Science.gov

Sample records for standard irradiation facilities

  1. BIOLOGICAL IRRADIATION FACILITY

    DOEpatents

    McCorkle, W.H.; Cern, H.S.

    1962-04-24

    A facility for irradiating biological specimens with neutrons is described. It includes a reactor wherein the core is off center in a reflector. A high-exposure room is located outside the reactor on the side nearest the core while a low-exposure room is located on the opposite side. Means for converting thermal neutrons to fast neutrons are movably disposed between the reactor core and the high and low-exposure rooms. (AEC)

  2. LLL calibration and standards facility

    SciTech Connect

    Campbell, G.W.; Elliott, J.H.

    1980-04-15

    The capabilities of Lawrence Livermore Laboratory's Calibration and Standards Facility are delineated. The facility's ability to provide radiation fields and measurements for a variety of radiation safety applications and the available radiation measurement equipment are described. The need for national laboratory calibration labs to maintain traceability to a national standard are discussed as well as the areas where improved standards and standardization techniques are needed.

  3. New facility for post irradiation examination of neutron irradiated beryllium

    SciTech Connect

    Ishitsuka, Etsuo; Kawamura, Hiroshi

    1995-09-01

    Beryllium is expected as a neutron multiplier and plasma facing materials in the fusion reactor, and the neutron irradiation data on properties of beryllium up to 800{degrees}C need for the engineering design. The acquisition of data on the tritium behavior, swelling, thermal and mechanical properties are first priority in ITER design. Facility for the post irradiation examination of neutron irradiated beryllium was constructed in the hot laboratory of Japan Materials Testing Reactor to get the engineering design data mentioned above. This facility consist of the four glove boxes, dry air supplier, tritium monitoring and removal system, storage box of neutron irradiated samples. Beryllium handling are restricted by the amount of tritium;7.4 GBq/day and {sup 60}Co;7.4 MBq/day.

  4. 42 CFR 493.1101 - Standard: Facilities.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Facility Administration for Nonwaived Testing § 493.1101 Standard: Facilities. (a) The laboratory must be constructed, arranged, and maintained to..., amplification and product detection, and, as applicable, reagent preparation. (b) The laboratory must...

  5. 42 CFR 493.1101 - Standard: Facilities.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 42 Public Health 5 2013-10-01 2013-10-01 false Standard: Facilities. 493.1101 Section 493.1101... (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Facility Administration for Nonwaived Testing § 493.1101 Standard: Facilities. (a) The laboratory must be constructed, arranged, and maintained...

  6. Characterization of the fast neutron irradiation facility of the Portuguese Research Reactor after core conversion.

    PubMed

    Marques, J G; Sousa, M; Santos, J P; Fernandes, A C

    2011-08-01

    The fast neutron irradiation facility of the Portuguese Research Reactor was characterized after the reduction in uranium enrichment and rearrangement of the core configuration. In this work we report on the determination of the hardness parameter and the 1MeV equivalent neutron flux along the facility, in the new irradiation conditions, following ASTM E722 standard. PMID:21071234

  7. 42 CFR 493.1101 - Standard: Facilities.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Standard: Facilities. 493.1101 Section 493.1101 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Facility Administration for Nonwaived...

  8. Energy Codes and Standards: Facilities

    SciTech Connect

    Bartlett, Rosemarie; Halverson, Mark A.; Shankle, Diana L.

    2007-01-01

    Energy codes and standards play a vital role in the marketplace by setting minimum requirements for energy-efficient design and construction. They outline uniform requirements for new buildings as well as additions and renovations. This article covers basic knowledge of codes and standards; development processes of each; adoption, implementation, and enforcement of energy codes and standards; and voluntary energy efficiency programs.

  9. The SIRAD irradiation facility at LNL

    SciTech Connect

    Bisello, D.; Giubilato, P.; Mattiazzo, S.; Pantano, D.; Silvestrin, L.; Candelori, A.; Tessaro, M.; Wyss, J.

    2013-07-18

    SIRAD is the irradiation facility at the Tandem XTU accelerator of the INFN National Laboratory of Legnaro (Padova, Italy) dedicated to study radiation effects, both comulative and Single Event, on silicon detectors and microelectronic devices and systems. SIRAD is routinely used by various research groups involved in the development of semiconductor detectors and electronics to be used in radiation hostile environments as experiments at high-energy/high luminosity accelerators or in space, or interested to study the basic radiation damage mechanisms. Single Events Effects (SEE) studies with micrometric resolution can be performed at SIRAD thanks to an Ion Electron Emission Microscope (IEEM) inserted at the end of the beam line. Here we describe the SIRAD facility including the available and future beam characteristics, and the IEEM performances as well as the scientific and technological solutions which have been implemented for its construction.

  10. Upgrade to the Birmingham Irradiation Facility

    NASA Astrophysics Data System (ADS)

    Dervan, P.; French, R.; Hodgson, P.; Marin-Reyes, H.; Parker, K.; Wilson, J.; Baca, M.

    2015-10-01

    The Birmingham Irradiation Facility was developed in 2013 at the University of Birmingham using the Medical Physics MC40 cyclotron. It can achieve High Luminosity LHC (HL-LHC) fluences of 1015 (1 MeV neutron equivalent (neq)) cm-2 in 80 s with proton beam currents of 1 μA and so can evaluate effectively the performance and durability of detector technologies and new components to be used for the HL-LHC. Irradiations of silicon sensors and passive materials can be carried out in a temperature controlled cold box which moves continuously through the homogenous beamspot. This movement is provided by a pre-configured XY-axis Cartesian robot scanning system. In 2014 the cooling system and cold box were upgraded from a recirculating glycol chiller system to a liquid nitrogen evaporative system. The new cooling system achieves a stable temperature of -50 °C in 30 min and aims to maintain sub-0 °C temperatures on the sensors during irradiations. This paper reviews the design, development, commissioning and performance of the new cooling system.

  11. Computational analysis of irradiation facilities at the JSI TRIGA reactor.

    PubMed

    Snoj, Luka; Zerovnik, Gašper; Trkov, Andrej

    2012-03-01

    Characterization and optimization of irradiation facilities in a research reactor is important for optimal performance. Nowadays this is commonly done with advanced Monte Carlo neutron transport computer codes such as MCNP. However, the computational model in such calculations should be verified and validated with experiments. In the paper we describe the irradiation facilities at the JSI TRIGA reactor and demonstrate their computational characterization to support experimental campaigns by providing information on the characteristics of the irradiation facilities. PMID:22154389

  12. Standards for Community College Library Facilities.

    ERIC Educational Resources Information Center

    California State Postsecondary Education Commission, Sacramento.

    This report contains proposed standards for community college library facilities developed by the California Postsecondary Education Commission. Formulae for calculating stack space, staff space, reader station space, and total space are included in the report. Three alternative models for revising the present library standards were considered:…

  13. Spectral irradiance standard for the ultraviolet - The deuterium lamp

    NASA Technical Reports Server (NTRS)

    Saunders, R. D.; Ott, W. R.; Bridges, J. M.

