdom Atomic Energy Authority (UKAEA) Research Site at Winfrith - 13180

DOE Office of Scientific and Technical Information (OSTI.GOV)

Smith, Anthony A.

2013-07-01

The Dragon Reactor was constructed at the United Kingdom Atomic Energy Research Establishment at Winfrith in Dorset through the late 1950's and into the early 1960's. It was a High Temperature Gas Cooled Reactor (HTR) with helium gas coolant and graphite moderation. It operated as a fuel testing and demonstration reactor at up to 20 MW (Thermal) from 1964 until 1975, when international funding for this project was terminated. The fuel was removed from the core in 1976 and the reactor was put into Safestore. To meet the UK's Nuclear Decommissioning Authority (NDA) objective to 'drive hazard reduction' [1] itmore » is necessary to decommission and remediate all the Research Sites Restoration Ltd (RSRL) facilities. This includes the Dragon Reactor where the activated core, pressure vessel and control rods and the contaminated primary circuit (including a {sup 90}Sr source) still remain. It is essential to remove these hazards at the appropriate time and return the area occupied by the reactor to a safe condition. (author)« less

Decommissioning strategy for liquid low-level radioactive waste surface storage water reservoir.

PubMed

Utkin, S S; Linge, I I

2016-11-22

The Techa Cascade of water reservoirs (TCR) is one of the most environmentally challenging facilities resulted from FSUE "PA "Mayak" operations. Its reservoirs hold over 360 mln m 3 of liquid radioactive waste with a total activity of some 5 × 10 15 Bq. A set of actions implemented under a special State program involving the development of a strategic plan aimed at complete elimination of TCR challenges (Strategic Master-Plan for the Techa Cascade of water reservoirs) resulted in considerable reduction of potential hazards associated with this facility. The paper summarizes the key elements of this master-plan: defining TCR final state, feasibility study of the main strategies aimed at its attainment, evaluation of relevant long-term decommissioning strategy, development of computational tools enabling the long-term forecast of TCR behavior depending on various engineering solutions and different weather conditions. Copyright © 2016 Elsevier Ltd. All rights reserved.

Pacific Northwest Laboratory annual report for 1980 to the DOE Assistant Secretary for Environment. Part 5. Environmental assessment, control, health and safety

DOE Office of Scientific and Technical Information (OSTI.GOV)

Baalman, R.W.; Hays, I.D.

1981-02-01

Pacific Northwest Laboratory's (PNL) 1980 annual report to the DOE Assistant Secretary for Environment describes research in environment, health, and safety conducted during fiscal year 1980. Part 5 includes technology assessments for natural gas, enhanced oil recovery, oil shale, uranium mining, magnetic fusion energy, solar energy, uranium enrichment and industrial energy utilization; regional analysis studies of environmental transport and community impacts; environmental and safety engineering for LNG, oil spills, LPG, shale oil waste waters, geothermal liquid waste disposal, compressed air energy storage, and nuclear/fusion fuel cycles; operational and environmental safety studies of decommissioning, environmental monitoring, personnel dosimetry, and analysis ofmore » criticality safety; health physics studies; and epidemiological studies. Also included are an author index, organization of PNL charts and distribution lists of the annual report, along with lists of presentations and publications. (DLS)« less

Security of patient data when decommissioning ultrasound systems.

PubMed

Moggridge, James

2017-02-01

Although ultrasound systems generally archive to Picture Archiving and Communication Systems (PACS), their archiving workflow typically involves storage to an internal hard disk before data are transferred onwards. Deleting records from the local system will delete entries in the database and from the file allocation table or equivalent but, as with a PC, files can be recovered. Great care is taken with disposal of media from a healthcare organisation to prevent data breaches, but ultrasound systems are routinely returned to lease companies, sold on or donated to third parties without such controls. In this project, five methods of hard disk erasure were tested on nine ultrasound systems being decommissioned: the system's own delete function; full reinstallation of system software; the manufacturer's own disk wiping service; open source disk wiping software for full and just blank space erasure. Attempts were then made to recover data using open source recovery tools. All methods deleted patient data as viewable from the ultrasound system and from browsing the disk from a PC. However, patient identifiable data (PID) could be recovered following the system's own deletion and the reinstallation methods. No PID could be recovered after using the manufacturer's wiping service or the open source wiping software. The typical method of reinstalling an ultrasound system's software may not prevent PID from being recovered. When transferring ownership, care should be taken that an ultrasound system's hard disk has been wiped to a sufficient level, particularly if the scanner is to be returned with approved parts and in a fully working state.

Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

DOE Office of Scientific and Technical Information (OSTI.GOV)

Michael Kruzic

2007-09-01

Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolitionmore » (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.« less

What matters in the classroom: A structural model of standards-based scientific literacy

NASA Astrophysics Data System (ADS)

Shive, Louise E.

For over two decades educators and policy makers have been particularly concerned with student achievement in the wake of A Nation at Risk. A majority of studies indicates that students' family background has the strongest influence on achievement, although characteristics of their teachers and schools have significant impact as well. This study considered achievement in science in particular, investigating the influence of alterable factors within the classroom on students' gains in scientific literacy. Scientific literacy included three elements: content knowledge, scientific process skills, and attitude towards science. Based on a review of the literature on student achievement, a structural equation model was constructed with five latent variables: teacher's education, instructional practices, teacher's attitudes, school's context, and students' scientific literacy. The model was tested using data from the five-month implementation of a standards-based integrated text/technology/laboratory program, Biology: Exploring Life. The sixteen biology teachers completed two pre-implementation surveys, and 664 of their students completed the three pretests and the corresponding posttests. The initial model did not fit well (chi2(80) = 2784.16; chi 2/df = 34.80; GFI = .70; IFI = .49; CFI = .49) and was inadmissible due to the presence of negative variances. After revision of the model, fit improved somewhat (chi2(53) = 1623.97; chi 2/df = 30.64; GFI = .77; IFI = .65; CFI = .65), although a negative variance migrated and persisted. The total effects were greatest for the teacher's attitudes (largely indirect, mediated through instructional practices), followed by school's context, and instructional practices. Teacher's education had the lowest total effects due to almost equal but opposite direct effects (positive) and indirect effects (mediated through instructional practices and teacher's attitudes). The investigator concluded that alterable factors such as teachers

Lessons Learned in the Decommissioning of the Stardust Spacecraft

NASA Technical Reports Server (NTRS)

Larson, Timothy W.

2012-01-01

The Stardust spacecraft completed its prime mission in 2006, returning samples from the coma of comet Wild 2 to earth in the sample return capsule. Still healthy, and in a heliocentric orbit, the Stardust spacecraft was repurposed for a new mission - Stardust NExT. This new mission would take the veteran spacecraft to a 2011 encounter with comet Tempel 1, providing a new look at the comet visited in 2005 by the Deep Impact mission. This extended mission for Stardust would push it to the limits of its fuel reserves, prompting several studies aimed at determining the actual remaining fuel on board. The results were used to plan mission events within the constraints of this dwindling resource. The team tracked fuel consumption and adjusted the mission plans to stay within the fuel budget. This effort intensified toward the end of the mission, when a final assessment showed even less remaining fuel than previously predicted, triggering a delay in the start of comet imaging during the approach phase. The flyby of comet Tempel 1 produced spectacular up close views of this comet, imaging previously seen areas as well as new territory, and providing clear views of the location of the 2005 impact. The spacecraft was decommissioned about a month after the flyby, revealing that the fuel tank was now empty after having flown successfully for 12 years, returned comet dust samples to earth, and flown by an asteroid and two comets.

Security of patient data when decommissioning ultrasound systems

PubMed Central

2017-01-01

Background Although ultrasound systems generally archive to Picture Archiving and Communication Systems (PACS), their archiving workflow typically involves storage to an internal hard disk before data are transferred onwards. Deleting records from the local system will delete entries in the database and from the file allocation table or equivalent but, as with a PC, files can be recovered. Great care is taken with disposal of media from a healthcare organisation to prevent data breaches, but ultrasound systems are routinely returned to lease companies, sold on or donated to third parties without such controls. Methods In this project, five methods of hard disk erasure were tested on nine ultrasound systems being decommissioned: the system’s own delete function; full reinstallation of system software; the manufacturer’s own disk wiping service; open source disk wiping software for full and just blank space erasure. Attempts were then made to recover data using open source recovery tools. Results All methods deleted patient data as viewable from the ultrasound system and from browsing the disk from a PC. However, patient identifiable data (PID) could be recovered following the system’s own deletion and the reinstallation methods. No PID could be recovered after using the manufacturer’s wiping service or the open source wiping software. Conclusion The typical method of reinstalling an ultrasound system’s software may not prevent PID from being recovered. When transferring ownership, care should be taken that an ultrasound system’s hard disk has been wiped to a sufficient level, particularly if the scanner is to be returned with approved parts and in a fully working state. PMID:28228821

Laboratories | NREL

Science.gov Websites

| Z A Accelerated Exposure Testing Laboratory Advanced Optical Materials Laboratory Advanced Thermal Laboratory Structural Testing Laboratory Surface Analysis Laboratory Systems Performance Laboratory T Thermal Storage Materials Laboratory Thermal Storage Process and Components Laboratory Thin-Film Deposition

Conceptual Site Treatment Plan Laboratory for Energy-Related Health Research Environmental Restoration Project

DOE Office of Scientific and Technical Information (OSTI.GOV)

Chapman, T.E.

1993-10-01

The Federal Facilities Compliance Act (the Act) of 1992 waives sovereign immunity for federal facilities for fines and penalties under the provisions of the Resource Recovery and Conservation Act, state, interstate, and local hazardous and solid waste management requirements. However, for three years the Act delays the waiver for violations involving US Department of Energy (DOE) facilities. The Act, however, requires that the DOE prepare a Conceptual Site Treatment Plan (CSTP) for each of its sites that generate or store mixed wastes (MWs). The purpose of the CSTP is to present DOE`s preliminary evaluations of the development of treatment capacitiesmore » and technologies for treating a site`s MW. This CSTP presents the preliminary capacity and technology evaluation for the Laboratory for Energy-Related Health Research (LEHR). The five identified MW streams at LEHR are evaluated to the extent possible given available information. Only one MW stream is sufficiently well defined to permit a technology evaluation to be performed. Two other MW streams are in the process of being characterized so that an evaluation can be performed. The other two MW streams will be generated by the decommissioning of inactive facilities onsite within the next five years.« less

Decommissioning of offshore oil and gas facilities: a comparative assessment of different scenarios.

PubMed

Ekins, Paul; Vanner, Robin; Firebrace, James

2006-06-01

A material and energy flow analysis, with corresponding financial flows, was carried out for different decommissioning scenarios for the different elements of an offshore oil and gas structure. A comparative assessment was made of the non-financial (especially environmental) outcomes of the different scenarios, with the reference scenario being to leave all structures in situ, while other scenarios envisaged leaving them on the seabed or removing them to shore for recycling and disposal. The costs of each scenario, when compared with the reference scenario, give an implicit valuation of the non-financial outcomes (e.g. environmental improvements), should that scenario be adopted by society. The paper concludes that it is not clear that the removal of the topsides and jackets of large steel structures to shore, as currently required by regulations, is environmentally justified; that concrete structures should certainly be left in place; and that leaving footings, cuttings and pipelines in place, with subsequent monitoring, would also be justified unless very large values were placed by society on a clear seabed and trawling access.

Confirmatory radiological survey of the BORAX-V turbine building Idaho National Engineering Laboratory, Idaho Falls, Idaho

DOE Office of Scientific and Technical Information (OSTI.GOV)

Stevens, G.H.; Coleman, R.L.; Jensen, M.K.

1993-07-01

An independent assessment of the remediation of the BORAX-V (Boiling Water Reactor Experiment) turbine building at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho, was accomplished by the Oak Ridge National Laboratory Pollutant Assessments Group (ORNL/PAG). The purpose of the assessment was to confirm the site`s compliance with applicable Department of Energy guidelines. The assessment included reviews of both the decontamination and decommissioning Plan and data provided from the pre- and post-remedial action surveys and an independent verification survey of the facility. The independent verification survey included determination of background exposure rates and soil concentrations, beta-gamma and gamma radiationmore » scans, smears for detection of removable contamination, and direct measurements for alpha and beta-gamma radiation activity on the basement and mezzanine floors and the building`s interior and exterior walls. Soil samples were taken, and beta-gamma and gamma radiation exposure rates were measured on areas adjacent to the building. Results of measurements on building surfaces at this facility were within established contamination guidelines except for elevated beta-gamma radiation levels located on three isolated areas of the basement floor. Following remediation of these areas, ORNL/PAG reviewed the remedial action contractor`s report and agreed that remediation was effective in removing the source of the elevated direct radiation. Results of all independent soil analyses for {sup 60}Co were below the detection limit. The highest {sup 137}Cs analysis result was 4.6 pCi/g; this value is below the INEL site-specific guideline of 10 pCi/g.« less

PaR Tensile Truss for Nuclear Decontamination and Decommissioning - 12467

DOE Office of Scientific and Technical Information (OSTI.GOV)

Doebler, Gary R.

2012-07-01

Remote robotics and manipulators are commonly used in nuclear decontamination and decommissioning (D and D) processes. D and D robots are often deployed using rigid telescoping masts in order to apply and counteract side loads. However, for very long vertical reaches (15 meters or longer) and high lift capacities, a telescopic is usually not practical due to the large cross section and weight required to make the mast stiff and resist seismic forces. For those long vertical travel applications, PaR Systems has recently developed the Tensile Truss, a rigid, hoist-driven 'structure' that employs six independent wire rope hoists to achievemore » long vertical reaches. Like a mast, the Tensile Truss is typically attached to a bridge-mounted trolley and is used as a platform for robotic manipulators and other remotely operated tools. For suspended, rigid deployment of D and D tools with very long vertical reaches, the Tensile Truss can be a better alternative than a telescoping mast. Masts have length limitations that can make them impractical or unworkable as lengths increase. The Tensile Truss also has the added benefits of increased safety, ease of decontamination, superior stiffness and ability to withstand excessive side loading. A Tensile Truss system is currently being considered for D and D operations and spent fuel recovery at the Fukushima Daiichi Nuclear Power Plant in Japan. This system will deploy interchangeable tools such as underwater hydraulic manipulators, hydraulic shears and crushers, grippers and fuel grapples. (authors)« less

Site Environmental Report for Calendar Year 2004. DOE Operations at The Boeing Company Santa Susana Field Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Liu, Ning; Rutherford, Phil; Lee, Majelle

2005-09-01

This Annual Site Environmental Report (ASER) for 2004 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). In the past, the Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder components. All nuclear work was terminated inmore » 1988; all subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Closure of the liquid metal test facilities began in 1996. Results of the radiological monitoring program for the calendar year 2004 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less

Get In and Get Out: Assessing Stream Sediment Loading from Short Duration Forest Harvest Operations and Rapid Haul Road Decommissioning.

NASA Astrophysics Data System (ADS)

Corrigan, A.; Silins, U.; Stone, M.

2016-12-01

Best management practices (BMPs) and associated erosion control measures for mitigating sediment impacts from forestry roads and road-stream crossings are well documented. While rapid road decommissioning after forestry operations may serve to limit broader impacts on sediment production in high value headwater streams, few studies have evaluated the combined effects of accelerated harvest operations and rapid retirement of logging roads and road-stream crossings on stream sediment. The objectives of this study were to evaluate the initial impacts of these strategies on fine sediment loading and fate during a short duration harvesting operation in 3 headwater sub-catchments in the southwestern Rocky Mountains of Alberta, Canada. A multi-pronged sampling approach (ISCOs, event focused grab sampling, continuous wash load sampling, and stream bed sediment intrusion measurements) was used to measure sediment loading and deposition in streambeds upstream and downstream of road-stream bridge crossings during harvest operations (2015) and after road and bridge crossing retirement (2016). Sediment production from forestry roads was generally much lower than has been reported from other studies in similar settings. Average total suspended solids (TSS) downstream of the bridge crossings were actually lower (-3.28 g/L; -0.704 g/L) than upstream of two bridge crossings while in-stream sediment sources contributed to elevated sediment downstream of a third road-stream crossing. Minimal in stream sediment impacts from forest harvest and road-stream crossings was likely a reflection of combined factors including a) employment of erosion control BMPs to roads and bridge crossings, b) rapid decommissioning of roads and crossings to limit exposure of linear land disturbance features, and c) drier El Niño climatic conditions during the study.

DEVELOPMENT OF PERSONAL PROTECTIVE EQUIPMENT FOR DECONTAMINATION AND DECOMMISSIONING

DOE Office of Scientific and Technical Information (OSTI.GOV)

M.A. Ebadian, Ph.D.

1999-01-01

The purpose of this one-year investigation is to perform a technology integration/search, thereby ensuring that the safest and most cost-effective options are developed and subsequently used during the deactivation and decommissioning (D&D) of U.S. Department of Energy Environmental Management (DOE-EM) sites. Issues of worker health and safety are the main concern, followed by cost. Two lines of action were explored: innovative Personal Cooling Systems (PCS) and Personal Monitoring Equipment (PME). PME refers to sensors affixed to the worker that warn of an approaching heat stress condition, thereby preventing it. Three types of cooling systems were investigated: Pre-Chilled or Forced-Air Systemmore » (PCFA), Umbilical Fluid-Chilled System (UFCS), and Passive Vest System (PVS). Of these, the UFCS leads the way. The PVS or Gel pack vest lagged due to a limited cooling duration. And the PCFA or chilled liquid air supply was cumbersome and required an expensive and complex recharge system. The UFCS in the form of the Personal Ice Cooling System (PICS) performed exceptionally. The technology uses a chilled liquid circulating undergarment and a Personal Protective Equipment (PPE) external pump and ice reservoir. The system is moderately expensive, but the recharge is low-tech and inexpensive enough to offset the cost. There are commercially available PME that can be augmented to meet the DOE's heat stress alleviation need. The technology is costly, in excess of $4,000 per unit. Workers easily ignore the alarm. The benefit to health & safety is indirect so can be overlooked. A PCS is a more justifiable expenditure.« less

ANL Critical Assembly Covariance Matrix Generation

DOE Office of Scientific and Technical Information (OSTI.GOV)

McKnight, Richard D.; Grimm, Karl N.

2014-01-15

This report discusses the generation of a covariance matrix for selected critical assemblies that were carried out by Argonne National Laboratory (ANL) using four critical facilities-all of which are now decommissioned. The four different ANL critical facilities are: ZPR-3 located at ANL-West (now Idaho National Laboratory- INL), ZPR-6 and ZPR-9 located at ANL-East (Illinois) and ZPPr located at ANL-West.

Tri-Laboratory Linux Capacity Cluster 2007 SOW

DOE Office of Scientific and Technical Information (OSTI.GOV)

Seager, M

2007-03-22

The Advanced Simulation and Computing (ASC) Program (formerly know as Accelerated Strategic Computing Initiative, ASCI) has led the world in capability computing for the last ten years. Capability computing is defined as a world-class platform (in the Top10 of the Top500.org list) with scientific simulations running at scale on the platform. Example systems are ASCI Red, Blue-Pacific, Blue-Mountain, White, Q, RedStorm, and Purple. ASC applications have scaled to multiple thousands of CPUs and accomplished a long list of mission milestones on these ASC capability platforms. However, the computing demands of the ASC and Stockpile Stewardship programs also include a vastmore » number of smaller scale runs for day-to-day simulations. Indeed, every 'hero' capability run requires many hundreds to thousands of much smaller runs in preparation and post processing activities. In addition, there are many aspects of the Stockpile Stewardship Program (SSP) that can be directly accomplished with these so-called 'capacity' calculations. The need for capacity is now so great within the program that it is increasingly difficult to allocate the computer resources required by the larger capability runs. To rectify the current 'capacity' computing resource shortfall, the ASC program has allocated a large portion of the overall ASC platforms budget to 'capacity' systems. In addition, within the next five to ten years the Life Extension Programs (LEPs) for major nuclear weapons systems must be accomplished. These LEPs and other SSP programmatic elements will further drive the need for capacity calculations and hence 'capacity' systems as well as future ASC capability calculations on 'capability' systems. To respond to this new workload analysis, the ASC program will be making a large sustained strategic investment in these capacity systems over the next ten years, starting with the United States Government Fiscal Year 2007 (GFY07). However, given the growing need for 'capability

Financial Planning as a Tool for Efficient and Timely Decommissioning of Nuclear Research Facilities

DOE Office of Scientific and Technical Information (OSTI.GOV)

Cato, Anna; Lindskog, Staffan; Sjoeblom, Rolf

2008-01-15

It is generally recognized in the technical and economical literature that reliable cost evaluations with adequate estimates also of the errors and uncertainties involved are necessary in order for rational and appropriate management decisions to be made on any major plant investment. Such estimates are required for the selection of technologies to be applied and for selection to be made between alternative technologies and designs as well as for the overall financing issues including the one of whether to go ahead with the project. Inadequacies in the cost calculations typically lead to suboptimal decisions and ultimately substantial overruns and/or needsmore » for retrofits. Actually, a very strict discipline has to be applied with adaptation of the approach used with regard to the stage of the planning. Deviations from the expected tend to raise the estimated cost much more frequently than they lower it. The same rationale applies to planning and cost calculations for decommissioning of nuclear research facilities. There are, however, many reasons why such estimations may be very treacherous to carry out. This will be dealt with in the following. The knowledge base underlying the present paper has been developed and accumulated as a result of the research that the Swedish Nuclear Power Inspectorate (SKI) has carried out in support of its regulatory oversight over the Swedish system of finance. The findings are, however, equally applicable and appropriate for implementers in their planning, decision, monitoring and evaluation activities. In the nineteen fifties and sixties, Sweden had a comprehensive program for utilization of nuclear power including uranium mining, fuel fabrication, reprocessing and domestically developed heavy water reactors. Examples of facilities are presented in Figures 1-5. Eventually, the development work lead to the present nuclear program with ten modern light water reactors in operation at present. According to Swedish law, those who

Web-based training related to NRC staff review of dose modeling aspects of license termination and decommissioning plans

DOE Office of Scientific and Technical Information (OSTI.GOV)

LePoire, D.; Arnish, J.; Cheng, J.J.

NRC licensees at decommissioning nuclear facilities submit License Termination Plans (LTP) or Decommissioning Plans (DP) to NRC for review and approval. To facilitate a uniform and consistent review of these plans, the NRC developed training for its staff. A live classroom course was first developed in 2005, which targeted specific aspects of the LTP and DP review process related to dose-based compliance demonstrations or modeling. A web-based training (WBT) course is being developed in 2006 to replace the classroom-based course. The advantage of the WBT is that it will allow for staff training or refreshers at any time, while themore » advantage of a classroom-based course is that it provides a forum for lively discussion and the sharing of experience of classroom participants. The training course consists of the core and advanced modules tailored to specific NRC job functions. Topics for individual modules include identifying the characteristics of simple and complex sites, identifying when outside expertise or consultation is needed, demonstrating how to conduct acceptance and technical reviews of dose modeling, and providing details regarding the level of justification needed for realistic scenarios for both dose modeling and derivation of DCGLs. Various methods of applying probabilistic uncertainty analysis to demonstrate compliance with dose-based requirements are presented. These approaches include 1) modeling the pathways of radiological exposure and estimating doses to receptors from a combination of contaminated media and radionuclides, and 2) using probabilistic analysis to determine an appropriate set of input parameters to develop derived concentration guideline limits or DCGLs (DCGLs are media- and nuclide-specific concentration limits that will meet dose-based, license termination rule criteria found in 10 CFR Part 20, Subpart E). Calculation of operational (field) DCGL's from media- and nuclide-specific DCGLs and use of operational DCGLs in

Dismantling of the PETRA glove box: tritium contamination and inventory assessment

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wagner, R.

2015-03-15

The PETRA facility is the first installation in which experiments with tritium were carried out at the Tritium Laboratory Karlsruhe. After completion of two main experimental programs, the decommissioning of PETRA was initiated with the aim to reuse the glove box and its main still valuable components. A decommissioning plan was engaged to: -) identify the source of tritium release in the glove box, -) clarify the status of the main components, -) assess residual tritium inventories, and -) de-tritiate the components to be disposed of as waste. Several analytical techniques - calorimetry on small solid samples, wipe test followedmore » by liquid scintillation counting for surface contamination assessment, gas chromatography on gaseous samples - were deployed and cross-checked to assess the remaining tritium inventories and initiate the decommissioning process. The methodology and the main outcomes of the numerous different tritium measurements are presented and discussed. (authors)« less

Norm - contaminated iodine production facilities decommissioning in Turkmenistan: experience and results

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gelbutovskiy, Alexander; Cheremisin, Peter; Egorov, Alexander

2013-07-01

This report summarizes the data, including the cost parameters of the former iodine production facilities decommissioning project in Turkmenistan. Before the closure, these facilities were producing the iodine from the underground mineral water by the methods of charcoal adsorption. Balkanabat iodine and Khazar chemical plants' sites remediation, transportation and disposal campaigns main results could be seen. The rehabilitated area covers 47.5 thousand square meters. The remediation equipment main characteristics, technical solutions and rehabilitation operations performed are indicated also. The report shows the types of the waste shipping containers, the quantity and nature of the logistics operations. The project waste turnovermore » is about 2 million ton-kilometers. The problems encountered during the remediation of the Khazar chemical plant site are discussed: undetected waste quantities that were discovered during the operational activities required the additional volume of the disposal facility. The additional repository wall superstructure was designed and erected to accommodate this additional waste. There are data on the volume and characteristics of the NORM waste disposed: 60.4 thousand cu.m. of NORM with total activity 1 439 x 10{sup 9} Bq (38.89 Ci) were disposed at all. This report summarizes the project implementation results, from 2009 to 15.02.2012 (the date of the repository closure and its placement under the controlled supervision), including monitoring results within a year after the repository closure. (authors)« less

Site Environmental Report for Calendar Year 2006. DOE Operations at The Boeing Company Santa Susana Field Laboratory, Area IV

DOE Office of Scientific and Technical Information (OSTI.GOV)

Liu, Ning; Rutherford, Phil

2007-09-01

This Annual Site Environmental Report (ASER) for 2006 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). In the past, the Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder components. All nuclear work was terminated inmore » 1988; all subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Closure of the liquid metal test facilities began in 1996. Results of the radiological monitoring program for the calendar year 2006 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less

The role of total laboratory automation in a consolidated laboratory network.

PubMed

Seaberg, R S; Stallone, R O; Statland, B E

2000-05-01

In an effort to reduce overall laboratory costs and improve overall laboratory efficiencies at all of its network hospitals, the North Shore-Long Island Health System recently established a Consolidated Laboratory Network with a Core Laboratory at its center. We established and implemented a centralized Core Laboratory designed around the Roche/Hitachi CLAS Total Laboratory Automation system to perform the general and esoteric laboratory testing throughout the system in a timely and cost-effective fashion. All remaining STAT testing will be performed within the Rapid Response Laboratories (RRLs) at each of the system's hospitals. Results for this laboratory consolidation and implementation effort demonstrated a decrease in labor costs and improved turnaround time (TAT) at the core laboratory. Anticipated system savings are approximately $2.7 million. TATs averaged 1.3 h within the Core Laboratory and less than 30 min in the RRLs. When properly implemented, automation systems can reduce overall laboratory expenses, enhance patient services, and address the overall concerns facing the laboratory today: job satisfaction, decreased length of stay, and safety. The financial savings realized are primarily a result of labor reductions.

Mathematical and physical model of gravity-fed infusion outflow: application to soft-bag-packed solutions.

PubMed

Simon, N; Décaudin, B; Lannoy, D; Barthélémy, C; Lemdani, M; Odou, P

2011-12-01

Gravity-fed infusion (GFI) systems are acknowledged as being unable to keep their flow-rate constant. This may affect drug plasma levels such as aminoglycosides. Numerous factors have previously been cited, but their relative importance has never been quantified so far. The objective of this work is to identify the main factors that influence GFI in vitro outflow and to propose a mathematical model of flow-rate evolution as a function of time. In this model, pressure loss and infusion device creep have been considered as the main variation factors. Concomitantly, two experiments were undertaken. Firstly, the flow-rate evolution of an in vitro infusion of 250 mL of dextrose 5% was assessed. Secondly, the creep occurring on an infusion device was measured through a stress relaxation experiment. The experimental infusion flow-rate decreased by as much as 28.5% over 1 h. Simulated and experimental data are well correlated (r = 0.987; P < 0.0001). The maximum creep effect happens during the first 15 min of infusion. In this work, height of the liquid in the bag and tube creep were found to be the main variation factors in GFI flow-rate. This new mathematical model should help to explain the differences observed in drug plasma levels with gravity-fed devices.

Trial Vocal Fold Injection Predicts Thyroplasty Outcomes in Nonparalytic Glottic Incompetence.

PubMed

Dumberger, Lukas D; Overton, Lewis; Buckmire, Robert A; Shah, Rupali N

2017-04-01

Trial vocal fold injection (TVFI) may be used prior to permanent medialization when voice outcome is uncertain. We aimed to determine whether voice outcomes of TVFI are predictive of, or correlate with outcomes after type I Gore-Tex medialization thyroplasty (GMT) in patients with nonparalytic glottic incompetence (GI). Thirty-five patients with nonparalytic GI who underwent TVFI followed by GMT were retrospectively reviewed. Change in voice-related quality of life (VRQOL) after TVFI was compared to change in VRQOL 3 to 9 months after GMT. Similar comparisons were made for change in glottal function index (GFI) and change in grade, roughness, breathiness, asthenia, and strain (GRBAS). Sample correlation coefficients were calculated. Change in VRQOL after TVFI showed good correlation with change in VRQOL after GMT, r = 0.55. Change in GFI after TVFI showed strong correlation with change in GFI after GMT, r = 0.74. Change in GRBAS after TVFI showed excellent correlation with change in GRBAS after GMT, r = 0.90. The TVFI is a useful tool in nonparalytic GI when outcomes from glottic closure procedures are not clear. Voice outcome measures after TVFI strongly correlate with outcomes from GMT. These data may be used to more confidently counsel patients regarding their predicted outcomes of permanent medialization.

Functional segregation of the inferior frontal gyrus for syntactic processes: a functional magnetic-resonance imaging study.

PubMed

Uchiyama, Yuji; Toyoda, Hiroshi; Honda, Manabu; Yoshida, Haruyo; Kochiyama, Takanori; Ebe, Kazutoshi; Sadato, Norihiro

2008-07-01

We used functional magnetic resonance imaging in 18 normal volunteers to determine whether there is separate representation of syntactic, semantic, and verbal working memory processing in the left inferior frontal gyrus (GFi). We compared a sentence comprehension task with a short-term memory maintenance task to identify syntactic and semantic processing regions. To investigate the effects of syntactic and verbal working memory load while minimizing the differences in semantic processes, we used comprehension tasks with garden-path (GP) sentences, which require re-parsing, and non-garden-path (NGP) sentences. Compared with the short-term memory task, sentence comprehension activated the left GFi, including Brodmann areas (BAs) 44, 45, and 47, and the left superior temporal gyrus. In GP versus NGP sentences, there was greater activity in the left BAs 44, 45, and 46 extending to the left anterior insula, the pre-supplementary motor area, and the right cerebellum. In the left GFi, verbal working memory activity was located more dorsally (BA 44/45), semantic processing was located more ventrally (BA 47), and syntactic processing was located in between (BA 45). These findings indicate a close relationship between semantic and syntactic processes, and suggest that BA 45 might link verbal working memory and semantic processing via syntactic unification processes.

Postirradiation Testing Laboratory (327 Building)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kammenzind, D.E.

A Standards/Requirements Identification Document (S/RID) is the total list of the Environment, Safety and Health (ES and H) requirements to be implemented by a site, facility, or activity. These requirements are appropriate to the life cycle phase to achieve an adequate level of protection for worker and public health and safety, and the environment during design, construction, operation, decontamination and decommissioning, and environmental restoration. S/RlDs are living documents, to be revised appropriately based on change in the site`s or facility`s mission or configuration, a change in the facility`s life cycle phase, or a change to the applicable standards/requirements. S/RIDs encompassmore » health and safety, environmental, and safety related safeguards and security (S and S) standards/requirements related to the functional areas listed in the US Department of Energy (DOE) Environment, Safety and Health Configuration Guide. The Fluor Daniel Hanford (FDH) Contract S/RID contains standards/requirements, applicable to FDH and FDH subcontractors, necessary for safe operation of Project Hanford Management Contract (PHMC) facilities, that are not the direct responsibility of the facility manager (e.g., a site-wide fire department). Facility S/RIDs contain standards/requirements applicable to a specific facility that are the direct responsibility of the facility manager. S/RlDs are prepared by those responsible for managing the operation of facilities or the conduct of activities that present a potential threat to the health and safety of workers, public, or the environment, including: Hazard Category 1 and 2 nuclear facilities and activities, as defined in DOE 5480.23. Selected Hazard Category 3 nuclear, and Low Hazard non-nuclear facilities and activities, as agreed upon by RL. The Postirradiation Testing Laboratory (PTL) S/RID contains standards/ requirements that are necessary for safe operation of the PTL facility, and other building/areas that are the

Produced Water Treatment Using Geothermal Energy from Oil and Gas Wells: An Appropriateness of Decommissioned Wells Index (ADWI) Approach

NASA Astrophysics Data System (ADS)

Kiaghadi, A.; Rifai, H. S.

2016-12-01

This study investigated the feasibility of harnessing geothermal energy from retrofitted oil and gas decommissioned wells to power desalination units and overcome the produced water treatment energy barrier. Previous studies using heat transfer models have indicated that well depth, geothermal gradient, formation heat conductivity, and produced water salt levels were the most important constraints that affect the achievable volume of treated water. Thus, the challenge of identifying which wells would be best suited for retrofit as geothermal wells was addressed by defining an Appropriateness of Decommissioned Wells Index (ADWI) using a 25 km x 25 km grid over Texas. Heat transfer modeling combined with fuzzy logic methodology were used to estimate the ADWI at each grid cell using the scale of Very Poor, Poor, Average, Good and Excellent. Values for each of the four constraints were extracted from existing databases and were used to select 20 representative values that covered the full range of the data. A heat transfer model was run for all the 160,000 possible combination scenarios and the results were regressed to estimate weighting coefficients that indicate the relative effect of well depth, geothermal gradient, heat conductivity, and produced water salt levels on the volume of treated water in Texas. The results indicated that wells located in cells with ADWI of "Average", "Good" or "Excellent" can potentially deliver 35,000, 106,000, or 240,000 L/day of treated water, respectively. Almost 98% of the cells in the Granite Wash, 97% in Eagle Ford Shale, 90% in Haynesville Shale, 79% in Permian Basin, and 78% in Barnett Shale were identified as better than "Average" locations; whereas, south of the Eagle Ford, southwestern Permian Basin, and the center of Granite Wash were "Excellent". Importantly, most of the locations with better than "Average" ADWI are within drought prone agricultural regions that would benefit from this resilient source of clean water.

Laboratory Animal Facilities. Laboratory Design Notes.

ERIC Educational Resources Information Center

Jonas, Albert M.

1965-01-01

Design of laboratory animal facilities must be functional. Accordingly, the designer should be aware of the complex nature of animal research and specifically the type of animal research which will be conducted in a new facility. The building of animal-care facilities in research institutions requires special knowledge in laboratory animal…

Preparing for radiological assessments in the event of a tornado strike at Argonne National Lab. -East

DOE Office of Scientific and Technical Information (OSTI.GOV)

Goodkind, M.E.; Klimczak, C.A.; Munyon, W.J.

1993-01-01

Argonne National Laboratory-East (ANL) is a Department of Energy (DOE)-owned, contractor-operated national laboratory located 22 miles southwest of downtown Chicago on a wooded, 1700-acre site. The principal nuclear facilities at ANL include a large fast neutron source (Intense Pulse Neutron Source) in which high-energy protons strike a uranium target to produce neutrons for research studies; [sup 60]Co irradiation sources; chemical and metallurgical plutonium laboratories, some of which are currently being decommissioned; several large hot cell facilities designed for work with multicurie quantities of actinide elements and irradiated reactor fuel materials; a few small research reactors currently in different phases ofmore » being decommissioned; and a variety of research laboratories handling many different sources in various chemical and physical forms. The hazards analysis for the ANL site shows that tornado strikes are a serious threat. The site has been struck twice in the past 20 yr, receiving only minor building damage and no release of radioactivity to the environment. Although radioactive materials in general are handled in areas that provide good tornado protection, ANL is prepared to address the problems that would occur should there be a loss of control of radioactive materials due to severe building damage.« less

The total laboratory solution: a new laboratory E-business model based on a vertical laboratory meta-network.

PubMed

Friedman, B A

2001-08-01

Major forces are now reshaping all businesses on a global basis, including the healthcare and clinical laboratory industries. One of the major forces at work is information technology (IT), which now provides the opportunity to create a new economic and business model for the clinical laboratory industry based on the creation of an integrated vertical meta-network, referred to here as the "total laboratory solution" (TLS). Participants at the most basic level of such a network would include a hospital-based laboratory, a reference laboratory, a laboratory information system/application service provider/laboratory portal vendor, an in vitro diagnostic manufacturer, and a pharmaceutical/biotechnology manufacturer. It is suggested that each of these participants would add value to the network primarily in its area of core competency. Subvariants of such a network have evolved over recent years, but a TLS comprising all or most of these participants does not exist at this time. Although the TLS, enabled by IT and closely akin to the various e-businesses that are now taking shape, offers many advantages from a theoretical perspective over the current laboratory business model, its success will depend largely on (a) market forces, (b) how the collaborative networks are organized and managed, and (c) whether the network can offer healthcare organizations higher quality testing services at lower cost. If the concept is successful, new demands will be placed on hospital-based laboratory professionals to shift the range of professional services that they offer toward clinical consulting, integration of laboratory information from multiple sources, and laboratory information management. These information management and integration tasks can only increase in complexity in the future as new genomic and proteomics testing modalities are developed and come on-line in clinical laboratories.

Laboratory Testing of Waste Isolation Pilot Plant Surrogate Waste Materials

NASA Astrophysics Data System (ADS)

Broome, S.; Bronowski, D.; Pfeifle, T.; Herrick, C. G.

2011-12-01

The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy geological repository for the permanent disposal of defense-related transuranic (TRU) waste. The waste is emplaced in rooms excavated in the bedded Salado salt formation at a depth of 655 m below the ground surface. After emplacement of the waste, the repository will be sealed and decommissioned. WIPP Performance Assessment modeling of the underground material response requires a full and accurate understanding of coupled mechanical, hydrological, and geochemical processes and how they evolve with time. This study was part of a broader test program focused on room closure, specifically the compaction behavior of waste and the constitutive relations to model this behavior. The goal of this study was to develop an improved waste constitutive model. The model parameters are developed based on a well designed set of test data. The constitutive model will then be used to realistically model evolution of the underground and to better understand the impacts on repository performance. The present study results are focused on laboratory testing of surrogate waste materials. The surrogate wastes correspond to a conservative estimate of the degraded containers and TRU waste materials after the 10,000 year regulatory period. Testing consists of hydrostatic, uniaxial, and triaxial tests performed on surrogate waste recipes that were previously developed by Hansen et al. (1997). These recipes can be divided into materials that simulate 50% and 100% degraded waste by weight. The percent degradation indicates the anticipated amount of iron corrosion, as well as the decomposition of cellulosics, plastics, and rubbers. Axial, lateral, and volumetric strain and axial and lateral stress measurements were made. Two unique testing techniques were developed during the course of the experimental program. The first involves the use of dilatometry to measure sample volumetric strain under a hydrostatic condition. Bulk

Errors in clinical laboratories or errors in laboratory medicine?

PubMed

Plebani, Mario

2006-01-01

Laboratory testing is a highly complex process and, although laboratory services are relatively safe, they are not as safe as they could or should be. Clinical laboratories have long focused their attention on quality control methods and quality assessment programs dealing with analytical aspects of testing. However, a growing body of evidence accumulated in recent decades demonstrates that quality in clinical laboratories cannot be assured by merely focusing on purely analytical aspects. The more recent surveys on errors in laboratory medicine conclude that in the delivery of laboratory testing, mistakes occur more frequently before (pre-analytical) and after (post-analytical) the test has been performed. Most errors are due to pre-analytical factors (46-68.2% of total errors), while a high error rate (18.5-47% of total errors) has also been found in the post-analytical phase. Errors due to analytical problems have been significantly reduced over time, but there is evidence that, particularly for immunoassays, interference may have a serious impact on patients. A description of the most frequent and risky pre-, intra- and post-analytical errors and advice on practical steps for measuring and reducing the risk of errors is therefore given in the present paper. Many mistakes in the Total Testing Process are called "laboratory errors", although these may be due to poor communication, action taken by others involved in the testing process (e.g., physicians, nurses and phlebotomists), or poorly designed processes, all of which are beyond the laboratory's control. Likewise, there is evidence that laboratory information is only partially utilized. A recent document from the International Organization for Standardization (ISO) recommends a new, broader definition of the term "laboratory error" and a classification of errors according to different criteria. In a modern approach to total quality, centered on patients' needs and satisfaction, the risk of errors and mistakes

Laboratory Information Systems.

PubMed

Henricks, Walter H

2015-06-01

Laboratory information systems (LISs) supply mission-critical capabilities for the vast array of information-processing needs of modern laboratories. LIS architectures include mainframe, client-server, and thin client configurations. The LIS database software manages a laboratory's data. LIS dictionaries are database tables that a laboratory uses to tailor an LIS to the unique needs of that laboratory. Anatomic pathology LIS (APLIS) functions play key roles throughout the pathology workflow, and laboratories rely on LIS management reports to monitor operations. This article describes the structure and functions of APLISs, with emphasis on their roles in laboratory operations and their relevance to pathologists. Copyright © 2015 Elsevier Inc. All rights reserved.

Secondary standards laboratories for ionizing radiation calibrations: The national laboratory interests

NASA Astrophysics Data System (ADS)

Roberson, P. I.; Campbell, G. W.

1984-11-01

The national laboratories are probable candidates to serve as secondary standards laboratories for the federal sector. Representatives of the major Department of Energy laboratories were polled concerning attitudes toward a secondary laboratory structure. Generally, the need for secondary laboratories was recognized and the development of such a program was encouraged. The secondary laboratories should be reviewed and inspected by the National Bureau of Standards. They should offer all of the essential, and preferably additional, calibration services in the field of radiological health protection. The selection of secondary laboratories should be based on economic and geographic criteria and/or be voluntary.

Roles of laboratories and laboratory systems in effective tuberculosis programmes.

PubMed

Ridderhof, John C; van Deun, Armand; Kam, Kai Man; Narayanan, P R; Aziz, Mohamed Abdul

2007-05-01

Laboratories and laboratory networks are a fundamental component of tuberculosis (TB) control, providing testing for diagnosis, surveillance and treatment monitoring at every level of the health-care system. New initiatives and resources to strengthen laboratory capacity and implement rapid and new diagnostic tests for TB will require recognition that laboratories are systems that require quality standards, appropriate human resources, and attention to safety in addition to supplies and equipment. To prepare the laboratory networks for new diagnostics and expanded capacity, we need to focus efforts on strengthening quality management systems (QMS) through additional resources for external quality assessment programmes for microscopy, culture, drug susceptibility testing (DST) and molecular diagnostics. QMS should also promote development of accreditation programmes to ensure adherence to standards to improve both the quality and credibility of the laboratory system within TB programmes. Corresponding attention must be given to addressing human resources at every level of the laboratory, with special consideration being given to new programmes for laboratory management and leadership skills. Strengthening laboratory networks will also involve setting up partnerships between TB programmes and those seeking to control other diseases in order to pool resources and to promote advocacy for quality standards, to develop strategies to integrate laboratories functions and to extend control programme activities to the private sector. Improving the laboratory system will assure that increased resources, in the form of supplies, equipment and facilities, will be invested in networks that are capable of providing effective testing to meet the goals of the Global Plan to Stop TB.

Final report of the decontamination and decommissioning of Building 1 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-08-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also is the remedial action contractor. Building 1more » was found to be radiologically contaminated and was demolished in 1996. The soil beneath and adjacent to the building was remediated in accordance with identified standards and can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Regulatory Supervision of Radiological Protection in the Russian Federation as Applied to Facility Decommissioning and Site Remediation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sneve, M.K.; Shandala, N.K.

2007-07-01

The Russian Federation is carrying out major work to manage the legacy of exploitation of nuclear power and use of radioactive materials. This paper describes work on-going to provide enhanced regulatory supervision of these activities as regards radiological protection. The scope includes worker and public protection in routine operation; emergency preparedness and response; radioactive waste management, including treatment, interim storage and transport as well as final disposal; and long term site restoration. Examples examined include waste from facilities in NW Russia, including remediation of previous shore technical bases (STBs) for submarines, spent fuel and radioactive waste management from ice-breakers, andmore » decommissioning of Radio-Thermal-Generators (RTGs) used in navigational devices. Consideration is given to the identification of regulatory responsibilities among different regulators; development of necessary regulatory instruments; and development of regulatory procedures for safety case reviews and compliance monitoring and international cooperation between different regulators. (authors)« less

Establishment of National Laboratory Standards in Public and Private Hospital Laboratories

PubMed Central

ANJARANI, Soghra; SAFADEL, Nooshafarin; DAHIM, Parisa; AMINI, Rana; MAHDAVI, Saeed; MIRAB SAMIEE, Siamak

2013-01-01

In September 2007 national standard manual was finalized and officially announced as the minimal quality requirements for all medical laboratories in the country. Apart from auditing laboratories, Reference Health Laboratory has performed benchmarking auditing of medical laboratory network (surveys) in provinces. 12th benchmarks performed in Tehran and Alborz provinces, Iran in 2010 in three stages. We tried to compare different processes, their quality and accordance with national standard measures between public and private hospital laboratories. The assessment tool was a standardized checklist consists of 164 questions. Analyzing process show although in most cases implementing the standard requirements are more prominent in private laboratories, there is still a long way to complete fulfillment of requirements, and it takes a lot of effort. Differences between laboratories in public and private sectors especially in laboratory personnel and management process are significant. Probably lack of motivation, plays a key role in obtaining less desirable results in laboratories in public sectors. PMID:23514840

The Language Laboratory.

ERIC Educational Resources Information Center

Hughes, John P.

Concepts pertaining to the language laboratory are clarified for the layman unfamiliar with recent educational developments in foreign language instruction. These include discussion of: (1) language laboratory components and functions, (2) techniques used in the laboratory, (3) new linguistic methods, (4) laboratory exercises, (5) traditional…

Roles of laboratories and laboratory systems in effective tuberculosis programmes

PubMed Central

van Deun, Armand; Kam, Kai Man; Narayanan, PR; Aziz, Mohamed Abdul

2007-01-01

Abstract Laboratories and laboratory networks are a fundamental component of tuberculosis (TB) control, providing testing for diagnosis, surveillance and treatment monitoring at every level of the health-care system. New initiatives and resources to strengthen laboratory capacity and implement rapid and new diagnostic tests for TB will require recognition that laboratories are systems that require quality standards, appropriate human resources, and attention to safety in addition to supplies and equipment. To prepare the laboratory networks for new diagnostics and expanded capacity, we need to focus efforts on strengthening quality management systems (QMS) through additional resources for external quality assessment programmes for microscopy, culture, drug susceptibility testing (DST) and molecular diagnostics. QMS should also promote development of accreditation programmes to ensure adherence to standards to improve both the quality and credibility of the laboratory system within TB programmes. Corresponding attention must be given to addressing human resources at every level of the laboratory, with special consideration being given to new programmes for laboratory management and leadership skills. Strengthening laboratory networks will also involve setting up partnerships between TB programmes and those seeking to control other diseases in order to pool resources and to promote advocacy for quality standards, to develop strategies to integrate laboratories’ functions and to extend control programme activities to the private sector. Improving the laboratory system will assure that increased resources, in the form of supplies, equipment and facilities, will be invested in networks that are capable of providing effective testing to meet the goals of the Global Plan to Stop TB. PMID:17639219

Current significant challenges in the decommissioning and environmental remediation of radioactive facilities: A perspective from outside the nuclear industry.