    1978-01-01

    A set of deuterium lamps is calibrated as spectral irradiance standards in the 200-350-nm spectral region utilizing both a high accuracy tungsten spectral irradiance standard and a newly developed argon mini-arc spectral radiance standard. The method which enables a transfer from a spectral radiance to a spectral irradiance standard is described. The following characteristics of the deuterium lamp irradiance standard are determined: sensitivity to alignment; dependence on input power and solid angle; reproducibility; and stability. The absolute spectral radiance is also measured in the 167-330-nm region. Based upon these measurements, values of the spectral irradiance below 200 nm are obtained through extrapolation.

  14. DECOMMISSIONING THE BROOKHAVEN NATIONAL LABORATORY BUILDING 830 GAMMA IRRADIATION FACILITY.

    SciTech Connect

    BOWERMAN, B.S.; SULLIVAN, P.T.

    2001-08-13

    The Building 830 Gamma Irradiation Facility (GIF) at Brookhaven National Laboratory (BNL) was decommissioned because its design was not in compliance with current hazardous tank standards and its cobalt-60 sources were approaching the end of their useful life. The facility contained 354 stainless steel encapsulated cobalt-60 sources in a pool, which provided shielding. Total cobalt-60 inventory amounted to 24,000 Curies when the sources were shipped for disposal. The decommissioning project included packaging, transport, and disposal of the sources and dismantling and disposing of all other equipment associated with the facility. Worker exposure was a major concern in planning for the packaging and disposal of the sources. These activities were planned carefully according to ALARA (As Low As Reasonably Achievable) principles. As a result, the actual occupational exposures experienced during the work were within the planned levels. Disposal of the pool water required addressing environmental concerns, since the planned method was to discharge the slightly contaminated water to the BNL sewage treatment plant. After the BNL evaluation procedure for discharge to the sewage treatment plant was revised and reviewed by regulators and BNL's Community Advisory Council, the pool water was discharged to the Building 830 sanitary system. Because the sources were sealed and the pool water contamination levels were low, most of the remaining equipment was not contaminated; therefore disposal was straightforward, as scrap metal and construction debris.

  15. Experimental qualification of a code for optimizing gamma irradiation facilities

    NASA Astrophysics Data System (ADS)

    Mosse, D. C.; Leizier, J. J. M.; Keraron, Y.; Lallemant, T. F.; Perdriau, P. D. M.

    Dose computation codes are a prerequisite for the design of gamma irradiation facilities. Code quality is a basic factor in the achievement of sound economic and technical performance by the facility. This paper covers the validation of a code by reference dosimetry experiments. Developed by the "Société Générale pour les Techniques Nouvelles" (SGN), a supplier of irradiation facilities and member of the CEA Group, the code is currently used by that company. (ERHART, KERARON, 1986) Experimental data were obtained under conditions representative of those prevailing in the gamma irradiation of foodstuffs. Irradiation was performed in POSEIDON, a Cobalt 60 cell of ORIS-I. Several Cobalt 60 rods of known activity are arranged in a planar array typical of industrial irradiation facilities. Pallet density is uniform, ranging from 0 (air) to 0.6. Reference dosimetry measurements were performed by the "Laboratoire de Métrologie des Rayonnements Ionisants" (LMRI) of the "Bureau National de Métrologie" (BNM). The procedure is based on the positioning of more than 300 ESR/alanine dosemeters throughout the various target volumes used. The reference quantity was the absorbed dose in water. The code was validated by a comparison of experimental and computed data. It has proved to be an effective tool for the design of facilities meeting the specific requirements applicable to foodstuff irradiation, which are frequently found difficult to meet.

  16. The irradiation facility at the AGOR cyclotron

    NASA Astrophysics Data System (ADS)

    Brandenburg, Sytze; Ostendorf, Reint; Hofstee, Mariet; Kiewiet, Harry; Beijers, Hans

    2007-08-01

    The KVI is conducting radiobiology research using protons up to 190 MeV from the superconducting AGOR cyclotron in collaboration with the University Medical Center Groningen (UMCG) since 1998. Using the same set-up, we have started irradiations for radiation hardness studies of detectors and components for the European Space Agency (ESA) and industrial parties. For these irradiations, we use either mono-energetic protons or a simulated solar flare energy spectrum with fluxes up to 5 × 108 protons cm-2 s-1. Furthermore, tests of radiation effects such as single event upsets, are being performed with intensities down to a few particles/s. Different energies are achieved by degrading the primary beam energy. We are currently developing the capability for heavy ion irradiations in air with beams up to Xe at beam energies between 15 and 45 MeV per nucleon. Performing the irradiations in air simplifies handling and monitoring of the device under test. The high energy allows penetration to the active layer of electronic devices, without modifications to the chip housing. The different ions provide a wide range in LET.

  17. 40 CFR 279.52 - General facility standards.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false General facility standards. 279.52....52 General facility standards. (a) Preparedness and prevention. Owners and operators of used oil... operation of facility. Facilities must be maintained and operated to minimize the possibility of a...

  18. Standards Manual for Facilities Serving People with Disabilities.

    ERIC Educational Resources Information Center

    Commission on Accreditation of Rehabilitation Facilities, Tucson, AZ.

    The standards manual is intended for use in facility self-evaluation, planning of new facilities and organization of new programs, and in-service training. Standards are organized into three basic sections: standards for the organization (such as purpose, personnel administration and staff development, planning, and physical facilities and…

  19. RTNS-II fusion materials irradiation facility

    SciTech Connect

    Heikkinen, D.W.; Tuckerman, D.B.; Davis, J.C.; Massoletti, D.J.; Short, D.W.

    1986-01-01

    The Rotating Target Neutron Source (RTNS-II) facility provides an intense source of 14-MeV neutrons for the fusion energy programs of Japan and the United States. Each of the two identical accelerator-based neutron sources is capable of providing source strengths in excess of 3 x 10/sup 13/ n/s using deuteron beam currents up to 150 mA. The present status of the facility, as well as the various upgrade options, will be described in detail.

  20. Uniformity and standardization of single and opposing cobalt 60 sources for total body irradiation

    SciTech Connect

    Lam, W.C.; Order, S.E.; Thomas, E.D.

    1980-02-01

    The use of total body irradiation (TBI), chemotherapy, and allogeneic bone marrow transplantation in the management of relapsing leukemia has been established with dual source cobalt irradiation. In many facilities in order to reproduce the clinical results with single source irradiation, dosimetry must be compared under situations of varying configurations in order to standardize TBI techniques. Once intercomparison is achieved by on site dosimetric evaluation, recommendations are made for patient position, length of exposure in different positions and average thickness and beam data used to calculate absorbed dose. Homogeneity of single and opposing cobalt sources is also compared.