PubMed

Gil-Cerezo, V; Domínguez-Vilches, E; González-Barrios, A J

2017-05-01

This paper presents the results of implementing an extrajudicial environmental mediation procedure in the socioenvironmental conflict associated with routine operation of the El Cabril Disposal Facility for low- and medium- activity radioactive waste (Spain). We analyse the socio-ethical perspective of this facility's operation with regard to its nearby residents, detailing the structure and development of the environmental mediation procedure through the participation of society and interested parties who are or may become involved in such a conflict. The research, action, and participation method was used to apply the environmental mediation procedure. This experience provides lessons that could help improve decision-making processes in nuclear or radioactive facility decommissioning projects or in environmental remediation projects dealing with ageing facilities or with those in which nuclear or radioactive accidents/incidents may have occurred. Copyright © 2017 Elsevier Ltd. All rights reserved.

POLLUTION PREVENTION OPPORTUNITY ASSESSMENT - GEOCHEMISTRY LABORATORY AT SANDIA NATIONAL LABORATORIES

EPA Science Inventory

These reports summarize pollution prevention opportunity assessments conducted jointly by EPA and DOE at the Geochemistry Laboratory and the Manufacturing and Fabrication Repair Laboratory at the Department of Energy's Sandia National Laboratories facility in Albuquerque, New Mex...

RH-TRU Waste Shipments from Battelle Columbus Laboratories to the Hanford Nuclear Facility for Interim Storage

DOE Office of Scientific and Technical Information (OSTI.GOV)

Eide, J.; Baillieul, T. A.; Biedscheid, J.

2003-02-26

Battelle Columbus Laboratories (BCL), located in Columbus, Ohio, must complete decontamination and decommissioning (D&D) activities for nuclear research buildings and grounds by 2006, as directed by Congress. Most of the resulting waste (approximately 27 cubic meters [m3]) is remote-handled (RH) transuranic (TRU) waste destined for disposal at the Waste Isolation Pilot Plant (WIPP). The BCL, under a contract to the U.S. Department of Energy (DOE) Ohio Field Office, has initiated a plan to ship the TRU waste to the DOE Hanford Nuclear Facility (Hanford) for interim storage pending the authorization of WIPP for the permanent disposal of RH-TRU waste. Themore » first of the BCL RH-TRU waste shipments was successfully completed on December 18, 2002. This BCL shipment of one fully loaded 10-160B Cask was the first shipment of RH-TRU waste in several years. Its successful completion required a complex effort entailing coordination between different contractors and federal agencies to establish necessary supporting agreements. This paper discusses the agreements and funding mechanisms used in support of the BCL shipments of TRU waste to Hanford for interim storage. In addition, this paper presents a summary of the efforts completed to demonstrate the effectiveness of the 10-160B Cask system. Lessons learned during this process are discussed and may be applicable to other TRU waste site shipment plans.« less

Skylab mobile laboratory

NASA Technical Reports Server (NTRS)

Primeaux, G. R.; Larue, M. A.

1975-01-01

The Skylab mobile laboratory was designed to provide the capability to obtain necessary data on the Skylab crewmen 30 days before lift-off, within 1 hour after recovery, and until preflight physiological baselines were reattained. The mobile laboratory complex consisted of six laboratories that supported cardiovascular, metabolic, nutrition and endocrinology, operational medicine, blood, and microbiology experiments; a utility package; and two shipping containers. The objectives and equipment requirements of the Skylab mobile laboratory and the data acquisition systems are discussed along with processes such as permanently mounting equipment in the individual laboratories and methods of testing and transporting the units. The operational performance, in terms of amounts of data collected, and the concept of mobile laboratories for medical and scientific experiments are evaluated. The Skylab mobile laboratory succeeded in facilitating the data collection and sample preservation associated with the three Skylab manned flights.

Teaching laboratory neuroscience at bowdoin: the laboratory instructor perspective.

PubMed

Hauptman, Stephen; Curtis, Nancy

2009-01-01

Bowdoin College is a small liberal arts college that offers a comprehensive Neuroscience major. The laboratory experience is an integral part of the major, and many students progress through three stages. A core course offers a survey of concepts and techniques. Four upper-level courses function to give students more intensive laboratory research experience in neurophysiology, molecular neurobiology, social behavior, and learning and memory. Finally, many majors choose to work in the individual research labs of the Neuroscience faculty. We, as laboratory instructors, are vital to the process, and are actively involved in all aspects of the lab-based courses. We provide student instruction in state of the art techniques in neuroscience research. By sharing laboratory teaching responsibilities with course professors, we help to prepare students for careers in laboratory neuroscience and also support and facilitate faculty research programs.

Hg soil pollution around a decommissioned and unrestored Chlor-alkali plant: Jodar, Jaén province, SE Spain. Incidence in other environmental compartments.

NASA Astrophysics Data System (ADS)

López-Berdonces, Miguel Angel; María Esbrí, José; Lorenzo, Saturnino; Higueras, Pablo

2014-05-01

Data from soil pollution and its consequences around a decommissioned chlor-alkali plant are presented in this communication. The plant was active in the period 1977-1991, producing during these years a heavily pollution of Guadalquivir River and hidrargirism in more than local 45 workers. It is located at 7 km South of Jódar, a locality with some 12,120 inhabitants. Mercury usage was general in this type of plants, but at present it is being replaced by other types of technologies, due to the risks of mercury usage in personal and environment. A soil geochemistry survey was carried out in the area, together with the analysis of olive-tree leaves from the same area. 75 soil samples were taken at two different depths (0-15 cm. and 15-30 cm), together with 75 olive tree samples, 5 water samples. Besides, two monitoring surveys for total gaseous mercury in the atmosphere were performed. Mercury content of geologic and biologic samples was determined by means of Atomic Absorption Spectrometry with Zeeman Effect, using a Lumex RA-915+ device with the RP-91C pyrolysis attachment. Air surveys were carried our using a RA-915M Lumex portable analytical device, with GPS georreferenciation of the analysis points. Soil mercury contents were higher in topsoil than in the deeper soil samples, indicating that incorporation of mercury was due to dry and wet deposition of mercury vapors emitted from the plant. A local reference level was calculated as GM + 2SD (where GM is the geometric mean and SD the standard deviation). With this reference level it was possible to delimitate a contaminated soil area centered on the decommissioned chlor-alkali plant. A high affinity of local olive trees to accumulate mercury from the contaminated soil was also found, with a calculated maximum mercury content of 243.5 ng g-1. This maximum level is slightly higher than tolerable level for agronomic crops. Total mercury content in the analyzed waters was slightly higher than the chronic exposure

Transcriptional deregulation of oncogenic myocyte enhancer factor 2C in T-cell acute lymphoblastic leukemia.

PubMed

Nagel, Stefan; Venturini, Letizia; Meyer, Corinna; Kaufmann, Maren; Scherr, Michaela; Drexler, Hans G; Macleod, Roderick A F

2011-02-01

Myocyte enhancer factor 2C (MEF2C) encodes a transcription factor which is ectopically expressed in T-cell acute lymphoblastic leukemia (T-ALL) cell lines, deregulated directly by ectopically expressed homeodomain protein NKX2-5 or by loss of promoter regions via del(5)(q14). Here, we analyzed the MEF2C 5'-region, thus identifying potential regulatory binding sites for GFI1B, basic helix-loop-helix proteins, STAT5, and HOXA9/HOXA10. Chromatin immunoprecipitation and overexpression analyses demonstrated direct activation by GFI1B and LYL1 and inhibition by STAT5. HOXA9/HOXA10 activated expression of NMYC which in turn mediated MEF2C repression, indicating an indirect mode of regulation via NMYC interactor (NMI) and STAT5. Lacking comma: Chromosomal deletion of the STAT5 binding site in LOUCY cells reduced protein levels of STAT5 in some MEF2C-positve T-ALL cell lines, and the presence of inhibitory IL7-JAK-STAT5 signaling highlighted the repressive impact of this factor in MEF2C regulation. Taken together, our results indicate that the expression of MEF2C in T-ALL cells is principally deregulated via activating leukemic transcription factors GFI1B or NKX2-5 and by escaping inhibitory developmental STAT5 signaling.

Damage of the Interface Between an Orthodontic Bracket and Enamel - the Effect of Some Elastic Properties of the Adhesive Material

NASA Astrophysics Data System (ADS)

Durgesh, B. H.; Alkheraif, A. A.; Al Sharawy, M.; Varrela, J.; Vallittu, P. K.

2016-01-01

The aim of this study was to investigate the magnitude of debonding stress of an orthodontic bracket bonded to the enamel with resin systems having different elastic properties. For the same purpose, sixty human premolars were randomly divided into four groups according to the adhesive system used for bonding brackets: G Fix flowable resin (GFI) with Everstick NET (ESN), GFI, G Aenial Universal Flow (GAU) with ESN, and GAU. The brackets were stressed in the occlusogingival direction on a universal testing machine. The values of debonding load and displacement were determined at the point of debonding. The elastic modulus of the tested materials was determined using nanoindentation. An analysis of variance showed a significant difference in the loads required to debond the bracket among the groups tested. The GAU group had the highest elastic modulus, followed by the GFI and ESN groups. ARI (Adhesive Remnant Index) scores demonstrated more remnants of the adhesive material on the bracket surface with adhesives having a higher elastic modulus. Taking into consideration results of the present in-vitro study, it can be concluded that the incorporation of a glass-fiber-reinforced composite resin (FRC) with a low elastic modulus between the orthodontic bracket and enamel increases the debonding force and strain more than with adhesive systems having a higher elastic modulus.

Laboratory Building

DOE Office of Scientific and Technical Information (OSTI.GOV)

Herrera, Joshua M.

2015-03-01

This report is an analysis of the means of egress and life safety requirements for the laboratory building. The building is located at Sandia National Laboratories (SNL) in Albuquerque, NM. The report includes a prescriptive-based analysis as well as a performance-based analysis. Following the analysis are appendices which contain maps of the laboratory building used throughout the analysis. The top of all the maps is assumed to be north.

Site Environmental Report for Calendar Year 2008. DOE Operations at The Boeing Company Santa Susana Field Laboratory, Area IV

DOE Office of Scientific and Technical Information (OSTI.GOV)

Liu, Ning; Rutherford, Phil; Amar, Ravnesh

2009-09-01

This Annual Site Environmental Report (ASER) for 2008 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988; allmore » subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. In May 2007, the D&D operations in Area IV were suspended by the DOE. The environmental monitoring programs were continued throughout the year. Results of the radiological monitoring program for the calendar year 2008 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less

Virtual Laboratory "vs." Traditional Laboratory: Which Is More Effective for Teaching Electrochemistry?

ERIC Educational Resources Information Center

Hawkins, Ian; Phelps, Amy J.

2013-01-01

The use of virtual laboratories has become an increasing issue regarding science laboratories due to the increasing cost of hands-on laboratories, and the increase in distance education. Recent studies have looked at the use of virtual tools for laboratory to be used as supplements to the regular hands-on laboratories but many virtual tools have…

Calgary Laboratory Services

PubMed Central

2015-01-01

Calgary Laboratory Services provides global hospital and community laboratory services for Calgary and surrounding areas (population 1.4 million) and global academic support for the University of Calgary Cumming School of Medicine. It developed rapidly after the Alberta Provincial Government implemented an austerity program to address rising health care costs and to address Alberta’s debt and deficit in 1994. Over roughly the next year, all hospital and community laboratory test funding within the province was put into a single budget, fee codes for fee-for-service test billing were closed, roughly 40% of the provincial laboratory budget was cut, and roughly 40% of the pathologists left the province of Alberta. In Calgary, in the face of these abrupt changes in the laboratory environment, private laboratories, publicly funded hospital laboratories and the medical school department precipitously and reluctantly merged in 1996. The origin of Calgary Laboratory Services was likened to an “unhappy shotgun marriage” by all parties. Although such a structure could save money by eliminating duplicated services and excess capacity and could provide excellent city-wide clinical service by increasing standardization, it was less clear whether it could provide strong academic support for a medical school. Over the past decade, iterations of the Calgary Laboratory Services model have been implemented or are being considered in other Canadian jurisdictions. This case study analyzes the evolution of Calgary Laboratory Services, provides a metric-based review of academic performance over time, and demonstrates that this model, essentially arising as an unplanned experiment, has merit within a Canadian health care context. PMID:28725754

Laboratory hemostasis: milestones in Clinical Chemistry and Laboratory Medicine.

PubMed

Lippi, Giuseppe; Favaloro, Emmanuel J

2013-01-01

Hemostasis is a delicate, dynamic and intricate system, in which pro- and anti-coagulant forces cooperate for either maintaining blood fluidity under normal conditions, or else will prompt blood clot generation to limit the bleeding when the integrity of blood vessels is jeopardized. Excessive prevalence of anticoagulant forces leads to hemorrhage, whereas excessive activation of procoagulant forces triggers excessive coagulation and thrombosis. The hemostasis laboratory performs a variety of first, second and third line tests, and plays a pivotal role in diagnostic and monitoring of most hemostasis disturbances. Since the leading targets of Clinical Chemistry and Laboratory Medicine include promotion of progress in fundamental and applied research, along with publication of guidelines and recommendations in laboratory diagnostics, this journal is an ideal source of information on current developments in the laboratory technology of hemostasis, and this article is aimed to celebrate some of the most important and popular articles ever published by the journal in the filed of laboratory hemostasis.

Spatiotemporal changes of freezing/thawing indices and their response to recent climate change on the Qinghai-Tibet Plateau from 1980 to 2013

NASA Astrophysics Data System (ADS)

Wu, Tonghua; Qin, Yanhui; Wu, Xiaodong; Li, Ren; Zou, Defu; Xie, Changwei

2018-05-01

The spatial and temporal changes of the ground surface freezing indices (GFIs), ground surface thawing indices (GTIs), air freezing indices (AFIs), and air thawing indices (ATIs) in permafrost and seasonally frozen ground regions of the Qinghai-Tibet Plateau (QTP) were analyzed based on the daily ground surface and air temperatures from 69 meteorological stations using the Mann-Kendall test and Sen's slope estimate. The spatial patterns of the freezing indices (FIs) and thawing indices (TIs) are nearly negatively correlated. On the annual scale, the GFI and GTI are greater than the AFI and ATI in both permafrost and seasonally frozen ground regions. The marked upward and downward trends have been observed for the time series of TI and FI, respectively, since 1998 on the QTP. Moreover, GFI and AFI decrease more significantly in permafrost regions than in seasonally frozen ground regions; the increasing rate of GTI and ATI in the seasonally frozen ground regions is greater than that in the permafrost regions. In permafrost regions, the downward trend of FI is greater than the upward trend of TI. However, the upward trend of TI shows a more drastic change than the FI in the seasonally frozen ground regions. The results indicate that the warming in the permafrost regions is more pronounced in winter than in the other seasons. The summer warming is more pronounced than the other seasons in the seasonally frozen ground regions. The decreasing rate of AFI and GFI increases as the altitude rises, while they decrease with increasing ATI. The average decreasing rate of GFI is greater than that of the AFI in different altitudinal zones. The greatest decrease of FI occurs in permafrost regions in the hinterland of the QTP, which indicates the dominant winter warming in this region. The downward trend of FI and upward trend of TI are responsible for the reported permafrost degradation on the QTP.

Environmental assessment for the construction, operation, and decommissioning of the Waste Segregation Facility at the Savannah River Site

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1998-01-01

This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the construction, operation and decontamination and decommissioning (D&D) of the Waste Segregation Facility (WSF) for the sorting, shredding, and compaction of low-level radioactive waste (LLW) at the Savannah River Site (SRS) located near Aiken, South Carolina. The LLW to be processed consists of two waste streams: legacy waste which is currently stored in E-Area Vaults of SRS and new waste generated from continuing operations. The proposed action is to construct, operate, and D&D a facility to process low-activity job-controlmore » and equipment waste for volume reduction. The LLW would be processed to make more efficient use of low-level waste disposal capacity (E-Area Vaults) or to meet the waste acceptance criteria for treatment at the Consolidated Incineration Facility (CIF) at SRS.« less

Laboratory Governance: Issues for the Study Group on Regional Laboratories.

ERIC Educational Resources Information Center

Schultz, Thomas; Dominic, Joseph

Background information and an analysis of issues involved in the governance of new regional educational laboratories are presented. The new laboratories are to be established through a 1984 competition administered by the National Institute of Education (NIE). The analysis is designed to assist the Study Group on Regional Laboratories to advise…

Economic Education Laboratory: Initiating a Meaningful Economic Learning through Laboratory

ERIC Educational Resources Information Center

Noviani, Leny; Soetjipto, Budi Eko; Sabandi, Muhammad

2015-01-01

Laboratory is considered as one of the resources in supporting the learning process. The laboratory can be used as facilities to deepen the concepts, learning methods and enriching students' knowledge and skills. Learning process by utilizing the laboratory facilities can help lecturers and students in grasping the concept easily, constructing the…

A comprehensive Laboratory Services Survey of State Public Health Laboratories.

PubMed

Inhorn, Stanley L; Wilcke, Burton W; Downes, Frances Pouch; Adjanor, Oluwatosin Omolade; Cada, Ronald; Ford, James R

2006-01-01

In November 2004, the Association of Public Health Laboratories (APHL) conducted a Comprehensive Laboratory Services Survey of State Public Health Laboratories (SPHLs) in order to establish the baseline data necessary for Healthy People 2010 Objective 23-13. This objective aims to measure the increase in the proportion of health agencies that provide or assure access to comprehensive laboratory services to support essential public health services. This assessment addressed only SPHLs and served as a baseline to periodically evaluate the level of improvement in the provision of laboratory services over the decade ending 2010. The 2004 survey used selected questions that were identified as key indicators of provision of comprehensive laboratory services. The survey was developed in consultation with the Centers for Disease Control and Prevention National Center for Health Statistics, based on newly developed data sources. Forty-seven states and one territory responded to the survey. The survey was based on the 11 core functions of SPHLs as previously defined by APHL. The range of performance among individual laboratories for the 11 core functions (subobjectives) reflects the challenging issues that have confronted SPHLs in the first half of this decade. APHL is now working on a coordinated effort with other stakeholders to create seamless state and national systems for the provision of laboratory services in support of public health programs. These services are necessary to help face the threats raised by the specter of terrorism, emerging infections, and natural disasters.

Progressive loss of sensitivity to growth control by retinoic acid and transforming growth factor-beta at late stages of human papillomavirus type 16-initiated transformation of human keratinocytes.

PubMed

Creek, K E; Geslani, G; Batova, A; Pirisi, L

1995-01-01

Retinoids (vitamin A and its natural and synthetic derivatives) have shown potential as chemopreventive agents, and diets poor in vitamin A and/or its precursor beta-carotene have been linked to an increased risk of cancer at several sites including the cervix. Human papillomavirus (HPV) plays an important role in the etiology of cervical cancer. We have developed an in vitro model of cancer progression using human keratinocytes (HKc) immortalized by HPV16 DNA (HKc/HPV16). Although immortal, early passage HKc/HPV16, like normal HKc, require epidermal growth factor (EGF) and bovine pituitary extract (BPE) for proliferation and undergo terminal differentiation in response to serum and calcium. However, following prolonged culture, growth factor independent HKc/HPV16 lines that no longer require EGF and BPE can be selected (HKc/GFI). Further selection of HKc/GFI produces lines that are resistant to serum- and calcium- induced terminal differentiation (HKc/DR). HKc/DR, but not early passage HKc/HPV16, are susceptible to malignant conversion following transfection with viral Harvey ras or Herpes simplex virus type II DNA. We have investigated the sensitivity of low to high passage HKc/HPV16 and HKc/GFI to growth control by all-trans-retinoic acid (RA, an active metabolite of vitamin A). Early passage HKc/HPV16 are very sensitive to growth inhibition by RA, and in these cells RA decreases the expression of the HPV16 oncogenes E6 and E7. However, as the cells progress in culture they lose their sensitivity to RA. Growth inhibition by RA may be mediated through the cytokine transforming growth factor-beta (TGF-beta), a potent inhibitor of epithelial cell proliferation. RA treatment of HKc/HPV16 and HKc/GFI results in a dose-and time-dependent induction (maximal of 3-fold) in secreted levels of TGF-beta. Also, Northern blot analysis of mRNA isolated from HKc/HPV16 demonstrated that RA treatment induced TGF-beta 1 and TGF-beta 2 expression about 3- and 50-fold, respectively

Creep Laboratory manual

NASA Astrophysics Data System (ADS)

Osgerby, S.; Loveday, M. S.

1992-06-01

A manual for the NPL Creep Laboratory, a collective name given to two testing laboratories, the Uniaxial Creep Laboratory and the Advanced High Temperature Mechanical Testing Laboratory, is presented. The first laboratory is devoted to uniaxial creep testing and houses approximately 50 high sensitivity creep machines including 10 constant stress cam lever machines. The second laboratory houses a low cycle fatigue testing machine of 100 kN capacity driven by a servo-electric actuator, five machines for uniaxial tensile creep testing of engineering ceramics at temperatures up to 1600C, and an electronic creep machine. Details of the operational procedures for carrying out uniaxial creep testing are given. Calibration procedures to be followed in order to comply with the specifications laid down by British standards, and to provide traceability back to the primary standards are described.

Structural Evaluation of the Second Oldest Glued-Laminated Structure in the United States

Treesearch

Douglas R. Rammer; Jorge de Melo Moura

2013-01-01

The second glued-laminated structure built in the United States was constructed at the USDA Forest Products Laboratory (FPL) in 1934 to demonstrate the performance of wooden arch buildings. After decades of use the structure was decommissioned in 2010. Shortly after construction, researchers structurally evaluated the glued-laminated arch structure for uniform loading...

2016 Inspection and Annual Site Status Report for the Site A/Plot M, Illinois, Decommissioned Reactor Site July 2016

DOE Office of Scientific and Technical Information (OSTI.GOV)

Murl, Jeffrey; Miller, Michele

The Site A/Plot M, Illinois, Decommissioned Reactor Site was inspected on May 17, 2016. The site, located within Cook County forest preserve that is open to the public, was found to be in good condition with one exception. Erosion on top of the grass-covered mound at Plot M continues to be a concern as presented in previous inspections. Ruts form in the soil on top of Plot M as a result of bike traffic using the open field as a pass thru between established bike trails within the forest preserve. Argonne National Laboratory (ANL) who is contracted directly from U.S.more » Department of Energy (DOE) has filled in the ruts with top soil and reseeding remains an ongoing process. Reseeded areas from 2015 are progressing nicely. No cause for a follow-up inspection was identified. In 2015, ANL plugged and abandoned 8 of 25 monitoring wells (BH41, BH51, BH52, BH54, DH9, DH10, DH13, and DH17). The 17 groundwater monitoring wells remaining at the site were inspected to confirm that they were locked and in good condition. Preliminary environmental monitoring results for 2015 are provided in a draft report titled Surveillance of Site A and Plot M, Report for 2015, prepared by ANL. The report also contains results of an independent analysis conducted by the Illinois Emergency Management Agency on some of the samples collected by ANL in 2015. The draft report states that the results of the surveillance program continue to indicate that the impact of radioactivity at Site A/Plot M is very low and does not endanger the health of those living in the area or visiting the site. The ANL monitoring report will be made available to the public on the DOE Office of Legacy Management public website when it is issued as final. A new county forest preserve campsite opened in 2015 at Bull Frog Lake, which is east of Plot M. Hiking trails connect Bull Frog Lake with Site A/Plot M. The site might receive more traffic from forest preserve visitors now that this new campsite is opened.« less

Ecological aspects of decommissioning and decontamination of facilities on the Hanford Reservation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rickard, W.H.; Klepper, E.L.

1976-06-01

The Hanford environment and biota are described in relation to decommissioning of obsolescent facilities contaminated with low-levels of radioactive materials. The aridity at Hanford limits both the productivity and diversity of biota. Both productivity and diversity are increased when water is added, as for example on the margins of ponds. Certain plants, especially Salsola kali (Russian thistle or tumbleweed), are avid accumulators of minerals and will accumulate radioactive materials if their roots come into contact with contaminated soils. Data on concentration ratios (pCi per gDW of plant/pCi per gDW soil) are given for several native plants for long-lived radionuclides. Plantsmore » are generally more resistant than animals to ionizing radiation so that impacts of high-level radiation sources would be expected to occur primarily in the animals. Mammals and birds are discussed along with information on where they are to be found on the Reservation and what role they may play in the long-term management of radioactive wastes. Food habits of animals are discussed and plants which are palatable to common herbivores are listed. Food chains leading to man are shown to be very limited, including a soil-plant-mule deer-man path for terrestrial sites and a pond-waterfowl-man pathway for pond sites. Retention basins are discussed as an example of how an ecologically sound decommissioningprogram might be planned. Finally, burial of large volumes of low-level wastes can probably be done if barriers to biological invasion are provided.« less

Preservice laboratory education strengthening enhances sustainable laboratory workforce in Ethiopia

PubMed Central

2013-01-01

Background There is a severe healthcare workforce shortage in sub Saharan Africa, which threatens achieving the Millennium Development Goals and attaining an AIDS-free generation. The strength of a healthcare system depends on the skills, competencies, values and availability of its workforce. A well-trained and competent laboratory technologist ensures accurate and reliable results for use in prevention, diagnosis, care and treatment of diseases. Methods An assessment of existing preservice education of five medical laboratory schools, followed by remedial intervention and monitoring was conducted. The remedial interventions included 1) standardizing curriculum and implementation; 2) training faculty staff on pedagogical methods and quality management systems; 3) providing teaching materials; and 4) procuring equipment for teaching laboratories to provide practical skills to complement didactic education. Results A total of 2,230 undergraduate students from the five universities benefitted from the standardized curriculum. University of Gondar accounted for 252 of 2,230 (11.3%) of the students, Addis Ababa University for 663 (29.7%), Jimma University for 649 (29.1%), Haramaya University for 429 (19.2%) and Hawassa University for 237 (10.6%) of the students. Together the universities graduated 388 and 312 laboratory technologists in 2010/2011 and 2011/2012 academic year, respectively. Practical hands-on training and experience with well-equipped laboratories enhanced and ensured skilled, confident and competent laboratory technologists upon graduation. Conclusions Strengthening preservice laboratory education is feasible in resource-limited settings, and emphasizing its merits (ample local capacity, country ownership and sustainability) provides a valuable source of competent laboratory technologists to relieve an overstretched healthcare system. PMID:24164781

Safety in laboratories: Indian scenario.

PubMed

Mustafa, Ajaz; Farooq, A Jan; Qadri, Gj; S A, Tabish

2008-07-01

Health and safety in clinical laboratories is becoming an increasingly important subject as a result of emergence of highly infectious diseases such as Hepatitis and HIV. A cross sectional study was carried out to study the safety measures being adopted in clinical laboratories of India. Heads of laboratories of teaching hospitals of India were subjected to a standardized, pretested questionnaire. Response rate was 44.8%. only 60% of laboratories had person in-charge of safety in laboratory. Seventy three percent of laboratories had safety education program regarding hazards. In 91% of laboratories staff is using protective clothing while working in laboratories. Hazardous material regulations are followed in 78% of laboratories. Regular health check ups are carried among laboratory staff in 43.4% of laboratories.Safety manual is available in 56.5% of laboratories. 73.9% of laboratories are equipped with fire extinguishers. Fume cupboards are provided in 34.7% of laboratories and they are regularly checked in 87.5% of these laboratories. In 78.26% of laboratories suitable measures are taken to minimize formation of aerosols.In 95.6% of laboratories waste is disposed off as per bio-medical waste management handling rules. Laboratory of one private medical college was accredited with NABL and safety parameters were better in that laboratory. Installing safety engineered devices apparently contributes to significant decrease in injuries in laboratories; laboratory safety has to be a part of overall quality assurance programme in hospitals. Accreditation has to be made necessary for all laboratories.

Final report of the decontamination and decommissioning of Building 6 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-07-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the domestic uranium procurement program funded by the U.S. Atomic Energy Commission. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, is also the remedial actionmore » contractor. Radiological contamination was identified in Building 6, and the building was demolished in 1992. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Final report of the decontamination and decommissioning of Building 34 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-08-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7 acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the Grand Junction Projects Office Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, was also the remedialmore » action contractor. Building 34 was radiologically contaminated and the building was demolished in 1996. The soil area within the footprint of the building was analyzed and found to be not contaminated. The area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual closeout report for each contaminated GJPO building.« less

Final report of the decontamination and decommissioning of Building 39 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-07-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, is also the remedial action contractor. The soilmore » beneath Building 39 was radiologically contaminated and the building was demolished in 1992. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Final report of the decontamination and decommissioning of Building 44 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-07-01

The U.S. Department of Energy (DOE) Junction Projects Office (GJPO) occupies a 61.7 acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the Grand Junction Projects Office Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, is also the remedial actionmore » contractor. Building 44 was radiologically contaminated and the building was demolished in 1994. The soil area within the footprint of the building was not contaminated; it complies with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Final report of the decontamination and decommissioning of Building 18 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Widdop, M.R.

1996-08-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also is the remedial action contractor. The soilmore » beneath Building 18 was found to be radiologically contaminated; the building was not contaminated. The soil was remediated in accordance with identified standards. Building 18 and the underlying soil can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Undergraduate Chemistry Laboratory

ERIC Educational Resources Information Center

Bretz, Stacey Lowery; Fay, Michael; Bruck, Laura B.; Towns, Marcy H.

2013-01-01

Forty chemistry faculty from American Chemical Society-approved departments were interviewed to determine their goals for undergraduate chemistry laboratory. Faculty were stratified by type of institution, departmental success with regard to National Science Foundation funding for laboratory reform, and level of laboratory course. Interview…

Laboratory Equipment Criteria.

ERIC Educational Resources Information Center

State Univ. Construction Fund, Albany, NY.

Requirements for planning, designing, constructing and installing laboratory furniture are given in conjunction with establishing facility criteria for housing laboratory equipment. Furniture and equipment described include--(1) center tables, (2) reagent racks, (3) laboratory benches and their mechanical fixtures, (4) sink and work counters, (5)…

42 CFR 493.1355 - Condition: Laboratories performing PPM procedures; laboratory director.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 42 Public Health 5 2010-10-01 2010-10-01 false Condition: Laboratories performing PPM procedures; laboratory director. 493.1355 Section 493.1355 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS...

42 CFR 493.1355 - Condition: Laboratories performing PPM procedures; laboratory director.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 42 Public Health 5 2011-10-01 2011-10-01 false Condition: Laboratories performing PPM procedures; laboratory director. 493.1355 Section 493.1355 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS...

Theme: Laboratory Instruction.

ERIC Educational Resources Information Center

Bruening, Thomas H.; And Others

1992-01-01

A series of theme articles discuss setting up laboratory hydroponics units, the school farm at the Zuni Pueblo in New Mexico, laboratory experiences in natural resources management and urban horticulture, the development of teaching labs at Derry (PA) High School, management of instructional laboratories, and industry involvement in agricultural…

Structural Performance of the Second Oldest Glued-Laminated Structure in the United States

Treesearch

Douglas R. Rammer; Jorge de Melo Moura; Robert J. Ross

2014-01-01

The second glued-laminated structure built in the United States was constructed at the USDA Forest Products Laboratory (FPL) in 1934 to demonstrate the performance of wooden arch buildings. After 75 years of use the structure was decommissioned in 2010. Shortly after construction, researchers structurally evaluated the glued-laminated arch structure for uniform loading...

Safety in the Chemical Laboratory: Procedures for Laboratory Destruction of Chemicals.

ERIC Educational Resources Information Center

McKusick, Blaine C.

1984-01-01

Discusses a National Research Council report which summarizes what laboratories need to know about Environmental Protection Agency and Department of Transportation regulations that apply to laboratory waste. The report provides guidelines for establishing and operating waste management systems for laboratories and gives specific advice on waste…

Understanding and managing health and environmental risks of CIS, CGS, and CdTe photovoltaic module production and use: A workshop

DOE Office of Scientific and Technical Information (OSTI.GOV)

Moskowitz, P.D.; Zweibel, K.; DePhillips, M.P.

1994-04-28

Environmental, health and safety (EH&S) risks presented by CIS, CGS and CdTe photovoltaic module production, use and decommissioning have been reviewed and discussed by several authors. Several EH&S concerns exit. The estimated EH&S risks are based on extrapolations of toxicity, environmental mobility, and bioavailability data for other related inorganic compounds. Sparse data, however, are available for CIS, CGS or CdTe. In response to the increased interest in these materials, Brookhaven National Laboratory (BNL) has been engaged in a cooperative research program with the National Renewable Energy Laboratory (NREL), the Fraunhofer Institute for Solid State Technology (IFT), the Institute of Ecotoxicitymore » of the GSF Forschungszentrum fair Umwelt und Gesundheit, and the National Institute of Environmental Health Sciences (NIEHS) to develop fundamental toxicological and environmental data for these three compounds. This workshop report describes the results of these studies and describes their potential implications with respect to the EH&S risks presented by CIS, CGS, and CdTe module production, use and decommissioning.« less

Inter-laboratory comparison measurements of radiochemical laboratories in Slovakia.

PubMed

Meresová, J; Belanová, A; Vrsková, M

2010-01-01

The first inter-laboratory comparison organized by the radiochemistry laboratory of Water Research Institute (WRI) in Bratislava was carried out in 1993 and since then is it realized on an annual basis and about 10 radiochemical laboratories from all over Slovakia are participating. The gross alpha and gross beta activities, and the activity concentrations of (222)Rn, tritium, and (226)Ra, and U(nat) concentration in synthetic water samples are compared. The distributed samples are covering the concentration range prevailing in potable and surface waters and are prepared by dilution of certified reference materials. Over the course of the years 1993-2008, we observed the improvement in the quality of results for most of the laboratories. However, the success rate of the gross alpha determination activity is not improving as much as the other parameters. Copyright 2009 Elsevier Ltd. All rights reserved.

A dose assessment method for arbitrary geometries with virtual reality in the nuclear facilities decommissioning

NASA Astrophysics Data System (ADS)

Chao, Nan; Liu, Yong-kuo; Xia, Hong; Ayodeji, Abiodun; Bai, Lu

2018-03-01

During the decommissioning of nuclear facilities, a large number of cutting and demolition activities are performed, which results in a frequent change in the structure and produce many irregular objects. In order to assess dose rates during the cutting and demolition process, a flexible dose assessment method for arbitrary geometries and radiation sources was proposed based on virtual reality technology and Point-Kernel method. The initial geometry is designed with the three-dimensional computer-aided design tools. An approximate model is built automatically in the process of geometric modeling via three procedures namely: space division, rough modeling of the body and fine modeling of the surface, all in combination with collision detection of virtual reality technology. Then point kernels are generated by sampling within the approximate model, and when the material and radiometric attributes are inputted, dose rates can be calculated with the Point-Kernel method. To account for radiation scattering effects, buildup factors are calculated with the Geometric-Progression formula in the fitting function. The effectiveness and accuracy of the proposed method was verified by means of simulations using different geometries and the dose rate results were compared with that derived from CIDEC code, MCNP code and experimental measurements.

A professional development model for medical laboratory scientists working in the microbiology laboratory.

PubMed

Amerson, Megan H; Pulido, Lila; Garza, Melinda N; Ali, Faheem A; Greenhill, Brandy; Einspahr, Christopher L; Yarsa, Joseph; Sood, Pramilla K; Hu, Peter C

2012-01-01

The University of Texas M.D. Anderson Cancer Center, Division of Pathology and Laboratory Medicine is committed to providing the best pathology and medicine through: state-of-the art techniques, progressive ground-breaking research, education and training for the clinical diagnosis and research of cancer and related diseases. After surveying the laboratory staff and other hospital professionals, the Department administrators and Human Resource generalists developed a professional development model for Microbiology to support laboratory skills, behavior, certification, and continual education within its staff. This model sets high standards for the laboratory professionals to allow the labs to work at their fullest potential; it provides organization to training technologists based on complete laboratory needs instead of training technologists in individual areas in which more training is required if the laboratory needs them to work in other areas. This model is a working example for all microbiology based laboratories who want to set high standards and want their staff to be acknowledged for demonstrated excellence and professional development in the laboratory. The PDM model is designed to focus on the needs of the laboratory as well as the laboratory professionals.

[Study of quality of a branch laboratory--an opinion of a laboratory manager].

PubMed

Yazawa, Naoyuki

2006-11-01

At the stage of establishing a branch laboratory, quality evaluation is extremely difficult. Even the results of a control survey by the headquarters of the branch laboratory are unhelpful. For a clinical laboratory, the most important function is to provide reliable data all the time, and to maintain the reliability of clinical doctors with informed responses. We mostly refer to control surveys and daily quality control data to evaluate a clinical laboratory, but we rarely check its fundamental abilities, such as planning events, preserving statistical data about the standard range, using the right method for quality control and others. This is generally disregarded and it is taken for granted that they will be correct the first time. From my six years of experience working with X's branch laboratory, I realized that there might be some relation between the quality of a branch laboratory and the fundamental abilities of the company itself. I would never argue that all branch laboratories are ineffective, but they should be conscious of fundamental activities. The referring laboratory, not the referral laboratory, should be responsible for ensuring that the referral laboratory's examination results and findings are correct.

The assessment of ionising radiation impact on the cooling pond freshwater ecosystem non-human biota from the Ignalina NPP operation beginning to shut down and initial decommissioning.

PubMed

Mazeika, J; Marciulioniene, D; Nedveckaite, T; Jefanova, O

2016-01-01

The radiological doses to non-human biota of freshwater ecosystem in the Ignalina NPP cooling pond - Lake Druksiai were evaluated for several cases including the plant's operation period and initial decommissioning activities, using the ERICA 1.2 code with IAEA SRS-19 models integrated approach and tool. Among the Lake Druksiai freshwater ecosystem reference organisms investigated the highest exposure dose rate was determined for bottom fauna - benthic organisms (mollusc-bivalves, crustaceans, mollusc-gastropods, insect larvae), and among the other reference organisms - for vascular plants. The mean and maximum total dose rate values due to anthropogenic radionuclide ionising radiation impact in all investigated cases were lower than the ERICA screening dose rate value of 10 μGy/h. The main exposure of reference organisms as a result of Ignalina NPP former effluent to Lake Druksiai is due to ionizing radiation of radionuclides (60)Co and (137)Cs, of predicted releases to Lake Druksiai during initial decommissioning period - due to radionuclides (60)Co, (134)Cs and (137)Cs, and as a result of predicted releases to Lake Druksiai from low- and intermediate-level short-lived radioactive waste disposal site in 30-100 year period - due to radionuclides (99)Tc and (3)H. The risk quotient expected values in all investigated cases were <1, and therefore the risk to non-human biota can be considered negligible with the exception of a conservative risk quotient for insect larvae. Radiological protection of non-human biota in Lake Druksiai, the Ignalina NPP cooling pond, is both feasible and acceptable. Copyright © 2015 Elsevier Ltd. All rights reserved.

Teaching Laboratory Renovation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Al-Zuhairi, Ali Jassim; Al-Dahhan, Wedad; Hussein, Falah

Scientists at universities across Iraq are actively working to report actual incidents and accidents occurring in their laboratories, as well as structural improvements made to improve safety and security, to raise awareness and encourage openness, leading to widespread adoption of robust Chemical Safety and Security (CSS) practices. The improvement of students’ understanding of concepts in science and its applications, practical scientific skills and understanding of how science and scientists work in laboratory experiences have been considered key aspects of education in science for over 100 years. Facility requirements for the necessary level of safety and security combined with specific requirementsmore » relevant to the course to be conducted dictate the structural design of a particular laboratory, and the design process must address both. This manuscript is the second in a series of five case studies describing laboratory incidents, accidents, and laboratory improvements. We summarize the process used to guide a major renovation of the chemistry instructional laboratory facilities at Al-Nahrain University and discuss lessons learned from the project.« less

The Integration of the 241-Z Building Decontamination and Decommissioning Under Cercla with RCRA Closure at the Plutonium Finishing Plant

DOE Office of Scientific and Technical Information (OSTI.GOV)

Mattlin, E.; Charboneau, S.; Johnston, G.

2007-07-01

The 241-Z treatment and storage tanks, a hazardous waste Treatment, Storage and Disposal (TSD) unit permitted pursuant to the Resource Conservation and Recovery Act of 1976 (RCRA) and Washington State Hazardous Waste Management Act, RCW 70.105, , have been deactivated and are being actively decommissioned under the provisions of the Hanford Federal Facility Agreement and Consent Order (HFFACO), RCRA and Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) 42 U.S.C. 9601 et seq. The 241-Z TSD unit managed non-listed radioactive contaminated waste water, containing trace RCRA characteristic constituents. The 241-Z TSD unit consists of below grade tanks (D-4,more » D-5, D-7, D-8, and an overflow tank) located in a concrete containment vault, sample glovebox GB-2-241-ZA, and associated ancillary piping and equipment. The tank system is located beneath the 241-Z building. The 241-Z building is not a portion of the TSD unit. The sample glovebox is housed in the above-grade building. Waste managed at the TSD unit was received via underground piping from Plutonium Finishing Plant (PFP) sources. Tank D-6, located in the D-6 vault cell, is a past-practice tank that was taken out of service in 1972 and has never operated as a portion of the RCRA TSD unit. CERCLA actions will address Tank D-6, its containment vault cell, and soil beneath the cell that was potentially contaminated during past-practice operations and any other potential past-practice contamination identified during 241-Z closure, while outside the scope of the Hanford Facility Dangerous Waste Closure Plan, 241-Z Treatment and Storage Tanks. Under the RCRA closure plan, the 241-Z TSD unit is anticipated to undergo clean closure to the performance standards of the State of Washington with respect to dangerous waste contamination from RCRA operations. The TSD unit will be clean closed if physical closure activities identified in the plan achieve clean closure standards for all

Decommissioning of German Research Reactors Under the Governance of the Federal Ministry of Education and Research - 12154

DOE Office of Scientific and Technical Information (OSTI.GOV)

Weigl, M.

2012-07-01

Since 1956, nuclear research and development (R and D) in Germany has been supported by the Federal Government. The goal was to help German industry to become competitive in all fields of nuclear technology. National research centers were established and demonstration plants were built. In the meantime, all these facilities were shut down and are now in a state of decommissioning and dismantling (D and D). Meanwhile, Germany is one of the leading countries in the world in the field of D and D. Two big demonstration plants, the Niederaichbach Nuclear Power Plant (KKN) a heavy-water cooled pressure tube reactormore » with carbon-dioxide cooling and the Karlstein Superheated Steam Reactor (HDR) a boiling light water reactor with a thermal power of 100 MW, are totally dismantled and 'green field' is reached. Another big project was finished in 2008. The Forschungs-Reaktor Juelich 1 (FRJ1), a research reactor with a thermal power of 10 MW was completely dismantled and in September 2008 an oak tree was planted on a green field at the site, where the FRJ1 was standing before. This is another example for German success in the field of D and D. Within these projects a lot of new solutions and innovative techniques were tested, which were developed at German universities and in small and medium sized companies mostly funded by the Federal Ministry of Education and Research (BMBF). Some examples are underwater-cutting technologies like plasma arc cutting and contact arc metal cutting. This clearly shows that research on the field of D and D is important for the future. Moreover, these research activities are important to save the know-how in nuclear engineering in Germany and will enable enterprises to compete on the increasing market of D and D services. The author assumes that an efficient decommissioning of nuclear installations will help stabilize the credibility of nuclear energy. Some critics of nuclear energy are insisting that a return to 'green field sites' is not

Implementing a laboratory automation system: experience of a large clinical laboratory.

PubMed

Lam, Choong Weng; Jacob, Edward

2012-02-01

Laboratories today face increasing pressure to automate their operations as they are challenged by a continuing increase in workload, need to reduce expenditure, and difficulties in recruitment of experienced technical staff. Was the implementation of a laboratory automation system (LAS) in the Clinical Biochemistry Laboratory at Singapore General Hospital successful? There is no simple answer, so the following topics comparing and contrasting pre- and post-LAS have been explored: turnaround time (TAT), laboratory errors, and staff satisfaction. The benefits and limitations of LAS from the laboratory experience were also reviewed. The mean TAT for both stat and routine samples decreased post-LAS (30% and 13.4%, respectively). In the 90th percentile TAT chart, a 29% reduction was seen in the processing of stat samples on the LAS. However, no significant difference in the 90th percentile TAT was observed with routine samples. It was surprising to note that laboratory errors increased post-LAS. Considerable effort was needed to overcome the initial difficulties associated with adjusting to a new system, new software, and new working procedures. Although some of the known advantages and limitations of LAS have been validated, the claimed benefits such as improvements in TAT, laboratory errors, and staff morale were not evident in the initial months.

Characterization of the colorectal cancer-associated enhancer MYC-335 at 8q24: the role of rs67491583.

PubMed

Tuupanen, Sari; Yan, Jian; Turunen, Mikko; Gylfe, Alexandra E; Kaasinen, Eevi; Li, Li; Eng, Charis; Culver, Daniel A; Kalady, Matthew F; Pennison, Michael J; Pasche, Boris; Manne, Upender; de la Chapelle, Albert; Hampel, Heather; Henderson, Brian E; Marchand, Loic Le; Hautaniemi, Sampsa; Askhtorab, Hassan; Smoot, Duane; Sandler, Robert S; Keku, Temitope; Kupfer, Sonia S; Ellis, Nathan A; Haiman, Christopher A; Taipale, Jussi; Aaltonen, Lauri A

2012-01-01

Recent genome-wide association studies have identified multiple regions at 8q24 that confer susceptibility to many cancers. In our previous work, we showed that the colorectal cancer (CRC) risk variant rs6983267 at 8q24 resides within a TCF4 binding site at the MYC-335 enhancer, with the risk allele G having a stronger binding capacity and Wnt responsiveness. Here, we searched for other potential functional variants within MYC-335. Genetic variation within MYC-335 was determined in samples from individuals of European, African, and Asian descent, with emphasis on variants in putative transcription factor binding sites. A 2-bp GA deletion rs67491583 was found to affect a growth factor independent (GFI) binding site and was present only in individuals with African ancestry. Chromatin immunoprecipitation performed in heterozygous cells showed that the GA deletion had an ability to reduce binding of the transcriptional repressors GFI1 and GFI1b. Screening of 1,027 African American colorectal cancer cases and 1,773 healthy controls did not reveal evidence for association (odds ratio: 1.17, 95% confidence interval: 0.97-1.41, P = 0.095). In this study, rs67491583 was identified as another functional variant in the CRC-associated enhancer MYC-335, but further studies are needed to establish the role of rs67491583 in the colorectal cancer predisposition of African Americans. Copyright © 2012 Elsevier Inc. All rights reserved.

Summary of events and geotechnical factors leading to decommissioning of the Strategic Petroleum Reserve (SPR) facility at Weeks Island, Louisiana

DOE Office of Scientific and Technical Information (OSTI.GOV)

Neal, J.T.; Bauer, S.J.; Ehgartner, B.L.