  1. SOUTH ELEVATION OF IRRADIATED FUEL STORAGE FACILITY LOCATED IN FUEL ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SOUTH ELEVATION OF IRRADIATED FUEL STORAGE FACILITY LOCATED IN FUEL STORAGE BUILDING (CPP-603). PHOTO TAKEN LOOKING NORTH. INL PHOTO NUMBER HD-54-15-2. Mike Crane, Photographer, 8/2005 - Idaho National Engineering Laboratory, Idaho Chemical Processing Plant, Fuel Reprocessing Complex, Scoville, Butte County, ID

  2. NORTH ELEVATION OF IRRADIATED FUEL STORAGE FACILITY LOCATED IN FUEL ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    NORTH ELEVATION OF IRRADIATED FUEL STORAGE FACILITY LOCATED IN FUEL STORAGE BUILDING (CPP-603). PHOTO TAKEN LOOKING SOUTH. INL PHOTO NUMBER HD-54-16-1. Mike Crane, Photographer, 8/2005 - Idaho National Engineering Laboratory, Idaho Chemical Processing Plant, Fuel Reprocessing Complex, Scoville, Butte County, ID

  3. Irradiation Facilities at the Advanced Test Reactor

    SciTech Connect

    S. Blaine Grover

    2005-12-01

    The Advanced Test Reactor (ATR) is the third generation and largest test reactor built in the Reactor Technology Complex (RTC – formerly known as the Test Reactor Area), located at the Idaho National Laboratory (INL), to study the effects of intense neutron and gamma radiation on reactor materials and fuels. The RTC was established in the early 1950s with the development of the Materials Testing Reactor (MTR), which operated until 1970. The second major reactor was the Engineering Test Reactor (ETR), which operated from 1957 to 1981, and finally the ATR, which began operation in 1967 and will continue operation well into the future. These reactors have produced a significant portion of the world’s data on materials response to reactor environments. The wide range of experiment facilities in the ATR and the unique ability to vary the neutron flux in different areas of the core allow numerous experiment conditions to co-exist during the same reactor operating cycle. Simple experiments may involve a non-instrumented capsule containing test specimens with no real-time monitoring or control capabilities1. More sophisticated testing facilities include inert gas temperature control systems and pressurized water loops that have continuous chemistry, pressure, temperature, and flow control as well as numerous test specimen monitoring capabilities. There are also apparatus that allow for the simulation of reactor transients on test specimens.

  4. The Advanced Test Reactor Irradiation Facilities and Capabilities

    SciTech Connect

    S. Blaine Grover; Raymond V. Furstenau

    2007-03-01

    The Advanced Test Reactor (ATR) is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. The ATR is a very versatile facility with a wide variety of experimental test capabilities for providing the environment needed in an irradiation experiment. These different capabilities include passive sealed capsule experiments, instrumented and/or temperature-controlled experiments, and pressurized water loop experiment facilities. The ATR has enhanced capabilities in experiment monitoring and control systems for instrumented and/or temperature controlled experiments. The control systems utilize feedback from thermocouples in the experiment to provide a custom blended flowing inert gas mixture to control the temperature in the experiments. Monitoring systems have also been utilized on the exhaust gas lines from the experiment to monitor different parameters, such as fission gases for fuel experiments, during irradiation. ATR’s unique control system provides axial flux profiles in the experiments, unperturbed by axially positioned control components, throughout each reactor operating cycle and over the duration of test programs requiring many years of irradiation. The ATR irradiation positions vary in diameter from 1.6 cm (0.625 inches) to 12.7 cm (5.0 inches) over an active core length of 122 cm (48.0 inches). Thermal and fast neutron fluxes can be adjusted radially across the core depending on the needs of individual test programs. This paper will discuss the different irradiation capabilities available and the cost/benefit issues related to each capability. Examples of different experiments will also be discussed to demonstrate the use of the capabilities and facilities at ATR for performing irradiation experiments.

  5. Defocusing beam line design for an irradiation facility at the TAEA SANAEM Proton Accelerator Facility

    NASA Astrophysics Data System (ADS)

    Gencer, A.; Demirköz, B.; Efthymiopoulos, I.; Yiğitoğlu, M.

    2016-07-01

    Electronic components must be tested to ensure reliable performance in high radiation environments such as Hi-Limu LHC and space. We propose a defocusing beam line to perform proton irradiation tests in Turkey. The Turkish Atomic Energy Authority SANAEM Proton Accelerator Facility was inaugurated in May 2012 for radioisotope production. The facility has also an R&D room for research purposes. The accelerator produces protons with 30 MeV kinetic energy and the beam current is variable between 10 μA and 1.2 mA. The beam kinetic energy is suitable for irradiation tests, however the beam current is high and therefore the flux must be lowered. We plan to build a defocusing beam line (DBL) in order to enlarge the beam size, reduce the flux to match the required specifications for the irradiation tests. Current design includes the beam transport and the final focusing magnets to blow up the beam. Scattering foils and a collimator is placed for the reduction of the beam flux. The DBL is designed to provide fluxes between 107 p /cm2 / s and 109 p /cm2 / s for performing irradiation tests in an area of 15.4 cm × 21.5 cm. The facility will be the first irradiation facility of its kind in Turkey.

  6. Facility for gamma irradiations of cultured cells at low dose rates: design, physical characteristics and functioning.

    PubMed

    Esposito, Giuseppe; Anello, Pasquale; Pecchia, Ilaria; Tabocchini, Maria Antonella; Campa, Alessandro

    2016-09-01

    We describe a low dose/dose rate gamma irradiation facility (called LIBIS) for in vitro biological systems, for the exposure, inside a CO2 cell culture incubator, of cells at a dose rate ranging from few μGy/h to some tens of mGy/h. Three different (137)Cs sources are used, depending on the desired dose rate. The sample is irradiated with a gamma ray beam with a dose rate uniformity of at least 92% and a percentage of primary 662keV photons greater than 80%. LIBIS complies with high safety standards. PMID:27423023

  7. The Irradiation Facility at the IBR-2M Reactor in Dubna

    NASA Astrophysics Data System (ADS)

    Bulavin, M.; Cheplakov, A.; Kulikov, S.; Kukhtin, V.; Shabalin, E.; Verhoglyadov, A.

    2014-06-01

    After renovation neutron pulsed reactor was successfully put into operation. In view of HL-LHC development, the irradiation facility at the IBR-2m, previously used for the ATLAS Liquid Argon calorimeters electronics and materials certification, has been upgraded to permit accumulation in the warm temperature conditions of the fast neutrons fluences up to k*1017 n/cm2 per one standard reactor operation cycle - 11 days. The first test of materials for ATLAS was conducted.

  8. The application of Sunna dosimeter film for process control at industrial gamma- and electron beam irradiation facilities

    NASA Astrophysics Data System (ADS)

    Kovács, A.; Baranyai, M.; Fuochi, P. G.; Lavalle, M.; Corda, U.; Miller, S.; Murphy, M.; O'Doherty, J.

    2004-09-01

    The Sunna dosimeter was introduced for dose determination in the dose range of 50-300 kGy by measuring optically stimulated luminescence. The usefulness of the dosimeter film has already been shown in food irradiation for routine process control. The aim of the present study was to check the performance of the Sunna dosimeter film for process control in radiation sterilization under industrial processing conditions, i.e. at high activity gamma irradiators and at high energy electron beam facilities. To ensure similar irradiation conditions during calibration and routine irradiation "in-plant calibration" was performed by irradiating the Sunna dosimeters together with ethanol-monochlorobenzene transfer standard and alanine reference standard dosimeters. The Sunna dosimeters were then irradiated together with the routine dosimeter of the actual plant during regular production runs and the absorbed doses measured by the different dosimeters agreed within ±2%(1 σ).