1996-10-01

A sinkhole discovered over the edge of the Strategic Petroleum Reserve storage facility at Weeks Island salt dome, Louisiana, led to decommissioning the site during 1995--1998, following extensive diagnostics in 1994. The sinkhole resulted from mine-induced fractures in the salt which took may years to develop, eventually causing fresh water to leak into the storage chamber and dissolve the overlying salt, thus causing overburden collapse into the void. Prior to initiating the oil removal, a freeze wall was constructed at depth around the sinkhole in 1995 to prevent water inflow; a freeze plug will remain in place until the minemore » is backfilled with brine in 1997--8, and stability is reached. Residual oil will be removed; environmental monitoring has been initiated and will continue until the facility is completely plugged and abandoned, and environmental surety is achieved.« less

42 CFR 414.510 - Laboratory date of service for clinical laboratory and pathology specimens.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 42 Public Health 3 2010-10-01 2010-10-01 false Laboratory date of service for clinical laboratory... AND OTHER HEALTH SERVICES Payment for New Clinical Diagnostic Laboratory Tests § 414.510 Laboratory date of service for clinical laboratory and pathology specimens. The date of service for either a...

Development of a conditioning system for the dual-purpose transport and storage cask for spent nuclear fuel from decommissioned Russian submarines

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dyer, R.S.; Barnes, E.; Snipes, R.L.

2007-07-01

Russia, stores large quantities of spent nuclear fuel (SNF) from submarine and ice-breaker nuclear powered naval vessels. This high-level radioactive material presents a significant threat to the Arctic and marine environments. Much of the SNF from decommissioned Russian nuclear submarines is stored either onboard the submarines or in floating storage vessels in Northwest and Far East Russia. Some of the SNF is damaged, stored in an unstable condition, or of a type that cannot currently be reprocessed. In many cases, the existing Russian transport infrastructure and reprocessing facilities cannot meet the requirements for moving and reprocessing all of this fuelmore » from remote locations. Additional transport and storage options are required. Some of the existing storage facilities being used in Russia do not meet health and safety and physical security requirements. The U.S. has assisted Russia in the development of a new dual-purpose metal-concrete transport and storage cask (TUK-108/1) for their military SNF and assisted them in building several new facilities for off-loading submarine SNF and storing these TUK-108/1 casks. These efforts have reduced the technical, ecological, and security challenges for removal, handling, interim storage, and shipment of this submarine fuel. Currently, Russian licensing limits the storage period of the TUK-108/1 casks to no more than two years before the fuel must be shipped for reprocessing. In order to extend this licensed storage period, a system is required to condition the casks by removing residual water and creating an inert storage environment by backfilling the internal canisters with a noble gas such as argon. The U.S. has assisted Russia in the development of a mobile cask conditioning system for the TUK-108/1 cask. This new conditioning system allows the TUK 108/1 casks to be stored for up to five years after which the license may be considered for renewal for an additional five years or the fuel will be shipped

[Accreditation of medical laboratories].

PubMed

Horváth, Andrea Rita; Ring, Rózsa; Fehér, Miklós; Mikó, Tivadar

2003-07-27

In Hungary, the National Accreditation Body was established by government in 1995 as an independent, non-profit organization, and has exclusive rights to accredit, amongst others, medical laboratories. The National Accreditation Body has two Specialist Advisory Committees in the health care sector. One is the Health Care Specialist Advisory Committee that accredits certifying bodies, which deal with certification of hospitals. The other Specialist Advisory Committee for Medical Laboratories is directly involved in accrediting medical laboratory services of health care institutions. The Specialist Advisory Committee for Medical Laboratories is a multidisciplinary peer review group of experts from all disciplines of in vitro diagnostics, i.e. laboratory medicine, microbiology, histopathology and blood banking. At present, the only published International Standard applicable to laboratories is ISO/IEC 17025:1999. Work has been in progress on the official approval of the new ISO 15189 standard, specific to medical laboratories. Until the official approval of the International Standard ISO 15189, as accreditation standard, the Hungarian National Accreditation Body has decided to progress with accreditation by formulating explanatory notes to the ISO/IEC 17025:1999 document, using ISO/FDIS 15189:2000, the European EC4 criteria and CPA (UK) Ltd accreditation standards as guidelines. This harmonized guideline provides 'explanations' that facilitate the application of ISO/IEC 17025:1999 to medical laboratories, and can be used as a checklist for the verification of compliance during the onsite assessment of the laboratory. The harmonized guideline adapted the process model of ISO 9001:2000 to rearrange the main clauses of ISO/IEC 17025:1999. This rearrangement does not only make the guideline compliant with ISO 9001:2000 but also improves understanding for those working in medical laboratories, and facilitates the training and education of laboratory staff. With the

Safety in the Chemical Laboratory: Safety in the Chemistry Laboratories: A Specific Program.

ERIC Educational Resources Information Center

Corkern, Walter H.; Munchausen, Linda L.

1983-01-01

Describes a safety program adopted by Southeastern Louisiana University. Students are given detailed instructions on laboratory safety during the first laboratory period and a test which must be completely correct before they are allowed to return to the laboratory. Test questions, list of safety rules, and a laboratory accident report form are…

Development of an In-Situ Decommissioning Sensor Network Test Bed for Structural Condition Monitoring - 12156

DOE Office of Scientific and Technical Information (OSTI.GOV)

Zeigler, Kristine E.; Ferguson, Blythe A.

2012-07-01

The Savannah River National Laboratory (SRNL) has established an In Situ Decommissioning (ISD) Sensor Network Test Bed, a unique, small scale, configurable environment, for the assessment of prospective sensors on actual ISD system material, at minimal cost. The Department of Energy (DOE) is presently implementing permanent entombment of contaminated, large nuclear structures via ISD. The ISD end state consists of a grout-filled concrete civil structure within the concrete frame of the original building. Validation of ISD system performance models and verification of actual system conditions can be achieved through the development a system of sensors to monitor the materials andmore » condition of the structure. The ISD Sensor Network Test Bed has been designed and deployed to addresses the DOE-Environmental Management Technology Need to develop a remote monitoring system to determine and verify ISD system performance. Commercial off-the-shelf sensors have been installed on concrete blocks taken from walls of the P Reactor Building at the Savannah River Site. Deployment of this low-cost structural monitoring system provides hands-on experience with sensor networks. The initial sensor system consists of groutable thermistors for temperature and moisture monitoring, strain gauges for crack growth monitoring, tilt-meters for settlement monitoring, and a communication system for data collection. Baseline data and lessons learned from system design and installation and initial field testing will be utilized for future ISD sensor network development and deployment. The Sensor Network Test Bed at SRNL uses COTS sensors on concrete blocks from the outer wall of the P Reactor Building to measure conditions expected to occur in ISD structures. Knowledge and lessons learned gained from installation, testing, and monitoring of the equipment will be applied to sensor installation in a meso-scale test bed at FIU and in future ISD structures. The initial data collected from the

42 CFR 493.1441 - Condition: Laboratories performing high complexity testing; laboratory director.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 42 Public Health 5 2011-10-01 2011-10-01 false Condition: Laboratories performing high complexity testing; laboratory director. 493.1441 Section 493.1441 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY...

42 CFR 493.1441 - Condition: Laboratories performing high complexity testing; laboratory director.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 42 Public Health 5 2010-10-01 2010-10-01 false Condition: Laboratories performing high complexity testing; laboratory director. 493.1441 Section 493.1441 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY...

Site Environmental Report for Calendar Year 2009. DOE Operations at The Boeing Company Santa Susana Field Laboratory, Area IV

DOE Office of Scientific and Technical Information (OSTI.GOV)

Liu, Ning; Rutherford, Phil; Amar, Ravnesh

2010-09-01

This Annual Site Environmental Report (ASER) for 2009 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988, andmore » all subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2009 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less

Site Environmental Report for Calendar Year 2011. DOE Operations at The Boeing Company Santa Susana Field Laboratory, Area IV

DOE Office of Scientific and Technical Information (OSTI.GOV)

Liu, Ning; Rutherford, Phil; Dassler, David

2012-09-01

This Annual Site Environmental Report (ASER) for 2011 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, operation and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988,more » and all subsequent radiological work has been directed toward environmental restoration and decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2011 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less

Site Environmental Report for Calendar Year 2010. DOE Operations at The Boeing Company Santa Susana Field Laboratory, Area IV

DOE Office of Scientific and Technical Information (OSTI.GOV)

Liu, Ning; Rutherford, Phil; Amar, Ravnesh

2011-09-01

This Annual Site Environmental Report (ASER) for 2010 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988, andmore » all subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2010 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less

Site Environmental Report For Calendar Year 2012. DOE Operations at The Boeing Company Santa Susana Field Laboratory, Area IV

DOE Office of Scientific and Technical Information (OSTI.GOV)

Liu, Ning; Rutherford, Phil; Dassler, David

2013-09-01

This Annual Site Environmental Report (ASER) for 2012 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, operation and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988,more » and all subsequent radiological work has been directed toward environmental restoration and decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2012 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.« less

Laboratory safety handbook

USGS Publications Warehouse

Skinner, E.L.; Watterson, C.A.; Chemerys, J.C.

1983-01-01

Safety, defined as 'freedom from danger, risk, or injury,' is difficult to achieve in a laboratory environment. Inherent dangers, associated with water analysis and research laboratories where hazardous samples, materials, and equipment are used, must be minimized to protect workers, buildings, and equipment. Managers, supervisors, analysts, and laboratory support personnel each have specific responsibilities to reduce hazards by maintaining a safe work environment. General rules of conduct and safety practices that involve personal protection, laboratory practices, chemical handling, compressed gases handling, use of equipment, and overall security must be practiced by everyone at all levels. Routine and extensive inspections of all laboratories must be made regularly by qualified people. Personnel should be trained thoroughly and repetitively. Special hazards that may involve exposure to carcinogens, cryogenics, or radiation must be given special attention, and specific rules and operational procedures must be established to deal with them. Safety data, reference materials, and texts must be kept available if prudent safety is to be practiced and accidents prevented or minimized.

National survey on intra-laboratory turnaround time for some most common routine and stat laboratory analyses in 479 laboratories in China.

PubMed

Fei, Yang; Zeng, Rong; Wang, Wei; He, Falin; Zhong, Kun; Wang, Zhiguo

2015-01-01

To investigate the state of the art of intra-laboratory turnaround time (intra-TAT), provide suggestions and find out whether laboratories accredited by International Organization for Standardization (ISO) 15189 or College of American Pathologists (CAP) will show better performance on intra-TAT than non-accredited ones. 479 Chinese clinical laboratories participating in the external quality assessment programs of chemistry, blood gas, and haematology tests organized by the National Centre for Clinical Laboratories in China were included in our study. General information and the median of intra-TAT of routine and stat tests in last one week were asked in the questionnaires. The response rate of clinical biochemistry, blood gas, and haematology testing were 36% (479/1307), 38% (228/598), and 36% (449/1250), respectively. More than 50% of laboratories indicated that they had set up intra-TAT median goals and almost 60% of laboratories declared they had monitored intra-TAT generally for every analyte they performed. Among all analytes we investigated, the intra-TAT of haematology analytes was shorter than biochemistry while the intra-TAT of blood gas analytes was the shortest. There were significant differences between median intra-TAT on different days of the week for routine tests. However, there were no significant differences in median intra-TAT reported by accredited laboratories and non-accredited laboratories. Many laboratories in China are aware of intra-TAT control and are making effort to reach the target. There is still space for improvement. Accredited laboratories have better status on intra-TAT monitoring and target setting than the non-accredited, but there are no significant differences in median intra-TAT reported by them.

National survey on intra-laboratory turnaround time for some most common routine and stat laboratory analyses in 479 laboratories in China

PubMed Central

Fei, Yang; Zeng, Rong; Wang, Wei; He, Falin; Zhong, Kun

2015-01-01

Introduction To investigate the state of the art of intra-laboratory turnaround time (intra-TAT), provide suggestions and find out whether laboratories accredited by International Organization for Standardization (ISO) 15189 or College of American Pathologists (CAP) will show better performance on intra-TAT than non-accredited ones. Materials and methods 479 Chinese clinical laboratories participating in the external quality assessment programs of chemistry, blood gas, and haematology tests organized by the National Centre for Clinical Laboratories in China were included in our study. General information and the median of intra-TAT of routine and stat tests in last one week were asked in the questionnaires. Results The response rate of clinical biochemistry, blood gas, and haematology testing were 36% (479 / 1307), 38% (228 / 598), and 36% (449 / 1250), respectively. More than 50% of laboratories indicated that they had set up intra-TAT median goals and almost 60% of laboratories declared they had monitored intra-TAT generally for every analyte they performed. Among all analytes we investigated, the intra-TAT of haematology analytes was shorter than biochemistry while the intra-TAT of blood gas analytes was the shortest. There were significant differences between median intra-TAT on different days of the week for routine tests. However, there were no significant differences in median intra-TAT reported by accredited laboratories and non-accredited laboratories. Conclusions Many laboratories in China are aware of intra-TAT control and are making effort to reach the target. There is still space for improvement. Accredited laboratories have better status on intra-TAT monitoring and target setting than the non-accredited, but there are no significant differences in median intra-TAT reported by them. PMID:26110033

78 FR 55727 - Draft Guidance for Industry on Recommendations for Preparation and Submission of Animal Food...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-09-11

...] Draft Guidance for Industry on Recommendations for Preparation and Submission of Animal Food Additive...) entitled ``Recommendations for Preparation and Submission of Animal Food Additive Petitions.'' This draft... guidance for industry (GFI 221) entitled ``Recommendations for Preparation and Submission of Animal Food...

The Laboratory for Terrestrial Physics

NASA Technical Reports Server (NTRS)

2003-01-01

The Laboratory for Terrestrial Physics is dedicated to the advancement of knowledge in Earth and planetary science, by conducting innovative research using space technology. The Laboratory's mission and activities support the work and new initiatives at NASA's Goddard Space Flight Center (GSFC). The Laboratory's success contributes to the Earth Science Directorate as a national resource for studies of Earth from Space. The Laboratory is part of the Earth Science Directorate based at the GSFC in Greenbelt, MD. The Directorate itself is comprised of the Global Change Data Center (GCDC), the Space Data and Computing Division (SDCD), and four science Laboratories, including Laboratory for Terrestrial Physics, Laboratory for Atmospheres, and Laboratory for Hydrospheric Processes all in Greenbelt, MD. The fourth research organization, Goddard Institute for Space Studies (GISS), is in New York, NY. Relevant to NASA's Strategic Plan, the Laboratory ensures that all work undertaken and completed is within the vision of GSFC. The philosophy of the Laboratory is to balance the completion of near term goals, while building on the Laboratory's achievements as a foundation for the scientific challenges in the future.

A professional development model for medical laboratory scientists working in the immunohematology laboratory.

PubMed

Garza, Melinda N; Pulido, Lila A; Amerson, Megan; Ali, Faheem A; Greenhill, Brandy A; Griffin, Gary; Alvarez, Enrique; Whatley, Marsha; Hu, Peter C

2012-01-01

Transfusion medicine, a section of the Department of Laboratory Medicine at The University of Texas MD Anderson Cancer Center is committed to the education and advancement of its health care professionals. It is our belief that giving medical laboratory professionals a path for advancement leads to excellence and increases overall professionalism in the Immunohematology Laboratory. As a result of this strong commitment to excellence and professionalism, the Immunohematology laboratory has instituted a Professional Development Model (PDM) that aims to create Medical Laboratory Scientists (MLS) that are not only more knowledgeable, but are continually striving for excellence. In addition, these MLS are poised for advancement in their careers. The professional development model consists of four levels: Discovery, Application, Maturation, and Expert. The model was formulated to serve as a detailed path to the mastery of all process and methods in the Immunohematology Laboratory. Each level in the professional development model consists of tasks that optimize the laboratory workflow and allow for concurrent training. Completion of a level in the PDM is rewarded with financial incentive and further advancement in the field. The PDM for Medical Laboratory Scientists in the Immunohematology Laboratory fosters personal development, rewards growth and competency, and sets high standards for all services and skills provided. This model is a vital component of the Immunohematology Laboratory and aims to ensure the highest quality of care and standards in their testing. It is because of the success of this model and the robustness of its content that we hope other medical laboratories aim to reach the same level of excellence and professionalism, and adapt this model into their own environment.

Laboratory performance in the Sediment Laboratory Quality-Assurance Project, 1996-98

USGS Publications Warehouse

Gordon, John D.; Newland, Carla A.; Gagliardi, Shane T.

2000-01-01

Analytical results from all sediment quality-control samples are compiled and statistically summarized by the USGS, Branch of Quality Systems, both on an intra- and interlaboratory basis. When evaluating these data, the reader needs to keep in mind that every measurement has an error component associated with it. It is premature to use the data from the first five SLQA studies to judge any of the laboratories as performing in an unacceptable manner. There were, however, some notable differences in the results for the 12 laboratories that participated in the five SLQA studies. For example, the overall median percent difference for suspended-sediment concentration on an individual laboratory basis ranged from –18.04 to –0.33 percent. Five of the 12 laboratories had an overall median percent difference for suspended-sediment concentration of –2.02 to –0.33 percent. There was less variability in the median difference for the measured fine-size material mass. The overall median percent difference for fine-size material mass ranged from –10.11 to –4.27 percent. Except for one laboratory, the median difference for fine-size material mass was within a fairly narrow range of –6.76 to –4.27 percent. The median percent difference for sand-size material mass differed among laboratories more than any other physical sediment property measured in the study. The overall median percent difference for the sand-size material mass ranged from –1.49 percent to 26.39 percent. Five of the nine laboratories that do sand/fine separations had overall median percent differences that ranged from –1.49 to 2.98 percent for sand-size material mass. Careful review of the data reveals that certain laboratories consistently produced data within statistical control limits for some or all of the physical sediment properties measured in this study, whereas other laboratories occasionally produced data that exceeded the control limits.

Horizontal and vertical integration in hospital laboratories and the laboratory information system.

PubMed

Friedman, B A; Mitchell, W

1990-09-01

An understanding of horizontal and vertical integration and their quasi-integration variants is important for pathologists to formulate a competitive strategy for hospital clinical laboratories. These basic organizational concepts, in turn, are based on the need to establish control over critical laboratory inputs and outputs. The pathologist seeks greater control of mission-critical system inputs and outputs to increase the quality and efficiency of the laboratory operations. The LIS produces horizontal integration of the various hospital laboratories by integrating them vertically. Forward vertical quasi-integration of the laboratories is mediated primarily by the LIS through front-end valued-added features such as reporting of results and creating a long-term on-line test result archive. These features increase the value of the information product of pathology for clinicians and increase the cost of switching to another system. The LIS can also serve as a means for customizing the information product of the laboratories to appeal to new market segments such as hospital administrators.

Laboratory medicine education in Lithuania.

PubMed

Kucinskiene, Zita Ausrele; Bartlingas, Jonas

2011-01-01

In Lithuania there are two types of specialists working in medical laboratories and having a university degree: laboratory medicine physicians and medical biologists. Both types of specialists are officially being recognized and regulated by the Ministry of Health of Lithuania. Laboratory medicine physicians become specialists in laboratory medicine after an accredited 4-year multidisciplinary residency study program in Laboratory Medicine. The residency program curriculum for laboratory medicine physicians is presented. On December 9, 2009 the Equivalence of Standards for medical specialists was accepted and Lithuanian medical specialists in Clinical Chemistry and Laboratory Medicine can now apply for EC4 registration. Medical biologists become specialists in laboratory medicine after an accredited 2-year master degree multidisciplinary study program in Medical Biology, consisting of 80 credits. Various postgraduate advanced training courses for the continuous education of specialists in laboratory medicine were first introduced in 1966. Today it covers 1-2-week courses in different subspecialties of laboratory medicine. They are obligatory for laboratory medicine physicians for the renewal of their license. It is not compulsory for medical biologists to participate in these courses. The Centre of Laboratory Diagnostics represents a place for the synthesis and application of the basic sciences, the performance of research in various fields of laboratory medicine, as well as performance of thousands of procedures daily and provision of specific teaching programs.

Investigating Student Perceptions of the Chemistry Laboratory and Their Approaches to Learning in the Laboratory

NASA Astrophysics Data System (ADS)

Berger, Spencer Granett

This dissertation explores student perceptions of the instructional chemistry laboratory and the approaches students take when learning in the laboratory environment. To measure student perceptions of the chemistry laboratory, a survey instrument was developed. 413 students responded to the survey during the Fall 2011 semester. Students' perception of the usefulness of the laboratory in helping them learn chemistry in high school was related to several factors regarding their experiences in high school chemistry. Students' perception of the usefulness of the laboratory in helping them learn chemistry in college was also measured. Reasons students provided for the usefulness of the laboratory were categorized. To characterize approaches to learning in the laboratory, students were interviewed midway through semester (N=18). The interviews were used to create a framework describing learning approaches that students use in the laboratory environment. Students were categorized into three levels: students who view the laboratory as a requirement, students who believe that the laboratory augments their understanding, and students who view the laboratory as an important part of science. These categories describe the types of strategies students used when conducting experiments. To further explore the relationship between students' perception of the laboratory and their approaches to learning, two case studies are described. These case studies involve interviews in the beginning and end of the semester. In the interviews, students reflect on what they have learned in the laboratory and describe their perceptions of the laboratory environment. In order to encourage students to adopt higher-level approaches to learning in the laboratory, a metacognitive intervention was created. The intervention involved supplementary questions that students would answer while completing laboratory experiments. The questions were designed to encourage students to think critically about the

Phillips Laboratory Geophysics Scholar Program

DTIC Science & Technology

1993-09-30

research at Phillips Laboratory . Research sponsored by Air Force Geophysics Laboratory ...Geophysics Laboratory (now the Phillips Laboratory , Geophysics Directorate), United States Air Force for its sponsorship of this research through the Air ...September 1993 Approved for public release; distribution unlimited PHILLIPS LABORATORY Directorate of Geophysics AIR FORCE MATERIEL COMMAND

[How do hospital clinical laboratories and laboratory testing companies cooperate and build reciprocal relations?].

PubMed

Kawano, Seiji

2014-12-01

As the 2nd Joint Symposium of the Japanese Society of Laboratory Medicine and the Japanese Association of Laboratory Pathologists, the symposium on clinical test out-sourcing and branch laboratories was held at the 60th General Meeting of the Japanese Society of Laboratory Medicine on November 2nd, 2013 in Kobe. For the symposium, we conducted a questionnaire survey on the usage of clinical test out-sourcing and the introduction of branch laboratories to clinical laboratories of Japanese university hospitals, both private and public, between July 25th and August 20th, 2013. Seventy-two hospitals responded to the questionnaire survey, consisting of 41 public medical school hospitals and 31 private ones. According to the survey, the selection of each clinical test for out-sourcing was mainly determined by the capacities of hospital clinical laboratories and their equipment, as well as the profitability of each test. The main concerns of clinical laboratory members of university hospitals involved the continuity of measurement principles, traceability, and standardization of reference values for each test. They strongly requested the interchangeability and computerization of test data between laboratory testing companies. A branch laboratory was introduced to six hospitals, all of which were private medical college hospitals, out of 72 university hospitals, and eight of the other hospitals were open to its introduction. The merits and demerits of introducing a branch laboratory were also discussed. (Review).

Geoelectrical monitoring of simulated subsurface leakage to support high-hazard nuclear decommissioning at the Sellafield Site, UK.

PubMed

Kuras, Oliver; Wilkinson, Paul B; Meldrum, Philip I; Oxby, Lucy S; Uhlemann, Sebastian; Chambers, Jonathan E; Binley, Andrew; Graham, James; Smith, Nicholas T; Atherton, Nick

2016-10-01

A full-scale field experiment applying 4D (3D time-lapse) cross-borehole Electrical Resistivity Tomography (ERT) to the monitoring of simulated subsurface leakage was undertaken at a legacy nuclear waste silo at the Sellafield Site, UK. The experiment constituted the first application of geoelectrical monitoring in support of decommissioning work at a UK nuclear licensed site. Images of resistivity changes occurring since a baseline date prior to the simulated leaks revealed likely preferential pathways of silo liquor simulant flow in the vadose zone and upper groundwater system. Geophysical evidence was found to be compatible with historic contamination detected in permeable facies in sediment cores retrieved from the ERT boreholes. Results indicate that laterally discontinuous till units forming localized hydraulic barriers substantially affect flow patterns and contaminant transport in the shallow subsurface at Sellafield. We conclude that only geophysical imaging of the kind presented here has the potential to provide the detailed spatial and temporal information at the (sub-)meter scale needed to reduce the uncertainty in models of subsurface processes at nuclear sites. Copyright © 2016 British Geological Survey, NERC. Published by Elsevier B.V. All rights reserved.