  9. The medical-irradiation characteristics for neutron capture therapy at the Heavy Water Neutron Irradiation Facility of Kyoto University Research Reactor.

    PubMed

    Sakurai, Yoshinori; Kobayashi, Tooru

    2002-10-01

    At the Heavy Water Neutron Irradiation Facility of the Kyoto University Research Reactor, the mix irradiation of thermal and epi-thermal neutrons, and the solo irradiation of epi-thermal neutrons are available additionally to the thermal neutron irradiation, and then the neutron capture therapy (NCT) at this facility became more flexible, after the update in 1996. The estimation of the depth dose distributions in NCT clinical irradiation, were performed for the standard irradiation modes of thermal, mixed and epi-thermal neutrons, from the both sides of experiment and calculation. On the assumption that the 10B concentration in tumor part was 40 ppm and the ratio of tumor to normal tissue was 3.5, the advantage depth were estimated to 5.4, 6.0, and 8.0, for the respective standard irradiation modes. It was confirmed that the various irradiation conditions can be selected according to the target-volume conditions, such as size, depth, etc. Besides, in the viewpoint of the radiation shielding for patient, it was confirmed that the whole-body exposure is effectively reduced by the new clinical collimators, compared with the old one. PMID:12408307

  10. 78 FR 16692 - Chemical Facility Anti-Terrorism Standards (CFATS)

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-18

    ..., Chemical Facility Anti-Terrorism Standards (CFATS) for an additional 30 days. \\1\\ See 77 FR 74677. The 60... mandate at 72 FR 17688. Section 550 of the Homeland Security Appropriations Act of 2007 requires a risk... SECURITY Chemical Facility Anti-Terrorism Standards (CFATS) AGENCY: National Protection and...

  11. Neutron irradiation facilities for fission and fusion reactor materials studies

    SciTech Connect

    Rowcliffe, A.F.

    1985-01-01

    The successful development of energy-conversion machines based upon nuclear fission or fusion reactors is critically dependent upon the behavior of the engineering materials used to construct the full containment and primary heat extraction systems. The development of radiation damage-resistant materials requires irradiation testing facilities which reproduce, as closely as possible, the thermal and neutronic environment expected in a power-producing reactor. The Oak Ridge National Laboratory (ORNL) reference core design for the Center for Neutron Research (CNR) reactor provides for instrumented facilities in regions of both hard and mixed neutron spectra, with substantially higher fluxes than are currently available. The benefits of these new facilities to the development of radiation damage resistant materials are discussed in terms of the major US fission and fusion reactor programs.

  12. Minimum criticality dose evaluation for the Irradiated Fuel Storage Facility

    SciTech Connect

    Kim, S.S.

    1999-09-01

    The Irradiated Fuel Storage Facility (IFSF) is a government-owned, contractor-operated facility located at the Idaho National Engineering and Environmental Laboratory within the Idaho Nuclear Technology and Engineering Center. The mission of the facility is to provide safe dry storage for various types of irradiated fuels. Included are fuel elements such as irradiated ATR, EBR, MTR, Fort St. Vrain, TRIGA, and ROVER Parka fuels. Fuels requiring dry storage are received at the IFSF in fuel-shipping casks. At the facility receiving dock, the casks are removed from the transport vehicle, positioned in a cask transport car, and moved into the fuel-handling cave. Several functions are performed in the fuel-handling cave, including transferring fuel from shipping casks to storage canisters, preparing fuel elements for storage and processing. The minimum postulated criticality dose calculations were performed for the cask-receiving and fuel-handling areas to place criticality alarm system (CAS) detectors. The number of fissions for the minimum accident of concern is based on a dose of 20-rad air at 2 m in 1 min. The eigenvalue calculations were first performed to determine the size of the critical source. Then, two sets of fixed-source calculations were followed to calculate contributions from neutron and capture gamma rays and from prompt gamma rays. Two sets of MCNP calculations involved point and spherical critical sources. Validity of the Monte Carlo results was tested against ANISN deterministic calculations. The flux-to-dose conversion factors are based on ANSI/ANS-6.1.1-1977. All of the MCNP runs used continuous-energy ENDF/B-V cross sections. The BUGLE-80 cross-section library was used for the ANISN calculations.

  13. Design Standards for School Art Facilities.

    ERIC Educational Resources Information Center

    National Art Education Association, Reston, VA.

    The National Art Education Association (NAEA) began work on this general planning reference for school art facilities in 1989, basing its initial draft on a survey of over 90 different groups, including school districts and state education agencies. The final publication represents the views of a broad-based constituency. Photographs of existing…

  14. Standards for Residential Facilities for the Mentally Retarded.

    ERIC Educational Resources Information Center

    Joint Commission on Accreditation of Hospitals, Chicago, IL.

    Presented are standards for residential facilities for the mentally retarded that were developed by the Joint Commission on Accreditation of Hospitals. The accreditation process is said to have two major objects: setting standards for services and determining the degree to which a specific services complies with the designated standards. The…

  15. Standards for Psychological Services in Long-Term Care Facilities.

    ERIC Educational Resources Information Center

    Morrow-Howell, Nancy; Lichtenberg, Peter A.; Smith, Michael; Frazer, Deborah; Molinari, Victor; Rosowsky, Erlene; Crose, Royda; Stillwell, Nick; Kramer, Nanette; Hartman-Stein, Paula; Qualls, Sara; Salamon, Michael; Duffy, Michael; Parr, Joyce; Gallagher-Thompson, Dolores

    1998-01-01

    Describes the development of standards for psychological practice in long-term care facilities. The standards, which were developed by Psychologists in Long-Term Care, address provider characteristics, methods of referral, assessment practices, treatment, and ethical issues. Offers suggestions for use of the standards. (MKA)

  16. 40 CFR 413.04 - Standards for integrated facilities.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 29 2011-07-01 2009-07-01 true Standards for integrated facilities. 413.04 Section 413.04 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS ELECTROPLATING POINT SOURCE CATEGORY General Provisions § 413.04 Standards...

  17. 75 FR 1552 - Chemical Facility Anti-Terrorism Standards

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-12

    ...-Terrorism Standards, 6 CFR Part 27 (CFATS), on April 9, 2007. See 72 FR 17688. The CFATS interim final rule... chemical facility. See generally 72 FR 17696, 17700-17701. DHS also has authority to determine that a... 6 CFR 27.105; 72 FR 17700-17701. The Department assigns each facility that is initially...

  18. 7 CFR 205.271 - Facility pest management practice standard.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ...) ORGANIC FOODS PRODUCTION ACT PROVISIONS NATIONAL ORGANIC PROGRAM Organic Production and Handling Requirements § 205.271 Facility pest management practice standard. (a) The producer or handler of an organic... habitat, food sources, and breeding areas; (2) Prevention of access to handling facilities; and...