Final report of the decontamination and decommission of Building 31 at the Grand Junction Projects Office Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Krabacher, J.E.

1996-07-01

The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the domestic uranium procurement program funded by the U.S. Atomic Energy Commission. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also was the remedial actionmore » contractor. Radiological contamination was identified in Building 31 and the building was demolished in 1992. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This area was addressed in the summary final report of the remediation of the exterior areas of the GJPO facility. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building.« less

Laboratory and software applications for clinical trials: the global laboratory environment.

PubMed

Briscoe, Chad

2011-11-01

The Applied Pharmaceutical Software Meeting is held annually. It is sponsored by The Boston Society, a not-for-profit organization that coordinates a series of meetings within the global pharmaceutical industry. The meeting generally focuses on laboratory applications, but in recent years has expanded to include some software applications for clinical trials. The 2011 meeting emphasized the global laboratory environment. Global clinical trials generate massive amounts of data in many locations that must be centralized and processed for efficient analysis. Thus, the meeting had a strong focus on establishing networks and systems for dealing with the computer infrastructure to support such environments. In addition to the globally installed laboratory information management system, electronic laboratory notebook and other traditional laboratory applications, cloud computing is quickly becoming the answer to provide efficient, inexpensive options for managing the large volumes of data and computing power, and thus it served as a central theme for the meeting.

Laboratory Astrophysics White Paper

NASA Technical Reports Server (NTRS)

Brickhouse, Nancy; Federman, Steve; Kwong, Victor; Salama, Farid; Savin, Daniel; Stancil, Phillip; Weingartner, Joe; Ziurys, Lucy

2006-01-01

Laboratory astrophysics and complementary theoretical calculations are the foundations of astronomical and planetary research and will remain so for many generations to come. From the level of scientific conception to that of the scientific return, it is our understanding of the underlying processes that allows us to address fundamental questions regarding the origins and evolution of galaxies, stars, planetary systems, and life in the cosmos. In this regard, laboratory astrophysics is much like detector and instrument development at NASA and NSF; these efforts are necessary for the astronomical research being funded by the agencies. The NASA Laboratory Astrophysics Workshop met at the University of Nevada, Las Vegas (UNLV) from 14-16 February, 2006 to identify the current laboratory data needed to support existing and future NASA missions and programs in the Astrophysics Division of the Science Mission Directorate (SMD). Here we refer to both laboratory and theoretical work as laboratory astrophysics unless a distinction is necessary. The format for the Workshop involved invited talks by users of laboratory data, shorter contributed talks and poster presentations by both users and providers that highlighted exciting developments in laboratory astrophysics, and breakout sessions where users and providers discussed each others' needs and limitations. We also note that the members of the Scientific Organizing Committee are users as well as providers of laboratory data. As in previous workshops, the focus was on atomic, molecular, and solid state physics.

The Virtual Robotics Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kress, R.L.; Love, L.J.

The growth of the Internet has provided a unique opportunity to expand research collaborations between industry, universities, and the national laboratories. The Virtual Robotics Laboratory (VRL) is an innovative program at Oak Ridge National Laboratory (ORNL) that is focusing on the issues related to collaborative research through controlled access of laboratory equipment using the World Wide Web. The VRL will provide different levels of access to selected ORNL laboratory secondary education programs. In the past, the ORNL Robotics and Process Systems Division has developed state-of-the-art robotic systems for the Army, NASA, Department of Energy, Department of Defense, as well asmore » many other clients. After proof of concept, many of these systems sit dormant in the laboratories. This is not out of completion of all possible research topics. but from completion of contracts and generation of new programs. In the past, a number of visiting professors have used this equipment for their own research. However, this requires that the professor, and possibly his/her students, spend extended periods at the laboratory facility. In addition, only a very exclusive group of faculty can gain access to the laboratory and hardware. The VRL is a tool that enables extended collaborative efforts without regard to geographic limitations.« less

Virtual reality based adaptive dose assessment method for arbitrary geometries in nuclear facility decommissioning.

PubMed

Liu, Yong-Kuo; Chao, Nan; Xia, Hong; Peng, Min-Jun; Ayodeji, Abiodun

2018-05-17

This paper presents an improved and efficient virtual reality-based adaptive dose assessment method (VRBAM) applicable to the cutting and dismantling tasks in nuclear facility decommissioning. The method combines the modeling strength of virtual reality with the flexibility of adaptive technology. The initial geometry is designed with the three-dimensional computer-aided design tools, and a hybrid model composed of cuboids and a point-cloud is generated automatically according to the virtual model of the object. In order to improve the efficiency of dose calculation while retaining accuracy, the hybrid model is converted to a weighted point-cloud model, and the point kernels are generated by adaptively simplifying the weighted point-cloud model according to the detector position, an approach that is suitable for arbitrary geometries. The dose rates are calculated with the Point-Kernel method. To account for radiation scattering effects, buildup factors are calculated with the Geometric-Progression formula in the fitting function. The geometric modeling capability of VRBAM was verified by simulating basic geometries, which included a convex surface, a concave surface, a flat surface and their combination. The simulation results show that the VRBAM is more flexible and superior to other approaches in modeling complex geometries. In this paper, the computation time and dose rate results obtained from the proposed method were also compared with those obtained using the MCNP code and an earlier virtual reality-based method (VRBM) developed by the same authors. © 2018 IOP Publishing Ltd.

42 CFR 414.510 - Laboratory date of service for clinical laboratory and pathology specimens.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 42 Public Health 3 2011-10-01 2011-10-01 false Laboratory date of service for clinical laboratory and pathology specimens. 414.510 Section 414.510 Public Health CENTERS FOR MEDICARE & MEDICAID... AND OTHER HEALTH SERVICES Payment for New Clinical Diagnostic Laboratory Tests § 414.510 Laboratory...

Transition of occupational health issues associated with stabilization and decommissioning of the nuclear reactors in the Fukushima Daiichi Nuclear Power Plant through 2013.

PubMed

Mori, Koji; Tateishi, Seiichiro; Kubo, Tatsuhiko; Okazaki, Ryuji; Suzuki, Katsunori; Kobayashi, Yuichi; Hiraoka, Koh; Hayashi, Takeshi; Takeda, Masaru; Kiyomoto, Yoshifumi; Kawashita, Futoshi; Yoshikawa, Toru; Sakai, Kazuhiro

2014-11-01

To clarify the occupational health (OH) issues that arose, what actions were taken, and the OH performances during the disaster involving the Fukushima Daiichi Nuclear Power Plant and thus improve the OH management system with respect to long-term decommissioning work and preparation for future disasters. We used information in advisory reports to the Tokyo Electric Power Company by an OH expert group, observation through support activities, and data officially released by the Tokyo Electric Power Company. Occupational health issues transitioned as work progressed and seasons changed. They were categorized into OH management system establishment, radiation exposure control, heat illness prevention, infectious disease prevention and control, and fitness for workers' duties. Occupational health management systems involving OH experts should be implemented to manage multiple health risks with several conflicts and trade-offs after a disaster.

The reduction of disability in community-dwelling frail older people: design of a two-arm cluster randomized controlled trial.

PubMed

Metzelthin, Silke F; van Rossum, Erik; de Witte, Luc P; Hendriks, Marike R C; Kempen, Gertrudis I J M

2010-08-23

Frailty among older people is related to an increased risk of adverse health outcomes such as acute and chronic diseases, disability and mortality. Although many intervention studies for frail older people have been reported, only a few have shown positive effects regarding disability prevention. This article presents the design of a two-arm cluster randomized controlled trial on the effectiveness, cost-effectiveness and feasibility of a primary care intervention that combines the most promising elements of disability prevention in community-dwelling frail older people. In this study twelve general practitioner practices were randomly allocated to the intervention group (6 practices) or to the control group (6 practices). Three thousand four hundred ninety-eight screening questionnaires including the Groningen Frailty Indicator (GFI) were sent out to identify frail older people. Based on their GFI score (≥5), 360 participants will be included in the study. The intervention will receive an interdisciplinary primary care intervention. After a comprehensive assessment by a practice nurse and additional assessments by other professionals, if needed, an individual action plan will be defined. The action plan is related to a flexible toolbox of interventions, which will be conducted by an interdisciplinary team. Effects of the intervention, both for the frail older people and their informal caregivers, will be measured after 6, 12 and 24 months using postal questionnaires and telephone interviews. Data for the process evaluation and economic evaluation will be gathered continuously over a 24-month period. The proposed study will provide information about the usefulness of an interdisciplinary primary care intervention. The postal screening procedure was conducted in two cycles between December 2009 and April 2010 and turned out to be a feasible method. The response rate was 79.7%. According to GFI scores 29.3% of the respondents can be considered as frail (GFI ≥ 5

POLLUTION PREVENTION OPPORTUNITY ASSESSMENT - MANUFACTURING AND FABRICATION REPAIR LABORATORY AT SANDIA NATIONAL LABORATORIES

EPA Science Inventory

These reports summarize pollution prevention opportunity assessments conducted jointly by EPA and DOE at the Geochemistry Laboratory and the Manufacturing and Fabrication Repair Laboratory at the Department of Energy's Sandia National Laboratories facility in Albuquerque, New Mex...

[Laboratory accreditation and proficiency testing].

PubMed

Kuwa, Katsuhiko

2003-05-01

ISO/TC 212 covering clinical laboratory testing and in vitro diagnostic test systems will issue the international standard for medical laboratory quality and competence requirements, ISO 15189. This standard is based on the ISO/IEC 17025, general requirements for competence of testing and calibration laboratories and ISO 9001, quality management systems-requirements. Clinical laboratory services are essential to patient care and therefore should be available to meet the needs of all patients and clinical personnel responsible for human health care. If a laboratory seeks accreditation, it should select an accreditation body that operates according to this international standard and in a manner which takes into account the particular requirements of clinical laboratories. Proficiency testing should be available to evaluate the calibration laboratories and reference measurement laboratories in clinical medicine. Reference measurement procedures should be of precise and the analytical principle of measurement applied should ensure reliability. We should be prepared to establish a quality management system and proficiency testing in clinical laboratories.

The ideal laboratory information system.

PubMed

Sepulveda, Jorge L; Young, Donald S

2013-08-01

Laboratory information systems (LIS) are critical components of the operation of clinical laboratories. However, the functionalities of LIS have lagged significantly behind the capacities of current hardware and software technologies, while the complexity of the information produced by clinical laboratories has been increasing over time and will soon undergo rapid expansion with the use of new, high-throughput and high-dimensionality laboratory tests. In the broadest sense, LIS are essential to manage the flow of information between health care providers, patients, and laboratories and should be designed to optimize not only laboratory operations but also personalized clinical care. To list suggestions for designing LIS with the goal of optimizing the operation of clinical laboratories while improving clinical care by intelligent management of laboratory information. Literature review, interviews with laboratory users, and personal experience and opinion. Laboratory information systems can improve laboratory operations and improve patient care. Specific suggestions for improving the function of LIS are listed under the following sections: (1) Information Security, (2) Test Ordering, (3) Specimen Collection, Accessioning, and Processing, (4) Analytic Phase, (5) Result Entry and Validation, (6) Result Reporting, (7) Notification Management, (8) Data Mining and Cross-sectional Reports, (9) Method Validation, (10) Quality Management, (11) Administrative and Financial Issues, and (12) Other Operational Issues.

Technical Information on the Carbonation of the EBR-II Reactor, Summary Report Part 1: Laboratory Experiments and Application to EBR-II Secondary Sodium System

DOE Office of Scientific and Technical Information (OSTI.GOV)

Steven R. Sherman

Residual sodium is defined as sodium metal that remains behind in pipes, vessels, and tanks after the bulk sodium metal has been melted and drained from such components. The residual sodium has the same chemical properties as bulk sodium, and differs from bulk sodium only in the thickness of the sodium deposit. Typically, sodium is considered residual when the thickness of the deposit is less than 5-6 cm. This residual sodium must be removed or deactivated when a pipe, vessel, system, or entire reactor is permanently taken out of service, in order to make the component or system safer and/ormore » to comply with decommissioning regulations. As an alternative to the established residual sodium deactivation techniques (steam-and-nitrogen, wet vapor nitrogen, etc.), a technique involving the use of moisture and carbon dioxide has been developed. With this technique, sodium metal is converted into sodium bicarbonate by reacting it with humid carbon dioxide. Hydrogen is emitted as a by-product. This technique was first developed in the laboratory by exposing sodium samples to humidified carbon dioxide under controlled conditions, and then demonstrated on a larger scale by treating residual sodium within the Experimental Breeder Reactor II (EBR-II) secondary cooling system, followed by the primary cooling system, respectively. The EBR-II facility is located at the Idaho National Laboratory (INL) in southeastern Idaho, U.S.A. This report is Part 1 of a two-part report. It is divided into three sections. The first section describes the chemistry of carbon dioxide-water-sodium reactions. The second section covers the laboratory experiments that were conducted in order to develop the residual sodium deactivation process. The third section discusses the application of the deactivation process to the treatment of residual sodium within the EBR-II secondary sodium cooling system. Part 2 of the report, under separate cover, describes the application of the technique to

Mice examined in Animal Laboratory of Lunar Receiving Laboratory

NASA Technical Reports Server (NTRS)

1969-01-01

Landrum Young (seated), Brown and Root-Northrup, and Russell Stullken, Manned Spacecraft Center, examine mice in the Animal laboratory of the Lunar Receiving Laboratory which have been inoculated with lunar sample material. wish for peace for all mankind. astronauts will be released from quarantine on August 11, 1969. Donald K. Slayton (right), MSC Director of Flight Crew Operations; and Lloyd Reeder, training coordinator.

Plasma creatinine in dogs: intra- and inter-laboratory variation in 10 European veterinary laboratories

PubMed Central

2011-01-01

Background There is substantial variation in reported reference intervals for canine plasma creatinine among veterinary laboratories, thereby influencing the clinical assessment of analytical results. The aims of the study was to determine the inter- and intra-laboratory variation in plasma creatinine among 10 veterinary laboratories, and to compare results from each laboratory with the upper limit of its reference interval. Methods Samples were collected from 10 healthy dogs, 10 dogs with expected intermediate plasma creatinine concentrations, and 10 dogs with azotemia. Overlap was observed for the first two groups. The 30 samples were divided into 3 batches and shipped in random order by postal delivery for plasma creatinine determination. Statistical testing was performed in accordance with ISO standard methodology. Results Inter- and intra-laboratory variation was clinically acceptable as plasma creatinine values for most samples were usually of the same magnitude. A few extreme outliers caused three laboratories to fail statistical testing for consistency. Laboratory sample means above or below the overall sample mean, did not unequivocally reflect high or low reference intervals in that laboratory. Conclusions In spite of close analytical results, further standardization among laboratories is warranted. The discrepant reference intervals seem to largely reflect different populations used in establishing the reference intervals, rather than analytical variation due to different laboratory methods. PMID:21477356

EPA Environmental Chemistry Laboratory

NASA Technical Reports Server (NTRS)

1993-01-01

The Environmental Protection Agency's (EPA) Chemistry Laboratory (ECL) is a national program laboratory specializing in residue chemistry analysis under the jurisdiction of the EPA's Office of Pesticide Programs in Washington, D.C. At Stennis Space Center, the laboratory's work supports many federal anti-pollution laws. The laboratory analyzes environmental and human samples to determine the presence and amount of agricultural chemicals and related substances. Pictured, ECL chemists analyze environmental and human samples for the presence of pesticides and other pollutants.

Procedures of Exercise Physiology Laboratories

NASA Technical Reports Server (NTRS)

Bishop, Phillip A.; Fortney, Suzanne; Greenisen, Michael; Siconolfi, Steven F.; Bamman, Marcas M.; Moore, Alan D., Jr.; Squires, William

1998-01-01

This manual describes the laboratory methods used to collect flight crew physiological performance data at the Johnson Space Center. The Exercise Countermeasures Project Laboratory is a standard physiology laboratory; only the application to the study of human physiological adaptations to spaceflight is unique. In the absence of any other recently published laboratory manual, this manual should be a useful document staffs and students of other laboratories.

Laboratory Astrophysics White Paper: Summary of Laboratory Astrophysics Needs

NASA Technical Reports Server (NTRS)

2002-01-01

The NASA Laboratory Astrophysics Workshop (NASA LAW) met at NASA Ames Research Center from 1-3 May 2002 to assess the role that laboratory astrophysics plays in the optimization of NASA missions, both at the science conception level and at the science return level. Space missions provide understanding of fundamental questions regarding the origin and evolution of galaxies, stars, and planetary systems. In all of these areas the interpretation of results from NASA's space missions relies crucially upon data obtained from the laboratory. We stress that Laboratory Astrophysics is important not only in the interpretation of data, but also in the design and planning of future missions. We recognize a symbiosis between missions to explore the universe and the underlying basic data needed to interpret the data from those missions. In the following we provide a summary of the consensus results from our Workshop, starting with general programmatic findings and followed by a list of more specific scientific areas that need attention. We stress that this is a 'living document' and that these lists are subject to change as new missions or new areas of research rise to the fore.

[ISO 15189 accreditation in clinical microbiology laboratory: general concepts and the status in our laboratory].

PubMed

Akyar, Işin

2009-10-01

One important trend in the laboratory profession and quality management is the global convergence of laboratory operations. The goal of an accredited medical laboratory is to continue "offering useful laboratory service for diagnosis and treatment of the patients and also aid to the health of the nation". An accredited clinical laboratory is managed by a quality control system, it is competent technically and the laboratory service meets the needs of all its patients and physicians by taking the responsibility of all the medical tests and therapies. For this purpose, ISO 15189 international standard has been prepared by 2003. ISO 15189 standard is originated from the arrangement of ISO 17025 and ISO 9001:2000 standards. Many countries such as England, Germany, France, Canada and Australia have preferred ISO 15189 as their own laboratory accreditation programme, meeting all the requirements of their medical laboratories. The accreditation performance of a clinical microbiology laboratory is mainly based on five essential points; preanalytical, analytical, postanalytical, quality control programmes (internal, external, interlaboratory) and audits (internal, external). In this review article, general concepts on ISO 15189 accreditation standards for the clinical microbiology laboratories have been summarized and the status of a private laboratory (Acibadem LabMed, Istanbul) in Turkey has been discussed.

Inter-Laboratory Comparison for Calibration of Relative Humidity Devices Among Accredited Laboratories in Malaysia

NASA Astrophysics Data System (ADS)

Hussain, F.; Khairuddin, S.; Othman, H.

2017-01-01

An inter-laboratory comparison in relative humidity measurements among accredited laboratories has been coordinated by the National Metrology Institute of Malaysia. It was carried out to determine the performance of the participating laboratories. The objective of the comparison was to acknowledge the participating laboratories competencies and to verify the level of accuracies declared in their scope of accreditation, in accordance with the MS ISO/IEC 17025 accreditation. The measurement parameter involved was relative humidity for the range of 30-90 %rh at a nominal temperature of 50°C. Eight accredited laboratories participated in the inter-laboratory comparison. Two units of artifacts have been circulated among the participants as the transfer standards.

Reliability on intra-laboratory and inter-laboratory data of hair mineral analysis comparing with blood analysis.

PubMed

Namkoong, Sun; Hong, Seung Phil; Kim, Myung Hwa; Park, Byung Cheol

2013-02-01

Nowadays, although its clinical value remains controversial institutions utilize hair mineral analysis. Arguments about the reliability of hair mineral analysis persist, and there have been evaluations of commercial laboratories performing hair mineral analysis. The objective of this study was to assess the reliability of intra-laboratory and inter-laboratory data at three commercial laboratories conducting hair mineral analysis, compared to serum mineral analysis. Two divided hair samples taken from near the scalp were submitted for analysis at the same time, to all laboratories, from one healthy volunteer. Each laboratory sent a report consisting of quantitative results and their interpretation of health implications. Differences among intra-laboratory and interlaboratory data were analyzed using SPSS version 12.0 (SPSS Inc., USA). All the laboratories used identical methods for quantitative analysis, and they generated consistent numerical results according to Friedman analysis of variance. However, the normal reference ranges of each laboratory varied. As such, each laboratory interpreted the patient's health differently. On intra-laboratory data, Wilcoxon analysis suggested they generated relatively coherent data, but laboratory B could not in one element, so its reliability was doubtful. In comparison with the blood test, laboratory C generated identical results, but not laboratory A and B. Hair mineral analysis has its limitations, considering the reliability of inter and intra laboratory analysis comparing with blood analysis. As such, clinicians should be cautious when applying hair mineral analysis as an ancillary tool. Each laboratory included in this study requires continuous refinement from now on for inducing standardized normal reference levels.

[ISO 15189 medical laboratory accreditation].

PubMed

Aoyagi, Tsutomu

2004-10-01

This International Standard, based upon ISO/IEC 17025 and ISO 9001, provides requirements for competence and quality that are particular to medical laboratories. While this International Standard is intended for use throughout the currently recognized disciplines of medical laboratory services, those working in other services and disciplines will also find it useful and appropriate. In addition, bodies engaged in the recognition of the competence of medical laboratories will be able to use this International Standard as the basis for their activities. The Japan Accreditation Board for Conformity Assessment (AB) and the Japanese Committee for Clinical Laboratory Standards (CCLS) are jointly developing the program of accreditation of medical laboratories. ISO 15189 requirements consist of two parts, one is management requirements and the other is technical requirements. The former includes the requirements of all parts of ISO 9001, moreover it includes the requirement of conformity assessment body, for example, impartiality and independence from any other party. The latter includes the requirements of laboratory competence (e.g. personnel, facility, instrument, and examination methods), moreover it requires that laboratories shall participate proficiency testing(s) and laboratories' examination results shall have traceability of measurements and implement uncertainty of measurement. Implementation of ISO 15189 will result in a significant improvement in medical laboratories management system and their technical competence. The accreditation of medical laboratory will improve medical laboratory service and be useful for patients.

Laboratory Activities in Israel

ERIC Educational Resources Information Center

Mamlok-Naaman, Rachel; Barnea, Nitza

2012-01-01

Laboratory activities have long had a distinctive and central role in the science curriculum, and science educators have suggested that many benefits accrue from engaging students in science laboratory activities. Many research studies have been conducted to investigate the educational effectiveness of laboratory work in science education in…

University-level Non-proliferation and Safeguards Education and Human Capital Development Activities at Brookhaven National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bachner K. M.; Pepper, S.; Gomera, J.

BNL has offered Nuclear Nonproliferation, Safeguards and Security in the 21st Century,? referred to as NNSS, every year since 2009 for graduate students in technical and policy fields related to nuclear safeguards and nonproliferation. The course focuses on relevant policy issues, in addition to technical components, and is part of a larger NGSI short course initiative that includes separate courses that are delivered at three other national laboratories and NNSA headquarters. [SCHOLZ and ROSENTHAL] The course includes lectures from esteemed nonproliferation experts, tours of various BNL facilities and laboratories, and in-field and table-top exercises on both technical and policy subjects.more » Topics include the history of the Treaty on the Non-proliferation of Nuclear Weapons (NPT) and other relevant treaties, the history of and advances in international nuclear safeguards, current relevant political situations in countries such as Iran, Iraq, and the Democratic Peoples? Republic of Korea (DPRK), nuclear science and technology, instrumentation and techniques used for verification activities, and associated research and development. The students conduct a mock Design Information Verification (DIV) at BNL?s decommissioned Medical Research Reactor. The capstone of the course includes a series of student presentations in which students act as policy advisors and provide recommendations in response to scenarios involving a current nonproliferation related event that are prepared by the course organizers. ?The course is open to domestic and foreign students, and caters to students in, entering, or recently having completed graduate school. Interested students must complete an application and provide a resume and a statement describing their interest in the course. Eighteen to 22 students attend annually; 165 students have completed the course to date. A stipend helps to defray students? travel and subsistence expenses. In 2015, the course was shortened from three

An evaluation of medication appropriateness and frailty among residents of aged care homes in Malaysia: A cross-sectional study.