  19. 7 CFR 205.271 - Facility pest management practice standard.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ...) ORGANIC FOODS PRODUCTION ACT PROVISIONS NATIONAL ORGANIC PROGRAM Organic Production and Handling Requirements § 205.271 Facility pest management practice standard. (a) The producer or handler of an organic... habitat, food sources, and breeding areas; (2) Prevention of access to handling facilities; and...

  20. Dosimetry in Thermal Neutron Irradiation Facility at BMRR

    SciTech Connect

    Hu, J. P.; Holden, N. E.; Reciniello, R. N.

    2014-05-23

    Radiation dosimetry for Neutron Capture Therapy (NCT) has been performed since 1959 at Thermal Neutron Irradiation Facility (TNIF) of the three-megawatt light-water cooled Brookhaven Medical Research Reactor (BMRR). In the early 1990s when more effective drug carriers were developed for NCT, in which the eye melanoma and brain tumors in rats were irradiated in situ, extensive clinical trials of small animals began using a focused thermal neutron beam. To improve the dosimetry at irradiation facility, a series of innovative designs and major modifications made to enhance the beam intensity and to ease the experimental sampling at BMRR were performed; including (1) in-core fuel addition to increase source strength and balance flux of neutrons towards two ports, (2) out of core moderator remodeling, done by replacing thicker D2O tanks at graphite-shutter interfacial areas, to expedite neutron thermalization, (3) beam shutter upgrade to reduce strayed neutrons and gamma dose, (4) beam collimator redesign to optimize the beam flux versus dose for animal treatment, (5) beam port shielding installation around the shutter opening area (lithium-6 enriched polyester-resin in boxes, attached with polyethylene plates) to reduce prompt gamma and fast neutron doses, (6) sample holder repositioning to optimize angle versus distance for a single organ or whole body irradiation, and (7) holder wall buildup with neutron reflector materials to increase dose and dose rate from scattered thermal neutrons. During the facility upgrade, reactor dosimetry was conducted using thermoluminescent dosimeters TLD for gamma dose estimate, using ion chambers to confirm fast neutron and gamma dose rate, and by the activation of gold-foils with and without cadmium-covers, for fast and thermal neutron flux determination. Based on the combined effect from the size and depth of tumor cells and the location and geometry of dosimeters, the measured flux from cadmium-difference method was 4 - 7

  1. Dosimetry in Thermal Neutron Irradiation Facility at BMRR

    NASA Astrophysics Data System (ADS)

    Hu, J.-P.; Holden, N. E.; Reciniello, R. N.

    2016-02-01

    Radiation dosimetry for Neutron Capture Therapy (NCT) has been performed since 1959 at Thermal Neutron Irradiation Facility (TNIF) of the three-megawatt light-water cooled Brookhaven Medical Research Reactor (BMRR). In the early 1990s when more effective drug carriers were developed for NCT, in which the eye melanoma and brain tumors in rats were irradiated in situ, extensive clinical trials of small animals began using a focused thermal neutron beam. To improve the dosimetry at irradiation facility, a series of innovative designs and major modifications made to enhance the beam intensity and to ease the experimental sampling at BMRR were performed; including (1) in-core fuel addition to increase source strength and balance flux of neutrons towards two ports, (2) out of core moderator remodeling, done by replacing thicker D2O tanks at graphite-shutter interfacial areas, to expedite neutron thermalization, (3) beam shutter upgrade to reduce strayed neutrons and gamma dose, (4) beam collimator redesign to optimize the beam flux versus dose for animal treatment, (5) beam port shielding installation around the shutter opening area (lithium-6 enriched polyester-resin in boxes, attached with polyethylene plates) to reduce prompt gamma and fast neutron doses, (6) sample holder repositioning to optimize angle versus distance for a single organ or whole body irradiation, and (7) holder wall buildup with neutron reflector materials to increase dose and dose rate from scattered thermal neutrons. During the facility upgrade, reactor dosimetry was conducted using thermoluminescent dosimeters TLD for gamma dose estimate, using ion chambers to confirm fast neutron and gamma dose rate, and by the activation of gold-foils with and without cadmium-covers, for fast and thermal neutron flux determination. Based on the combined effect from the size and depth of tumor cells and the location and geometry of dosimeters, the measured flux from cadmium-difference method was 4-7% lower than

  2. Characterization of nuclear transmutations in materials irradiated test facilities

    SciTech Connect

    Gomes, I.C.; Smith, D.L.

    1994-05-01

    This study presents a comparison of nuclear transmutation rates for candidate fusion first wall/blanket structural materials in available, fission test reactors with those produced in a typical fusion spectrum. The materials analyzed in this study include a vanadium alloy (V-4Cr-4Ti), a reduced activation martensitic steel (Fe-9Cr-2WVTa), a high conductivity copper alloy (Cu-Cr-Zr), and the SiC compound. The fission irradiation facilities considered include the EBR-II fast reactor, and two high flux mixed spectrum reactors, HFIR (High Flux Irradiation Reactor) and SM-3 (Russian reactor). The transmutation and dpa rates that occur in these test reactors are compared with the calculated transmutation and dpa rates characteristic of a D-T fusion first wall spectrum. In general, past work has shown that the displacement damage produced in these fission reactors can be correlated to displacement damage in a fusion spectrum; however, the generation of helium and hydrogen through threshold reactions [(n,x,{alpha}) and (n,xp)] are much higher in a fusion spectrum. As shown in this study, the compositional changes for several candidate structural materials exposed to a fast fission reactor spectrum are very low, similar to those for a characteristic fusion spectrum. However, the relatively high thermalized spectrum of a mixed spectrum reactor produces transmutation rates quite different from the ones predicted for a fusion reactor, resulting in substantial differences in the final composition of several candidate alloys after relatively short irradiation time.

  3. ACSM's Health/Fitness Facility Standards and Guidelines. Second Edition.

    ERIC Educational Resources Information Center

    Peterson, James A., Ed; Tharrett, Stephen J., Ed.

    The American College of Sports Medicine (ACSM) sets the industry standard for certifying professionals involved in health and fitness and their clinical applications. This 5-part publication provides a revised edition of six standards representing the industry's consensus on design and operation of a safe and high-quality health/fitness facility.…

  4. 40 CFR 279.52 - General facility standards.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... (CONTINUED) STANDARDS FOR THE MANAGEMENT OF USED OIL Standards for Used Oil Processors and Re-Refiners § 279...) An internal communications or alarm system capable of providing immediate emergency instruction... sprinklers, or water spray systems. (3) Testing and maintenance of equipment. All facility communications...

  5. 7 CFR 205.271 - Facility pest management practice standard.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 7 Agriculture 3 2011-01-01 2011-01-01 false Facility pest management practice standard. 205.271 Section 205.271 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE (CONTINUED) ORGANIC FOODS PRODUCTION ACT PROVISIONS...

  6. 7 CFR 205.271 - Facility pest management practice standard.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 7 Agriculture 3 2012-01-01 2012-01-01 false Facility pest management practice standard. 205.271 Section 205.271 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE (CONTINUED) ORGANIC FOODS PRODUCTION ACT PROVISIONS...

  7. Standards for Educational Facilities. An Annotated Reference List.

    ERIC Educational Resources Information Center

    Wakefield, Howard E.

    This annotated reference list was drawn from documents in the collection of the Clearinghouse on Educational Facilities, using the indexing terms "standards", and "state standards". The ERIC abstract is reprinted for each document selected. The range of the document covers a variety of areas including--(1) health and safety, (2) lighting, (3)…

  8. Fusion materials irradiation test facility test-cell instrumentation

    NASA Astrophysics Data System (ADS)

    Fuller, J. L.; Burke, R. J.

    1982-05-01

    Many of the facility instrumentation components and systems currently under development, though specifically designed for FMIT purposes, are similar to those useful for fusion reactors. Various ceramic-insulated signal-cable components are being evaluated for 14-MeV neutron tolerance. Thermocouples are shown to decalibrate in high energy fields. Nondestructive optical viewing of deuteron-induced residual gas flow is planned for beam profiling in real space and phase space. Various optics were irradiated to 10(18) n/cm(2) at 14 MeV with good results. Feasibility of neutron and gamma field imaging was demonstrated using pinhole collimator and microchannel plate devices. Infrared thermography and optical monitoring of the target surface is being investigated. Considerable experience on the compatibility of optical and insulator materials with (highly reactive) lithium was obtained.

  9. Gamma Irradiation Facility at Sandia National Laboratories, Albuquerque, New Mexico. Final environmental assessment

    SciTech Connect

    1995-11-01

    The US Department of Energy (DOE) has prepared an environmental assessment (EA) on the proposed construction and operation of a new Gamma Irradiation Facility (GIF) at Sandia National Laboratories/New Mexico (SNL/NM). This facility is needed to: enhance capabilities to assure technical excellence in nuclear weapon radiation environments testing, component development, and certification; comply with all applicable ES and H safeguards, standards, policies, and regulations; reduce personnel radiological exposure to comply with ALARA limits in accordance with DOE orders and standards; consolidate major gamma ray sources into a central, secured area; and reduce operational risks associated with operation of the GIF and LICA in their present locations. This proposed action provides for the design, construction, and operation of a new GIF located within TA V and the removal of the existing GIF and Low Intensity Cobalt Array (LICA). The proposed action includes potential demolition of the gamma shield walls and removal of equipment in the existing GIF and LICA. The shielding pool used by the existing GIF will remain as part of the ACRR facility. Transportation of the existing {sup 60}Co sources from the existing LICA and GIF to the new facility is also included in the proposed action. Relocation of the gamma sources to the new GIF will be accomplished by similar techniques to those used to install the sources originally.

  10. Accelerator-Based Biological Irradiation Facility Simulating Neutron Exposure from an Improvised Nuclear Device.

    PubMed

    Xu, Yanping; Randers-Pehrson, Gerhard; Turner, Helen C; Marino, Stephen A; Geard, Charles R; Brenner, David J; Garty, Guy

    2015-10-01

    We describe here an accelerator-based neutron irradiation facility, intended to expose blood or small animals to neutron fields mimicking those from an improvised nuclear device at relevant distances from the epicenter. Neutrons are generated by a mixed proton/deuteron beam on a thick beryllium target, generating a broad spectrum of neutron energies that match those estimated for the Hiroshima bomb at 1.5 km from ground zero. This spectrum, dominated by neutron energies between 0.2 and 9 MeV, is significantly different from the standard reactor fission spectrum, as the initial bomb spectrum changes when the neutrons are transported through air. The neutron and gamma dose rates were measured using a custom tissue-equivalent gas ionization chamber and a compensated Geiger-Mueller dosimeter, respectively. Neutron spectra were evaluated by unfolding measurements using a proton-recoil proportional counter and a liquid scintillator detector. As an illustration of the potential use of this facility we present micronucleus yields in single divided, cytokinesis-blocked human peripheral lymphocytes up to 1.5 Gy demonstrating 3- to 5-fold enhancement over equivalent X-ray doses. This facility is currently in routine use, irradiating both mice and human blood samples for evaluation of neutron-specific biodosimetry assays. Future studies will focus on dose reconstruction in realistic mixed neutron/photon fields. PMID:26414507

  11. 75 FR 2445 - Chemical Facility Anti-Terrorism Standards

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-15

    ... withdrawing the version of this document published in the Federal Register, at 75 FR 1552, on January 12, 2010...-Terrorism Standards, 6 CFR part 27 (CFATS), on April 9, 2007. See 72 FR 17688. The CFATS interim final rule... chemical facility. See generally 72 FR 17696, 17700-17701. DHS also has authority to determine that...

  12. Performance Evaluation Of An Irradiation Facility Using An Electron Accelerator

    NASA Astrophysics Data System (ADS)

    Uribe, R. M.; Filppi, E.; Hullihen, K.

    2011-06-01

    Irradiation parameters over a period of seven years have been evaluated for a radiation processing electron accelerator facility. The parameters monitored during this time were the electron beam energy, linearity of beam current, linearity of dose with the reciprocal value of the samples speed, and dose uniformity along the scanning area after a maintenance audit performed by the electron accelerator manufacturer. The electron energy was determined from the depth-dose curve by using a two piece aluminum wedge and measuring the practical range from the obtained curves. The linearity of dose with beam current, and reciprocal value of the speed and dose uniformity along the scanning area of the electron beam were determined by measuring the dose under different beam current and cart conveyor speed conditions using film dosimetry. The results of the experiments have shown that the energy in the range from 1 to 5 MeV has not changed by more than 15% from the High Voltage setting of the machine over the evaluation period, and dose linearity with beam current and cart conveyor speed has not changed. The dose uniformity along the scanning direction of the beam showed a dose uniformity of 90% or better for energies between 2 and 5 MeV, however for 1 MeV electrons this value was reduced to 80%. This parameter can be improved by changing the beam optics settings in the control console of the accelerator though.

  13. Present status of the liquid lithium target facility in the international fusion materials irradiation facility (IFMIF)

    NASA Astrophysics Data System (ADS)

    Nakamura, Hiroo; Riccardi, B.; Loginov, N.; Ara, K.; Burgazzi, L.; Cevolani, S.; Dell'Orco, G.; Fazio, C.; Giusti, D.; Horiike, H.; Ida, M.; Ise, H.; Kakui, H.; Matsui, H.; Micciche, G.; Muroga, T.; Nakamura, Hideo; Shimizu, K.; Sugimoto, M.; Suzuki, A.; Takeuchi, H.; Tanaka, S.; Yoneoka, T.

    2004-08-01

    During the three year key element technology phase of the International Fusion Materials Irradiation Facility (IFMIF) project, completed at the end of 2002, key technologies have been validated. In this paper, these results are summarized. A water jet experiment simulating Li flow validated stable flow up to 20 m/s with a double reducer nozzle. In addition, a small Li loop experiment validated stable Li flow up to 14 m/s. To control the nitrogen content in Li below 10 wppm will require surface area of a V-Ti alloy getter of 135 m 2. Conceptual designs of diagnostics have been carried out. Moreover, the concept of a remote handling system to replace the back wall based on `cut and reweld' and `bayonet' options has been established. Analysis by FMEA showed safe operation of the target system. Recent activities in the transition phase, started in 2003, and plan for the next phase are also described.