PubMed

Hasan, Syed Shahzad; Kow, Chia Siang; Verma, Rohit Kumar; Ahmed, Syed Imran; Mittal, Piyush; Chong, David W K

2017-09-01

Aging is significantly associated with the development of comorbid chronic conditions. These conditions indicate the use of multiple medications, and are often warranted by clinical guidelines. The aim of the present study was to evaluate medication appropriateness and frailty among Malaysian aged care home residents with chronic disease. The participants were 202 elderly (≥65 years) individuals, a cross-sectional sample from 17 aged care homes. After ethics approval, each participant was interviewed to collect data on sociodemographics, frailty status (Groningen Frailty Indicator [GFI]), medication appropriateness (Medication Appropriateness Index (MAI), the 2015 Beers' criteria (Potentially Inappropriate Medication [PIM]), and 2014 STOPP criteria (Potentially Inappropriate Prescribing [PIP]). The findings show that 81% (n = 164) and 42% (n = 85) were taking medications for cardiovascular and central nervous system-related conditions, respectively, and 34% were using medications for diabetes (n = 69). Each participant had a mean of 2.9 ± 1.5 chronic diseases, with an average GFI score of 6.4 ± 3.6. More than three-quarters of the participants (76%) were frail and polypharmacy was a factor in nearly half (48%); 41% and 36% were prescribed at least one PIP and PIM, respectively, whereas the average MAI score was 0.6 (range: 0-6). The number of medications used per participant correlated significantly and positively (0.21, P = .002) with GFI score. These findings reinforce the need for participants of aged care homes to receive periodic medication review aimed at minimizing morbidity associated with inappropriate pharmacotherapy.

GRANULOCYTE INFILTRATION AND EXPRESSION OF THE PRO-ANGIOGENIC BV8 PROTEIN IN EXPERIMENTAL EL4 AND LEWIS LUNG CARCINOMA TUMORS.

PubMed

Jiang, Kan; Kwak, Hyeongil; Tosato, Giovanna

2013-01-18

Although Vascular Endothelial Growth Factor (VEGF)-targeted therapies have shown efficacy in the treatment of certain advanced cancers, benefits to patients have been modest, which is attributed to tumor resistance to VEGF neutralization. Recent efforts to identify new targets to inhibit tumor angiogenesis have identified Bv8 (prokineticin 2), a myeloid cell-derived protein that promotes endothelial cell growth and tumor angiogenesis, but many mechanistic aspects of the pro-tumorigenic function of Bv8 are unclear. Here we demonstrate that CD11b+, Ly6C+, Ly6G+ granulocytes are the predominant cell source of Bv8 expression in bone marrow, spleen and in tumor tissues. Using granulocyte-deficient Growth factor independence-1 (Gfi1)-null mutant mice and normal littermates, we found that EL4 lymphoma tumors grow significantly larger in the granulocyte and Bv8-deficient mutant mice in comparison to the normal mice that display abundant tumor-associated granulocytes and Bv8 expression. Conversely, Lewis lung carcinoma (LLC-1) tumors grew to a significantly greater size in the normal mice in comparison to the Gfi1-null mice, but normal granulocyte tumor infiltration was modest. Quantitative analysis of tissue vascularization showed that EL4 and LLC-1 tumors from normal and Gfi1-mutant mice are similarly vascularized. These results confirm the critical contribution of the tumor microenvironment in determining the rate of tumor progression independently of tumor angiogenesis, and reveal some of the complexities of granulocyte and Bv8 functions in modulating tumor growth.

GRANULOCYTE INFILTRATION AND EXPRESSION OF THE PRO-ANGIOGENIC BV8 PROTEIN IN EXPERIMENTAL EL4 AND LEWIS LUNG CARCINOMA TUMORS

PubMed Central

Jiang, Kan; Kwak, Hyeongil; Tosato, Giovanna

2014-01-01

Although Vascular Endothelial Growth Factor (VEGF)-targeted therapies have shown efficacy in the treatment of certain advanced cancers, benefits to patients have been modest, which is attributed to tumor resistance to VEGF neutralization. Recent efforts to identify new targets to inhibit tumor angiogenesis have identified Bv8 (prokineticin 2), a myeloid cell-derived protein that promotes endothelial cell growth and tumor angiogenesis, but many mechanistic aspects of the pro-tumorigenic function of Bv8 are unclear. Here we demonstrate that CD11b+, Ly6C+, Ly6G+ granulocytes are the predominant cell source of Bv8 expression in bone marrow, spleen and in tumor tissues. Using granulocyte-deficient Growth factor independence-1 (Gfi1)-null mutant mice and normal littermates, we found that EL4 lymphoma tumors grow significantly larger in the granulocyte and Bv8-deficient mutant mice in comparison to the normal mice that display abundant tumor-associated granulocytes and Bv8 expression. Conversely, Lewis lung carcinoma (LLC-1) tumors grew to a significantly greater size in the normal mice in comparison to the Gfi1-null mice, but normal granulocyte tumor infiltration was modest. Quantitative analysis of tissue vascularization showed that EL4 and LLC-1 tumors from normal and Gfi1-mutant mice are similarly vascularized. These results confirm the critical contribution of the tumor microenvironment in determining the rate of tumor progression independently of tumor angiogenesis, and reveal some of the complexities of granulocyte and Bv8 functions in modulating tumor growth. PMID:25493215

USING THE LANGUAGE LABORATORY.

ERIC Educational Resources Information Center

LADU, TORA TUVE

TO ENCOURAGE UTILIZATION OF THE LANGUAGE LABORATORY AS A TEACHING TECHNIQUE, THIS BULLETIN DESCRIBES SUCH POSSIBLE USES OF THE LABORATORY AS PROGRAMING LESSONS, RECORDING, AND TESTING LANGUAGE SKILL DEVELOPMENT. ONE OF THE MOST IMPORTANT FUNCTIONS OF THE LABORATORY IS THE PATTERN DRILL, DESCRIBED HERE FOR FRENCH, GERMAN, AND SPANISH. EXAMPLES ARE…

Good Laboratory Practice. Part 3. Implementing Good Laboratory Practice in the Analytical Lab

ERIC Educational Resources Information Center

Wedlich, Richard C.; Pires, Amanda; Fazzino, Lisa; Fransen, Joseph M.

2013-01-01

Laboratories submitting experimental results to the Food and Drug Administration (FDA) or the Environmental Protection Agency (EPA) in support of Good Laboratory Practice (GLP) nonclinical laboratory studies must conduct such work in compliance with the GLP regulations. To consistently meet these requirements, lab managers employ a "divide…

Interactive virtual optical laboratories

NASA Astrophysics Data System (ADS)

Liu, Xuan; Yang, Yi

2017-08-01

Laboratory experiences are essential for optics education. However, college students have limited access to advanced optical equipment that is generally expensive and complicated. Hence there is a need for innovative solutions to expose students to advanced optics laboratories. Here we describe a novel approach, interactive virtual optical laboratory (IVOL) that allows unlimited number of students to participate the lab session remotely through internet, to improve laboratory education in photonics. Although students are not physically conducting the experiment, IVOL is designed to engage students, by actively involving students in the decision making process throughout the experiment.

Biotechnology Laboratory Methods.

ERIC Educational Resources Information Center

Davis, Robert H.; Kompala, Dhinakar S.

1989-01-01

Describes a course entitled "Biotechnology Laboratory" which introduces a variety of laboratory methods associated with biotechnology. Describes the history, content, and seven experiments of the course. The seven experiments are selected from microbiology and molecular biology, kinetics and fermentation, and downstream…

Laboratories | Energy Systems Integration Facility | NREL

Science.gov Websites

laboratories to be safely divided into multiple test stand locations (or "capability hubs") to enable Fabrication Laboratory Energy Systems High-Pressure Test Laboratory Energy Systems Integration Laboratory Energy Systems Sensor Laboratory Fuel Cell Development and Test Laboratory High-Performance Computing

Deposition of Suspended Clay to Open and Sand-Filled Framework Gravel Beds in a Laboratory Flume

NASA Astrophysics Data System (ADS)

Mooneyham, Christian; Strom, Kyle

2018-01-01

Pulses of fine sediment composed of sand, silt, and clay can be introduced to gravel bed rivers through runoff from burn-impacted hillslopes, landslides, bank failure, or the introduction of reservoir sediment as a result of sluicing or dam decommissioning. Here we present a study aimed at quantifying exchange between suspensions of clay and gravel beds. The questions that motivate the work are: how do bed roughness and pore space characteristics, shear velocity (u∗), and initial concentration (C0) affect clay deposition on or within gravel beds? Where does deposition within these beds occur, and can deposited clay be resuspended while the gravel is immobile? We examine these questions in a laboratory flume using acrylic, open-framework gravel, and armored sand-gravel beds under conditions of varying u∗ and C0. Deposition of clay occurred to all beds (even with Rouse numbers ˜ 0.01). We attribute deposition under full suspension conditions to be an outcome of localized protected zones where clay can settle and available pore space in the bed. For smooth wall cases, protection came from the viscous wall region and the development of bed forms; for the rough beds, protection came from separation zones and low-velocity pore spaces. Bed porosity was the strongest influencer of nondimensional deposition rate; deposition increased with porosity. Deposition was inversely related to u∗ for the acrylic bed runs; no influence of u∗ was found for the porous bed runs. Increases in discharge resulted in resuspension of clay from acrylic beds; no resuspension was observed in the porous bed runs.

External quality assessment of medical laboratories in Croatia: preliminary evaluation of post-analytical laboratory testing.

PubMed

Krleza, Jasna Lenicek; Dorotic, Adrijana; Grzunov, Ana

2017-02-15

Proper standardization of laboratory testing requires assessment of performance after the tests are performed, known as the post-analytical phase. A nationwide external quality assessment (EQA) scheme implemented in Croatia in 2014 includes a questionnaire on post-analytical practices, and the present study examined laboratory responses in order to identify current post-analytical phase practices and identify areas for improvement. In four EQA exercises between September 2014 and December 2015, 145-174 medical laboratories across Croatia were surveyed using the Module 11 questionnaire on the post-analytical phase of testing. Based on their responses, the laboratories were evaluated on four quality indicators: turnaround time (TAT), critical values, interpretative comments and procedures in the event of abnormal results. Results were presented as absolute numbers and percentages. Just over half of laboratories (56.3%) monitored TAT. Laboratories varied substantially in how they dealt with critical values. Most laboratories (65-97%) issued interpretative comments with test results. One third of medical laboratories (30.6-33.3%) issued abnormal test results without confirming them in additional testing. Our results suggest that the nationwide post-analytical EQA scheme launched in 2014 in Croatia has yet to be implemented to the full. To close the gaps between existing recommendations and laboratory practice, laboratory professionals should focus on ensuring that TAT is monitored and lists of critical values are established within laboratories. Professional bodies/institutions should focus on clarify and harmonized rules to standardized practices and applied for adding interpretative comments to laboratory test results and for dealing with abnormal test results.

Laboratory Waste Management. A Guidebook.

ERIC Educational Resources Information Center

American Chemical Society, Washington, DC.

A primary goal of the American Chemical Society Task Force on Laboratory Waste Management is to provide laboratories with the information necessary to develop effective strategies and training programs for managing laboratory wastes. This book is intended to present a fresh look at waste management from the laboratory perspective, considering both…

Data Sharing Report Characterization of Isotope Row Facilities Oak Ridge National Laboratory Oak Ridge TN

DOE Office of Scientific and Technical Information (OSTI.GOV)

Weaver, Phyllis C.

The U.S. Department of Energy (DOE) Oak Ridge Office of Environmental Management (EM-OR) requested that Oak Ridge Associated Universities (ORAU), working under the Oak Ridge Institute for Science and Education (ORISE) contract, provide technical and independent waste management planning support using funds provided by the American Recovery and Reinvestment Act (ARRA). Specifically, DOE EM-OR requested ORAU to plan and implement a survey approach, focused on characterizing the Isotope Row Facilities located at the Oak Ridge National Laboratory (ORNL) for future determination of an appropriate disposition pathway for building debris and systems, should the buildings be demolished. The characterization effort wasmore » designed to identify and quantify radiological and chemical contamination associated with building structures and process systems. The Isotope Row Facilities discussed in this report include Bldgs. 3030, 3031, 3032, 3033, 3033A, 3034, 3036, 3093, and 3118, and are located in the northeast quadrant of the main ORNL campus area, between Hillside and Central Avenues. Construction of the isotope production facilities was initiated in the late 1940s, with the exception of Bldgs. 3033A and 3118, which were enclosed in the early 1960s. The Isotope Row facilities were intended for the purpose of light industrial use for the processing, assemblage, and storage of radionuclides used for a variety of applications (ORNL 1952 and ORAU 2013). The Isotope Row Facilities provided laboratory and support services as part of the Isotopes Production and Distribution Program until 1989 when DOE mandated their shutdown (ORNL 1990). These facilities performed diverse research and developmental experiments in support of isotopes production. As a result of the many years of operations, various projects, and final cessation of operations, production was followed by inclusion into the surveillance and maintenance (S&M) project for eventual decontamination and decommissioning (D

Post-Baccalaureate Laboratory Specialist Certifications and Master’s Degrees in Laboratory Medicine

PubMed Central

Johnson, Susan T.

2013-01-01

Opportunities to advance one’s knowledge and position are available within the clinical laboratory arena. By obtaining a specialist credential in chemistry, hematology or microbiology, a laboratorian has demonstrated advance knowledge and ability in their respective discipline. These specialist certifications open doors within and outside the laboratory profession and may lead to promotion. The specialist in blood banking credential is unique in that accredited training programs are available, some of which are affiliated with universities and graduate credit is granted for program completion. Other avenues available include pathologist assistants programs, diplomats in laboratory management and Master of Science degrees in clinical laboratory science. There are a number of choices available to achieve your professional goal. PMID:27683434

Laboratory Ventilation and Safety.

ERIC Educational Resources Information Center

Steere, Norman V.

1965-01-01

In order to meet the needs of both safety and economy, laboratory ventilation systems must effectively remove air-borne toxic and flammable materials and at the same time exhaust a minimum volume of air. Laboratory hoods are the most commonly used means of removing gases, dusts, mists, vapors, and fumed from laboratory operations. To be effective,…

The Case for Laboratory Developed Procedures

PubMed Central

Sabatini, Linda M.; Tsongalis, Gregory J.; Caliendo, Angela M.; Olsen, Randall J.; Ashwood, Edward R.; Bale, Sherri; Benirschke, Robert; Carlow, Dean; Funke, Birgit H.; Grody, Wayne W.; Hayden, Randall T.; Hegde, Madhuri; Lyon, Elaine; Pessin, Melissa; Press, Richard D.; Thomson, Richard B.

2017-01-01

An explosion of knowledge and technology is revolutionizing medicine and patient care. Novel testing must be brought to the clinic with safety and accuracy, but also in a timely and cost-effective manner, so that patients can benefit and laboratories can offer testing consistent with current guidelines. Under the oversight provided by the Clinical Laboratory Improvement Amendments, laboratories have been able to develop and optimize laboratory procedures for use in-house. Quality improvement programs, interlaboratory comparisons, and the ability of laboratories to adjust assays as needed to improve results, utilize new sample types, or incorporate new mutations, information, or technologies are positive aspects of Clinical Laboratory Improvement Amendments oversight of laboratory-developed procedures. Laboratories have a long history of successful service to patients operating under Clinical Laboratory Improvement Amendments. A series of detailed clinical examples illustrating the quality and positive impact of laboratory-developed procedures on patient care is provided. These examples also demonstrate how Clinical Laboratory Improvement Amendments oversight ensures accurate, reliable, and reproducible testing in clinical laboratories. PMID:28815200

Guidelines for biosafety laboratory competency: CDC and the Association of Public Health Laboratories.

PubMed

Delany, Judy R; Pentella, Michael A; Rodriguez, Joyce A; Shah, Kajari V; Baxley, Karen P; Holmes, David E

2011-04-15

These guidelines for biosafety laboratory competency outline the essential skills, knowledge, and abilities required for working with biologic agents at the three highest biosafety levels (BSLs) (levels 2, 3, and 4). The competencies are tiered to a worker's experience at three levels: entry level, midlevel (experienced), and senior level (supervisory or managerial positions). These guidelines were developed on behalf of CDC and the Association of Public Health Laboratories (APHL) by an expert panel comprising 27 experts representing state and federal public health laboratories, private sector clinical and research laboratories, and academic centers. They were then reviewed by approximately 300 practitioners representing the relevant fields. The guidelines are intended for laboratorians working with hazardous biologic agents, obtained from either samples or specimens that are maintained and manipulated in clinical, environmental, public health, academic, and research laboratories.

75 FR 3245 - Accreditation and Approval of King Laboratories, Inc., as a Commercial Gauger and Laboratory

Federal Register 2010, 2011, 2012, 2013, 2014

2010-01-20

... King Laboratories, Inc., as a Commercial Gauger and Laboratory AGENCY: U.S. Customs and Border... Laboratories, Inc., as a commercial gauger and laboratory. SUMMARY: Notice is hereby given that, pursuant to 19 CFR 151.12 and 19 CFR 151.13, King Laboratories, Inc., 1300 E. 223rd St., 401, Carson, CA 90745, has...

75 FR 57478 - Accreditation and Approval of King Laboratories, Inc., as a Commercial Gauger and Laboratory

Federal Register 2010, 2011, 2012, 2013, 2014

2010-09-21

... King Laboratories, Inc., as a Commercial Gauger and Laboratory AGENCY: U.S. Customs and Border... Laboratories, Inc., as a commercial gauger and laboratory. SUMMARY: Notice is hereby given that, pursuant to 19 CFR 151.12 and 19 CFR 151.13, King Laboratories, Inc., 5009 S. MacDill Ave., Tampa, FL 33611, has been...

Evaluation of Calibration Laboratories Performance

NASA Astrophysics Data System (ADS)

Filipe, Eduarda

2011-12-01

One of the main goals of interlaboratory comparisons (ILCs) is the evaluation of the laboratories performance for the routine calibrations they perform for the clients. In the frame of Accreditation of Laboratories, the national accreditation boards (NABs) in collaboration with the national metrology institutes (NMIs) organize the ILCs needed to comply with the requirements of the international accreditation organizations. In order that an ILC is a reliable tool for a laboratory to validate its best measurement capability (BMC), it is needed that the NMI (reference laboratory) provides a better traveling standard—in terms of accuracy class or uncertainty—than the laboratories BMCs. Although this is the general situation, there are cases where the NABs ask the NMIs to evaluate the performance of the accredited laboratories when calibrating industrial measuring instruments. The aim of this article is to discuss the existing approaches for the evaluation of ILCs and propose a basis for the validation of the laboratories measurement capabilities. An example is drafted with the evaluation of the results of mercury-in-glass thermometers ILC with 12 participant laboratories.

Zero-gravity cloud physics laboratory: Experiment program definition and preliminary laboratory concept studies

NASA Technical Reports Server (NTRS)

Eaton, L. R.; Greco, E. V.

1973-01-01

The experiment program definition and preliminary laboratory concept studies on the zero G cloud physics laboratory are reported. This program involves the definition and development of an atmospheric cloud physics laboratory and the selection and delineations of a set of candidate experiments that must utilize the unique environment of zero gravity or near zero gravity.

ISO 15189 accreditation: Requirements for quality and competence of medical laboratories, experience of a laboratory I.

PubMed

Guzel, Omer; Guner, Ebru Ilhan

2009-03-01

Medical laboratories are the key partners in patient safety. Laboratory results influence 70% of medical diagnoses. Quality of laboratory service is the major factor which directly affects the quality of health care. The clinical laboratory as a whole has to provide the best patient care promoting excellence. International Standard ISO 15189, based upon ISO 17025 and ISO 9001 standards, provides requirements for competence and quality of medical laboratories. Accredited medical laboratories enhance credibility and competency of their testing services. Our group of laboratories, one of the leading institutions in the area, had previous experience with ISO 9001 and ISO 17025 Accreditation at non-medical sections. We started to prepared for ISO 15189 Accreditation at the beginning of 2006 and were certified in March, 2007. We spent more than a year to prepare for accreditation. Accreditation scopes of our laboratory were as follows: clinical chemistry, hematology, immunology, allergology, microbiology, parasitology, molecular biology of infection serology and transfusion medicine. The total number of accredited tests is 531. We participate in five different PT programs. Inter Laboratory Comparison (ILC) protocols are performed with reputable laboratories. 82 different PT Program modules, 277 cycles per year for 451 tests and 72 ILC program organizations for remaining tests have been performed. Our laboratory also organizes a PT program for flow cytometry. 22 laboratories participate in this program, 2 cycles per year. Our laboratory has had its own custom made WEB based LIS system since 2001. We serve more than 500 customers on a real time basis. Our quality management system is also documented and processed electronically, Document Management System (DMS), via our intranet. Preparatory phase for accreditation, data management, external quality control programs, personnel related issues before, during and after accreditation process are presented. Every laboratory has

The Language Laboratory.

ERIC Educational Resources Information Center

Hocking, Elton

This condensed article on the language laboratory describes educational and financial possibilities and limitations, often citing the foreign language program at Purdue University as an example. The author discusses: (1) costs and amortization, (2) preventive maintenance, (3) laboratory design, (4) the multichannel recorder, and (5) visuals. Other…

Measuring laboratory-based influenza surveillance capacity: development of the 'International Influenza Laboratory Capacity Review' Tool.

PubMed

Muir-Paulik, S A; Johnson, L E A; Kennedy, P; Aden, T; Villanueva, J; Reisdorf, E; Humes, R; Moen, A C

2016-01-01

The 2005 International Health Regulations (IHR 2005) emphasized the importance of laboratory capacity to detect emerging diseases including novel influenza viruses. To support IHR 2005 requirements and the need to enhance influenza laboratory surveillance capacity, the Association of Public Health Laboratories (APHL) and the Centers for Disease Control and Prevention (CDC) Influenza Division developed the International Influenza Laboratory Capacity Review (Tool). Data from 37 assessments were reviewed and analyzed to verify that the quantitative analysis results accurately depicted a laboratory's capacity and capabilities. Subject matter experts in influenza and laboratory practice used an iterative approach to develop the Tool incorporating feedback and lessons learnt through piloting and implementation. To systematically analyze assessment data, a quantitative framework for analysis was added to the Tool. The review indicated that changes in scores consistently reflected enhanced or decreased capacity. The review process also validated the utility of adding a quantitative analysis component to the assessments and the benefit of establishing a baseline from which to compare future assessments in a standardized way. Use of the Tool has provided APHL, CDC and each assessed laboratory with a standardized analysis of the laboratory's capacity. The information generated is used to improve laboratory systems for laboratory testing and enhance influenza surveillance globally. We describe the development of the Tool and lessons learnt. Copyright © 2015 The Authors. Published by Elsevier Ltd.. All rights reserved.

Harmonization of good laboratory practice requirements and laboratory accreditation programs.