  14. University of Wisconsin Ion Beam Laboratory: A facility for irradiated materials and ion beam analysis

    SciTech Connect

    Field, K. G.; Wetteland, C. J.; Cao, G.; Maier, B. R.; Gerczak, T. J.; Kriewaldt, K.; Sridharan, K.; Allen, T. R.; Dickerson, C.; Field, C. R.

    2013-04-19

    The University of Wisconsin Ion Beam Laboratory (UW-IBL) has recently undergone significant infrastructure upgrades to facilitate graduate level research in irradiated materials phenomena and ion beam analysis. A National Electrostatics Corp. (NEC) Torodial Volume Ion Source (TORVIS), the keystone upgrade for the facility, can produce currents of hydrogen ions and helium ions up to {approx}200 {mu}A and {approx}5 {mu}A, respectively. Recent upgrades also include RBS analysis packages, end station developments for irradiation of relevant material systems, and the development of an in-house touch screen based graphical user interface for ion beam monitoring. Key research facilitated by these upgrades includes irradiation of nuclear fuels, studies of interfacial phenomena under irradiation, and clustering dynamics of irradiated oxide dispersion strengthened steels. The UW-IBL has also partnered with the Advanced Test Reactor National Scientific User Facility (ATR-NSUF) to provide access to the irradiation facilities housed at the UW-IBL as well as access to post irradiation facilities housed at the UW Characterization Laboratory for Irradiated Materials (CLIM) and other ATR-NSUF partner facilities. Partnering allows for rapid turnaround from proposed research to finalized results through the ATR-NSUF rapid turnaround proposal system. An overview of the UW-IBL including CLIM and relevant research is summarized.

  15. Standards Development Activities at White Sands Test Facility

    NASA Technical Reports Server (NTRS)

    Baker, D. L.; Beeson, H. D.; Saulsberry, R. L.; Julien, H. L.; Woods, S. S.

    2003-01-01

    The development of standards and standard activities at the JSC White Sands Test Facility (WSTF) has been expanded to include the transfer of technology and standards to voluntary consensus organizations in five technical areas of importance to NASA. This effort is in direct response to the National Technology Transfer Act designed to accelerate transfer of technology to industry and promote government-industry partnerships. Technology transfer is especially important for WSTF, whose longterm mission has been to develop and provide vital propellant safety and hazards information to aerospace designers, operations personnel, and safety personnel. Meeting this mission is being accomplished through the preparation of consensus guidelines and standards, propellant hazards analysis protocols, and safety courses for the propellant use of hydrogen, oxygen, and hypergols, as well as the design and inspection of spacecraft pressure vessels and the use of pyrovalves in spacecraft propulsion systems. The overall WSTF technology transfer program is described and the current status of technology transfer activities are summarized.

  16. DOE standard: Filter test facility quality program plan

    SciTech Connect

    1999-02-01

    This standard was developed primarily for application in US Department of Energy programs. It contains specific direction for HEPA filter testing performed at a DOE-accepted HEPA Filter Test Facility (FTF). Beneficial comments (recommendations, additions, deletions) and any pertinent data that may improve this document should be sent to the Office of Nuclear Safety Policy and Standards (EH-31), US Department of Energy, Washington, DC 20585, by letter or by using the self-addressed Document Improvement Proposal form (DOE F 1300.3) appearing at the end of this document.

  17. Development of Hydrocarbon Flow Calibration Facility as a National Standard

    NASA Astrophysics Data System (ADS)

    Shimada, Takashi; Doihara, Ryouji; Terao, Yoshiya; Takamoto, Masaki

    A new primary standard for hydrocarbon flow measurements has been constructed at National Metrology Institute of Japan (NMIJ). The facility was designed for the calibration of hydrocarbon flowmeters in the flow rate range between 3 and 300 m3/h. The expanded uncertainty is estimated to be 0.03 % for volumetric flow rate and 0.02 % for mass flow rate (coverage factor: k = 2). The primary standard is based on a static and gravimetric method with a flying start and finish. The facility consists of two test rigs using kerosene and light oil as working fluids. The test lines for the flowmeters are 50, 100 and 150 mm in diameter and three servo positive displacement meters are used as working standards. To verify the calibration performance, a Coriolis flowmeter, a turbine meter and a positive displacement flowmeter have been calibrated at both test rigs. Furthermore, an international comparison with SP, Swedish National Testing Research Institute, was carried out. A screw-type positive displacement flowmeter was selected as the transfer standard and was calibrated at NMIJ and SP. The result shows that the two national standards at the two institutes agree within the quoted expanded uncertainties.

  18. North Carolina Public Schools Facility Standards. A Guide for Planning School Facilities.

    ERIC Educational Resources Information Center

    Knott, Gerald H.; Lora, James M.; Acker, Marjorie L.; Taynton, Steven; Logan, Gladys B.; Harrell, Ronald C.

    The State of North Carolina has developed a planning guide for those in the process of building, enlarging, or renovating school facilities. This guide defines and describes the educational spaces needed to support a modern, comprehensive educational program and sets minimal standards for the types and sizes of spaces required. It serves as a…

  19. Single proton counting at the RIKEN cell irradiation facility

    SciTech Connect

    Mäckel, V. Puttaraksa, N.; Kobayashi, T.; Yamazaki, Y.

    2015-08-15

    We present newly developed tapered capillaries with a scintillator window, which enable us to count single protons at the RIKEN cell irradiation setup. Their potential for performing single proton irradiation experiments at our beamline setup is demonstrated with CR39 samples, showing a single proton detection fidelity of 98%.

  20. Developing a standard of practice while undergoing a facility merger.

    PubMed

    Derrick, J

    1993-01-01

    While the three facilities that eventually became Centennial Medical Center in Nashville were in the process of merging, it became necessary to merge all of the nursing policies and procedures to establish one standard of practice. Many areas of nursing are not accountable to the vice president of nursing, yet she is responsible for nursing standards of care and practice. To bring it all together, the author formed a council of all the chairs of the manual revision process; this council condensed 35 manuals to 19 manuals, developed historical files on all active and inactive policies, developed a flow chart for new policy manual assignments, and developed one standard of practice for the medical center. PMID:10124575

  1. Monte Carlo simulation for dose distribution calculations in a CT-based phantom at the Portuguese gamma irradiation facility

    NASA Astrophysics Data System (ADS)

    Oliveira, Carlos; Yoriyaz, Hélio; Oliveira, M. Carmo; Ferreira, L. M.

    2004-01-01

    In preview works the Portuguese Gamma Irradiation Facility, UTR, has been simulated using the MCNP code and the product to be irradiated has been drawn using the boolean operators with the MCNP surfaces. However, sometimes the product to be irradiated could have an irregular shape. The paper describes an alternative way for drawing the corresponding volume based on CT image data in a format of a 3D matrix of voxels. This data are read by a specific code called SCMS which transforms it into a MCNP input file. The dimensions of each MCNP voxel depend on the number of elements in the CT-based matrix. Additionally, the new approach allows one to know dose distributions anywhere without extra definitions of surfaces or volumes. Experimental dose measurements were carried out using Amber Perspex dosimeters. This work presents the results of MCNP simulations using both modeling modes - the standard mode and the voxel mode.