PubMed

Royal, P D

1994-09-01

Efforts to harmonize Good Laboratory Practice (GLP) requirements have been underway through the Organization for Economic Cooperation and Development (OECD) since 1981. In 1985, a GLP panel was established to facilitate the practical implementation of the OECD/GLP program. Through the OECD/GLP program, Memoranda of Understanding (MOU) agreements which foster requirements for reciprocal data and study acceptance and unified GLP standards have been developed among member countries. Three OECD Consensus Workshops and three inspectors training workshops have been held. In concert with these efforts, several OECD countries have developed GLP accreditation programs, managed by local health and environmental ministries. In addition, Canada and the United States are investigating Laboratory Accreditation programs for environmental monitoring assessment and GLP-regulated studies. In the European Community (EC), the need for quality standards specifying requirements for production and international trade has promoted International Standards Organization (ISO) certification for certain products. ISO-9000 standards identify requirements for certification of quality systems. These certification programs may affect the trade and market of laboratories conducting GLP studies. Two goals identified by these efforts are common to both programs: first, harmonization and recognition of requirements, and second, confidence in the rigor of program components used to assess the integrity of data produced and study activities. This confidence can be promoted, in part, through laboratory inspection and screening processes. However, the question remains, will data produced by sanctioned laboratories be mutually accepted on an international basis?(ABSTRACT TRUNCATED AT 250 WORDS)

Conceptual design of new metrology laboratories for the National Physical Laboratory, United Kingdom

NASA Astrophysics Data System (ADS)

Manning, Christopher J.

1994-10-01

The National Physical Laboratory is planning to house the Division of Mechanical and Optical Metrology and the Division of Material Metrology in a new purpose built laboratory building on its site at Teddington, London, England. The scientific staff were involved in identifying and agreeing the vibration performance requirements of the conceptual design. This was complemented by an extensive surgery of vibration levels within the existing facilities and ambient vibration studies at the proposed site. At one end of the site there is significant vibration input from road traffic. Some of the test equipment is also in itself a source of vibration input. These factors, together with normal occupancy inputs, footfalls and door slams, and a highly serviced building led to vibration being dominant in influencing the structural form. The resulting structural concept comprises three separate structural elements for vibration and geotechnical reasons. The laboratories most sensitive to disturbance by vibration are located at the end of the site farthest from local roads on a massive ground bearing slab. Less sensitive laboratories and those containing vibration sources are located on a massive slab in deep, piled foundations. A common central plant area is located alongside on its own massive slab. Medium sensitivity laboratories and offices are located at first floor level on a reinforced concrete suspended floor of maximum stiffness per unit mass. The whole design has been such as to permit upgrading of areas, eg office to laboratory; laboratory to `high sensitivity' laboratory, to cater for changes in future use of the building.

National Laboratory Planning: Developing Sustainable Biocontainment Laboratories in Limited Resource Areas.

PubMed

Yeh, Kenneth B; Adams, Martin; Stamper, Paul D; Dasgupta, Debanjana; Hewson, Roger; Buck, Charles D; Richards, Allen L; Hay, John

2016-01-01

Strategic laboratory planning in limited resource areas is essential for addressing global health security issues. Establishing a national reference laboratory, especially one with BSL-3 or -4 biocontainment facilities, requires a heavy investment of resources, a multisectoral approach, and commitments from multiple stakeholders. We make the case for donor organizations and recipient partners to develop a comprehensive laboratory operations roadmap that addresses factors such as mission and roles, engaging national and political support, securing financial support, defining stakeholder involvement, fostering partnerships, and building trust. Successful development occurred with projects in African countries and in Azerbaijan, where strong leadership and a clear management framework have been key to success. A clearly identified and agreed management framework facilitate identifying the responsibility for developing laboratory capabilities and support services, including biosafety and biosecurity, quality assurance, equipment maintenance, supply chain establishment, staff certification and training, retention of human resources, and sustainable operating revenue. These capabilities and support services pose rate-limiting yet necessary challenges. Laboratory capabilities depend on mission and role, as determined by all stakeholders, and demonstrate the need for relevant metrics to monitor the success of the laboratory, including support for internal and external audits. Our analysis concludes that alternative frameworks for success exist for developing and implementing capabilities at regional and national levels in limited resource areas. Thus, achieving a balance for standardizing practices between local procedures and accepted international standards is a prerequisite for integrating new facilities into a country's existing public health infrastructure and into the overall international scientific community.

National Laboratory Planning: Developing Sustainable Biocontainment Laboratories in Limited Resource Areas

PubMed Central

Adams, Martin; Stamper, Paul D.; Dasgupta, Debanjana; Hewson, Roger; Buck, Charles D.; Richards, Allen L.; Hay, John

2016-01-01

Strategic laboratory planning in limited resource areas is essential for addressing global health security issues. Establishing a national reference laboratory, especially one with BSL-3 or -4 biocontainment facilities, requires a heavy investment of resources, a multisectoral approach, and commitments from multiple stakeholders. We make the case for donor organizations and recipient partners to develop a comprehensive laboratory operations roadmap that addresses factors such as mission and roles, engaging national and political support, securing financial support, defining stakeholder involvement, fostering partnerships, and building trust. Successful development occurred with projects in African countries and in Azerbaijan, where strong leadership and a clear management framework have been key to success. A clearly identified and agreed management framework facilitate identifying the responsibility for developing laboratory capabilities and support services, including biosafety and biosecurity, quality assurance, equipment maintenance, supply chain establishment, staff certification and training, retention of human resources, and sustainable operating revenue. These capabilities and support services pose rate-limiting yet necessary challenges. Laboratory capabilities depend on mission and role, as determined by all stakeholders, and demonstrate the need for relevant metrics to monitor the success of the laboratory, including support for internal and external audits. Our analysis concludes that alternative frameworks for success exist for developing and implementing capabilities at regional and national levels in limited resource areas. Thus, achieving a balance for standardizing practices between local procedures and accepted international standards is a prerequisite for integrating new facilities into a country's existing public health infrastructure and into the overall international scientific community. PMID:27559843

[Quality use of commercial laboratory for clinical testing services - considering laboratory's role].

PubMed

Ogawa, Shinji

2014-12-01

The number of commercial laboratories for clinical testing in Japan run privately has decreased to about 30 companies, and their business is getting tougher. Branch Lab. and FMS businesses have not expanded recently due to the new reimbursement system which adds an additional sample management fee, becoming effective in 2010. This presentation gives an outline of each role for hospital and commercial laboratories, and their pros & cons considering the current medical situation. Commercial laboratories have investigated how to utilize ICT systems for sharing test information between hospitals and our facilities. It would be very helpful to clarify issues for each hospital. We will develop and create new values for clinical laboratory testing services and forge mutually beneficial relationships with medical institutions. (Review).

Dental Laboratory Technology.

ERIC Educational Resources Information Center

Department of the Air Force, Washington, DC.

The Air Force dental laboratory technology manual is designed as a basic training text as well as a reference source for dental laboratory technicians, a specialty occupation concerned with the design, fabrication, and repair of dental prostheses. Numerous instructive diagrams and photographs are included throughout the manual. The comprehensive…

Student research laboratory for optical engineering

NASA Astrophysics Data System (ADS)

Tolstoba, Nadezhda D.; Saitgalina, Azaliya; Abdula, Polina; Butova, Daria

2015-10-01

Student research laboratory for optical engineering is comfortable place for student's scientific and educational activity. The main ideas of laboratory, process of creation of laboratory and also activity of laboratory are described in this article. At ITMO University in 2013-2014 were formed a lot of research laboratories. SNLO is a student research (scientific) laboratory formed by the Department of Applied and computer optics of the University ITMO (Information Technologies of Mechanics and Optics). Activity of laboratory is career guidance of entrants and students in the field of optical engineering. Student research laboratory for optical engineering is a place where student can work in the interesting and entertaining scientific atmosphere.

Anthropometric measures in cardiovascular disease prediction: comparison of laboratory-based versus non-laboratory-based model.

PubMed

Dhana, Klodian; Ikram, M Arfan; Hofman, Albert; Franco, Oscar H; Kavousi, Maryam

2015-03-01

Body mass index (BMI) has been used to simplify cardiovascular risk prediction models by substituting total cholesterol and high-density lipoprotein cholesterol. In the elderly, the ability of BMI as a predictor of cardiovascular disease (CVD) declines. We aimed to find the most predictive anthropometric measure for CVD risk to construct a non-laboratory-based model and to compare it with the model including laboratory measurements. The study included 2675 women and 1902 men aged 55-79 years from the prospective population-based Rotterdam Study. We used Cox proportional hazard regression analysis to evaluate the association of BMI, waist circumference, waist-to-hip ratio and a body shape index (ABSI) with CVD, including coronary heart disease and stroke. The performance of the laboratory-based and non-laboratory-based models was evaluated by studying the discrimination, calibration, correlation and risk agreement. Among men, ABSI was the most informative measure associated with CVD, therefore ABSI was used to construct the non-laboratory-based model. Discrimination of the non-laboratory-based model was not different than laboratory-based model (c-statistic: 0.680-vs-0.683, p=0.71); both models were well calibrated (15.3% observed CVD risk vs 16.9% and 17.0% predicted CVD risks by the non-laboratory-based and laboratory-based models, respectively) and Spearman rank correlation and the agreement between non-laboratory-based and laboratory-based models were 0.89 and 91.7%, respectively. Among women, none of the anthropometric measures were independently associated with CVD. Among middle-aged and elderly where the ability of BMI to predict CVD declines, the non-laboratory-based model, based on ABSI, could predict CVD risk as accurately as the laboratory-based model among men. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

76 FR 24345 - Airworthiness Directives; The Boeing Company Model 777-200, -200LR, -300, and -300ER Series...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-05-02

... certain boost pump relays with ground fault interrupter (GFI) relays. For certain other airplanes, this AD... service information identified in this AD, contact Boeing Commercial Airplanes, Attention: Data & Services... Building Ground Floor, Room W12-140, 1200 New Jersey Avenue, SE., Washington, DC 20590. FOR FURTHER...

Data Validation Package, June 2016 Groundwater Sampling at the Hallam, Nebraska, Decommissioned Reactor Site, August 2016

DOE Office of Scientific and Technical Information (OSTI.GOV)

Surovchak, Scott; Miller, Michele

The 2008 Long-Term Surveillance Plan [LTSP] for the Decommissioned Hallam Nuclear Power Facility, Hallam, Nebraska (http://www.lm.doe.gov/Hallam/Documents.aspx) requires groundwater monitoring once every 2 years. Seventeen monitoring wells at the Hallam site were sampled during this event as specified in the plan. Planned monitoring locations are shown in Attachment 1, Sampling and Analysis Work Order. Water levels were measured at all sampled wells and at two additional wells (6A and 6B) prior to the start of sampling. Additionally, water levels of each sampled well were measured at the beginning of sampling. See Attachment 2, Trip Report, for additional details. Sampling and analysismore » were conducted as specified in Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites (LMS/PRO/S04351, continually updated, http://energy.gov/lm/downloads/sampling-and-analysis-plan-us-department- energy-office-legacy-management-sites). Gross alpha and gross beta are the only parameters that were detected at statistically significant concentrations. Time/concentration graphs of the gross alpha and gross beta data are included in Attachment 3, Data Presentation. The gross alpha and gross beta activity concentrations observed are consistent with values previously observed and are attributed to naturally occurring radionuclides (e.g., uranium and uranium decay chain products) in the groundwater.« less

Clinical laboratory accreditation in India.

PubMed

Handoo, Anil; Sood, Swaroop Krishan

2012-06-01

Test results from clinical laboratories must ensure accuracy, as these are crucial in several areas of health care. It is necessary that the laboratory implements quality assurance to achieve this goal. The implementation of quality should be audited by independent bodies,referred to as accreditation bodies. Accreditation is a third-party attestation by an authoritative body, which certifies that the applicant laboratory meets quality requirements of accreditation body and has demonstrated its competence to carry out specific tasks. Although in most of the countries,accreditation is mandatory, in India it is voluntary. The quality requirements are described in standards developed by many accreditation organizations. The internationally acceptable standard for clinical laboratories is ISO15189, which is based on ISO/IEC standard 17025. The accreditation body in India is the National Accreditation Board for Testing and Calibration Laboratories, which has signed Mutual Recognition Agreement with the regional cooperation the Asia Pacific Laboratory Accreditation Cooperation and with the apex cooperation the International Laboratory Accreditation Cooperation.

[Safety in the Microbiology laboratory].

PubMed

Rojo-Molinero, Estrella; Alados, Juan Carlos; de la Pedrosa, Elia Gómez G; Leiva, José; Pérez, José L

2015-01-01

The normal activity in the laboratory of microbiology poses different risks - mainly biological - that can affect the health of their workers, visitors and the community. Routine health examinations (surveillance and prevention), individual awareness of self-protection, hazard identification and risk assessment of laboratory procedures, the adoption of appropriate containment measures, and the use of conscientious microbiological techniques allow laboratory to be a safe place, as records of laboratory-acquired infections and accidents show. Training and information are the cornerstones for designing a comprehensive safety plan for the laboratory. In this article, the basic concepts and the theoretical background on laboratory safety are reviewed, including the main legal regulations. Moreover, practical guidelines are presented for each laboratory to design its own safety plan according its own particular characteristics. Copyright © 2014 Elsevier España, S.L.U. y Sociedad Española de Enfermedades Infecciosas y Microbiología Clínica. All rights reserved.

Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Cochran, John Russell; Danneels, Jeffrey John

2009-03-01

Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraqmore » Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21-25, 2008. As noted in

42 CFR 493.1850 - Laboratory registry.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 42 Public Health 5 2010-10-01 2010-10-01 false Laboratory registry. 493.1850 Section 493.1850... (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Enforcement Procedures § 493.1850 Laboratory... laboratories, including the following: (1) A list of laboratories that have been convicted, under Federal or...

42 CFR 493.1850 - Laboratory registry.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 42 Public Health 5 2011-10-01 2011-10-01 false Laboratory registry. 493.1850 Section 493.1850... (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Enforcement Procedures § 493.1850 Laboratory... laboratories, including the following: (1) A list of laboratories that have been convicted, under Federal or...

Medical Laboratory Technician.

ERIC Educational Resources Information Center

Ohio State Univ., Columbus. Center on Education and Training for Employment.

This document, which is designed for use in developing a tech prep competency profile for the occupation of medical laboratory technician, lists technical competencies and competency builders for 18 units pertinent to the health technologies cluster in general and 8 units specific to the occupation of medical laboratory technician. The following…

Frederick National Laboratory Collaboration Success Stories | Frederick National Laboratory for Cancer Research

Cancer.gov

Nanotechnology Characterization Laboratory Unveils New Technical Services for Drug Developers Drug developers now have access to a shared analytical technology, developed and provided by the Frederick National Laboratory, that helps fine-tune nano

Severe congenital neutropenia in a multigenerational family with a novel neutrophil elastase (ELANE) mutation.

PubMed

van de Vosse, Esther; Verhard, Els M; Tool, Anton J T; de Visser, Adriëtte W; Kuijpers, Taco W; Hiemstra, Pieter S; van Dissel, Jaap T

2011-02-01

We have analysed a family with nine congenital neutropenia patients in four generations, several of which we have studied in a long-term follow-up of over 25 years. The patients were mild to severe neutropenic and suffered from various recurrent bacterial infections. Mutations in the genes ELANE, CSF3R and GFI1 have been reported in patients with autosomal dominant congenital neutropenias. Using a small-scale linkage analysis with markers around the ELANE, CSF3R, CSF3 and GFI1 genes, we were able to determine that the disease segregated with markers around the ELANE gene. We identified a novel mutation in the ELANE gene in all of the affected family members that was not present in any of the healthy family members. The mutation leads to an A28S missense mutation in the mature protein. None of these patients developed leukaemia. This is the first truly multigenerational family with mutations in ELANE as unambiguous cause of severe congenital neutropenia SCN.

27 CFR 22.108 - Other laboratories.

Code of Federal Regulations, 2010 CFR

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Other laboratories. 22.108... Other laboratories. Laboratories, other than pathological laboratories specified in § 22.107, may... products resulting from the use of tax-free alcohol shall be confined strictly to the laboratory premises...

27 CFR 22.108 - Other laboratories.

Code of Federal Regulations, 2011 CFR

2011-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2011-04-01 2011-04-01 false Other laboratories. 22.108... Other laboratories. Laboratories, other than pathological laboratories specified in § 22.107, may... products resulting from the use of tax-free alcohol shall be confined strictly to the laboratory premises...

Laboratory assessment of novel oral anticoagulants: method suitability and variability between coagulation laboratories.

PubMed

Helin, Tuukka A; Pakkanen, Anja; Lassila, Riitta; Joutsi-Korhonen, Lotta

2013-05-01

Laboratory tests to assess novel oral anticoagulants (NOACs) are under evaluation. Routine monitoring is unnecessary, but under special circumstances bioactivity assessment becomes crucial. We analyzed the effects of NOACs on coagulation tests and the availability of specific assays at different laboratories. Plasma samples spiked with dabigatran (Dabi; 120 and 300 μg/L) or rivaroxaban (Riva; 60, 146, and 305 μg/L) were sent to 115 and 38 European laboratories, respectively. International normalized ratio (INR) and activated partial thromboplastin time (APTT) were analyzed for all samples; thrombin time (TT) was analyzed specifically for Dabi and calibrated anti-activated factor X (anti-Xa) activity for Riva. We compared the results with patient samples. Results of Dabi samples were reported by 73 laboratories (13 INR and 9 APTT reagents) and Riva samples by 22 laboratories (5 INR and 4 APTT reagents). Both NOACs increased INR values; the increase was modest, albeit larger, for Dabi, with higher CV, especially with Quick (vs Owren) methods. Both NOACs dose-dependently prolonged the APTT. Again, the prolongation and CVs were larger for Dabi. The INR and APTT results varied reagent-dependently (P < 0.005), with less prolongation in patient samples. TT results (Dabi) and calibrated anti-Xa results (Riva) were reported by only 11 and 8 laboratories, respectively. The screening tests INR and APTT are suboptimal in assessing NOACs, having high reagent dependence and low sensitivity and specificity. They may provide information, if laboratories recognize their limitations. The variation will likely increase and the sensitivity differ in clinical samples. Specific assays measure NOACs accurately; however, few laboratories applied them. © 2013 American Association for Clinical Chemistry.

Safety in the Chemical Laboratory. Chemical Laboratory Safety: The Academic Anomaly.

ERIC Educational Resources Information Center

Bretherick, Leslie

1990-01-01

Discussed are accidents that occur in the laboratories of highly trained chemists. Four examples are provided to illustrate potential hazards that are often overlooked in chemistry laboratories, molten inorganic salt baths, the reaction of acetone and hydrogen peroxide, halogenated acetylene compounds, and the reaction of hydrogen peroxide and…

Intelligent Performance Assessment of Students' Laboratory Work in a Virtual Electronic Laboratory Environment

ERIC Educational Resources Information Center

Achumba, I. E.; Azzi, D.; Dunn, V. L.; Chukwudebe, G. A.

2013-01-01

Laboratory work is critical in undergraduate engineering courses. It is used to integrate theory and practice. This demands that laboratory activities are synchronized with lectures to maximize their derivable learning outcomes, which are measurable through assessment. The typical high costs of the traditional engineering laboratory, which often…

42 CFR 414.510 - Laboratory date of service for clinical laboratory and pathology specimens.

Code of Federal Regulations, 2014 CFR

2014-10-01

... and pathology specimens. 414.510 Section 414.510 Public Health CENTERS FOR MEDICARE & MEDICAID... Laboratory date of service for clinical laboratory and pathology specimens. The date of service for either a clinical laboratory test or the technical component of physician pathology service is as follows: (a...

42 CFR 414.510 - Laboratory date of service for clinical laboratory and pathology specimens.

Code of Federal Regulations, 2012 CFR

2012-10-01

... and pathology specimens. 414.510 Section 414.510 Public Health CENTERS FOR MEDICARE & MEDICAID... Laboratory date of service for clinical laboratory and pathology specimens. The date of service for either a clinical laboratory test or the technical component of physician pathology service is as follows: (a...

42 CFR 414.510 - Laboratory date of service for clinical laboratory and pathology specimens.

Code of Federal Regulations, 2013 CFR

2013-10-01

... and pathology specimens. 414.510 Section 414.510 Public Health CENTERS FOR MEDICARE & MEDICAID... Laboratory date of service for clinical laboratory and pathology specimens. The date of service for either a clinical laboratory test or the technical component of physician pathology service is as follows: (a...

Dental Laboratory Technician.

ERIC Educational Resources Information Center

Ohio State Univ., Columbus. Center on Education and Training for Employment.

This document, which is designed for use in developing a tech prep competency profile for the occupation of dental laboratory technician, lists technical competencies and competency builders for 13 units pertinent to the health technologies cluster in general and 8 units to the occupation of dental laboratory technician. The following skill areas…

Laboratory for Oceans

NASA Technical Reports Server (NTRS)

1988-01-01

A review is made of the activities of the Laboratory for Oceans. The staff and the research activities are nearly evenly divided between engineering and scientific endeavors. The Laboratory contributes engineering design skills to aircraft and ground based experiments in terrestrial and atmospheric sciences in cooperation with scientists from labs in Earth sciences.

Regeneration of a confined aquifer after redevelopment and decommission of artesian wells, example from Grafendorf aquifer (Styria, Austria)

NASA Astrophysics Data System (ADS)

Mehmedovski, Nudzejma; Winkler, Gerfried

2016-04-01

Water is essential for life and it is therefore necessary to protect drinking water sustainably. Compared to shallow groundwater, deeper groundwater is especially important due to its characteristic tendency to remain extensively unaffected by environmental impacts. Thus, the uncontrolled waste of this valuable resource has to be avoided. A lot of artesian wells have been established in Grafendorf bei Hartberg (Styria, Austria). Almost all wells were not state-of-the art. As a result the different aquifer horizons began to intermix. Additionally some of the artesian wells had a permanent free overflow and the water was not even used. Consequently, since 1950, where the mean discharge of 37 wells was 0,334 l/s per well, the discharge has decreased to 0,090 l/s until 2013, which means a decline of about 75 %. As a reaction to these declines a decommissioning campaign was conducted where 69 artesian wells have been closed by injecting a cement-bentonite suspension (ratio 3:1). The Grafendorf aquifer is situated in the Styrian Basin and consists of 5 separated artesian horizons in Neogene sediments. These artesian horizons range from 42 m (1st horizon) to 176 m (5th horizon) and mostly consist of sand, partly of fine/medium/coarse gravel and partially with minor clay content. In order to analyse the reaction of the Grafendorf aquifer to these redevelopments, 5 monitoring wells could be used for the analysis. Some monitoring wells include different aquifer horizons and hydraulically short cut them. Thus, in this work the analysis focus on the general trend of the whole aquifer system neglecting the individual interactions between the different aquifers. In a first investigation step the hydraulic properties of the aquifer system has been determined using pumping tests which were analysed with different analytical solutions with the software AQTESOLV. Overall the pumping test solutions hardly differ in the transmissivity and hydraulic conductivity. On the contrary the

Environmental Response Laboratory Network (ERLN) Laboratory Requirements

EPA Pesticide Factsheets

The Environmental Response Laboratory Network requires its member labs follow specified quality systems, sample management, data reporting, and general, in order to ensure consistent analytical data of known and documented quality.

Practical Laboratory Planning.

ERIC Educational Resources Information Center

Ferguson, W. R.

This book is intended as a guide for people who are planning chemistry and physics research laboratories. It deals with the importance of effective communication between client and architect, the value of preliminary planning, and the role of the project officer. It also discusses the size and layout of individual laboratories, the design of…

Definition of experiments and instruments for a communication/navigation research laboratory. Volume 3: Laboratory descriptions

NASA Technical Reports Server (NTRS)

1972-01-01

The following study objectives are covered: (1) identification of major laboratory equipment; (2) systems and operations analysis in support of the laboratory design; and (3) conceptual design of the comm/nav research laboratory.

Design and Calibration of the US Army Research Laboratory (ARL) Closed Loop Laboratory Radio Frequency (RF) Propagation Section

DTIC Science & Technology

2016-10-01

ARL-TR-7860 ● OCT 2016 US Army Research Laboratory Design and Calibration of the US Army Research Laboratory (ARL) Closed Loop ...ARL-TR-7860 ● OCT 2016 US Army Research Laboratory Design and Calibration of the US Army Research Laboratory (ARL) Closed Loop Laboratory...Design and Calibration of the US Army Research Laboratory (ARL) Closed Loop Laboratory Radio Frequency (RF) Propagation Section 5a. CONTRACT NUMBER