  2. Standardized treatment planning methodology for passively scattered proton craniospinal irradiation

    PubMed Central

    2013-01-01

    Background As the number of proton therapy centers increases, so does the need for studies which compare proton treatments between institutions and with photon therapy. However, results of such studies are highly dependent on target volume definition and treatment planning techniques. Thus, standardized methods of treatment planning are needed, particularly for proton treatment planning, in which special consideration is paid to the depth and sharp distal fall-off of the proton distribution. This study presents and evaluates a standardized method of proton treatment planning for craniospinal irradiation (CSI). Methods We applied our institution’s planning methodology for proton CSI, at the time of the study, to an anatomically diverse population of 18 pediatric patients. We evaluated our dosimetric results for the population as a whole and for the two subgroups having two different age-specific target volumes using the minimum, maximum, and mean dose values in 10 organs (i.e., the spinal cord, brain, eyes, lenses, esophagus, lungs, kidneys, thyroid, heart, and liver). We also report isodose distributions and dose-volume histograms (DVH) for 2 representative patients. Additionally we report population-averaged DVHs for various organs. Results The planning methodology here describes various techniques used to achieve normal tissue sparing. In particular, we found pronounced dose reductions in three radiosensitive organs (i.e., eyes, esophagus, and thyroid) which were identified for optimization. Mean doses to the thyroid, eyes, and esophagus were 0.2%, 69% and 0.2%, respectively, of the prescribed dose. In four organs not specifically identified for optimization (i.e., lungs, liver, kidneys, and heart) we found that organs lateral to the treatment field (lungs and kidneys) received relatively low mean doses (less than 8% of the prescribed dose), whereas the heart and liver, organs distal to the treatment field, received less than 1% of the prescribed dose

  3. 39 CFR 254.1 - Adoption of U.S. Access Board Standards as Postal Service Standards of Facility Accessibility.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Barriers Act (ABA) “Standards for Facility Accessibility,” the following sections of 36 CFR part 1191... 39 Postal Service 1 2012-07-01 2012-07-01 false Adoption of U.S. Access Board Standards as Postal Service Standards of Facility Accessibility. 254.1 Section 254.1 Postal Service UNITED STATES...

  4. 39 CFR 254.1 - Adoption of U.S. Access Board Standards as Postal Service Standards of Facility Accessibility.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Barriers Act (ABA) “Standards for Facility Accessibility,” the following sections of 36 CFR part 1191... 39 Postal Service 1 2014-07-01 2014-07-01 false Adoption of U.S. Access Board Standards as Postal Service Standards of Facility Accessibility. 254.1 Section 254.1 Postal Service UNITED STATES...

  5. 39 CFR 254.1 - Adoption of U.S. Access Board Standards as Postal Service Standards of Facility Accessibility.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... Barriers Act (ABA) “Standards for Facility Accessibility,” the following sections of 36 CFR part 1191... 39 Postal Service 1 2013-07-01 2013-07-01 false Adoption of U.S. Access Board Standards as Postal Service Standards of Facility Accessibility. 254.1 Section 254.1 Postal Service UNITED STATES...

  6. 41 CFR 102-74.165 - What energy standards must Federal agencies follow for existing facilities?

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 41 Public Contracts and Property Management 3 2014-01-01 2014-01-01 false What energy standards... REGULATION REAL PROPERTY 74-FACILITY MANAGEMENT Facility Management Energy Conservation § 102-74.165 What energy standards must Federal agencies follow for existing facilities? Existing Federal facilities...

  7. 41 CFR 102-74.165 - What energy standards must Federal agencies follow for existing facilities?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 41 Public Contracts and Property Management 3 2013-07-01 2013-07-01 false What energy standards... REGULATION REAL PROPERTY 74-FACILITY MANAGEMENT Facility Management Energy Conservation § 102-74.165 What energy standards must Federal agencies follow for existing facilities? Existing Federal facilities...

  8. 36 CFR Appendix A to Part 1234 - Minimum Security Standards for Level III Federal Facilities

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 36 Parks, Forests, and Public Property 3 2014-07-01 2014-07-01 false Minimum Security Standards... FACILITIES Pt. 1234, App. A Appendix A to Part 1234—Minimum Security Standards for Level III Federal Facilities Recommended Standards Chart Level III Perimeter Security Parking: Control of facility...

  9. Evaluation of irradiation facility options for fusion materials research and development

    SciTech Connect

    Zinkle, Steven J; Möslang, Anton

    2013-01-01

    Successful development of fusion energy will require the design of high-performance structural materials that exhibit dimensional stability and good resistance to fusion neutron degradation of mechanical and physical properties. The high levels of gaseous (H, He) transmutation products associated with deuterium-tritium (D-T) fusion neutron transmutation reactions, along with displacement damage dose requirements up to 50-200 displacements per atom (dpa) for a fusion demonstration reactor (DEMO), pose an extraordinary challenge. The intense neutron source(s) is needed to address two complimentary missions: 1) Scientific investigations of radiation degradation phenomena and microstructural evolution under fusion-relevant irradiation conditions (to provide the foundation for designing improved radiation resistant materials), and 2) Engineering database development for design and licensing of next-step fusion energy machines such as a fusion DEMO. A wide variety of irradiation facilities have been proposed to investigate materials science phenomena and to test and qualify materials for a DEMO reactor. Currently available and proposed facilities include fission reactors (including isotopic and spectral tailoring techniques to modify the rate of H and He production per dpa), dual- and triple-ion accelerator irradiation facilities that enable greatly accelerated irradiation studies with fusion-relevant H and He production rates per dpa within microscopic volumes, D-Li stripping reaction and spallation neutron sources, and plasma-based sources. The advantages and limitations of the main proposed fusion materials irradiation facility options are reviewed. Evaluation parameters include irradiation volume, potential for performing accelerated irradiation studies, capital and operating costs, similarity of neutron irradiation spectrum to fusion reactor conditions, temperature and irradiation flux stability/control, ability to perform multiple-effect tests (e.g., irradiation in

  10. Proton Irradiation Facility and space radiation monitoring at the Paul Scherrer Institute.

    PubMed

    Hajdas, W; Zehnder, A; Adams, L; Buehler, P; Harboe-Sorensen, R; Daum, M; Nickson, R; Daly, E; Nieminen, P

    2001-01-01

    The Proton Irradiation Facility (PIF) has been designed and constructed, in cooperation between Paul Scherrer Institute (PSI) and European Space Agency (ESA), for terrestrial proton testing of components and materials for spacecraft. Emphasis has been given to generating realistic proton spectra encountered by space-flights at any potential orbit. The facility, designed in a user-friendly manner, can be readily adapted to the individual requirements of experimenters. It is available for general use serving also in testing of radiation monitors and for proton experiments in different scientific disciplines. The Radiation Environment Monitor REM has been developed for measurements of the spacecraft radiation conditions. Two instruments were launched into space, one into a Geo-stationary Transfer Orbit on board of the STRV-1b satellite and one into a Low Earth Orbit on the Russian MIR station. The next generation of monitors (SREMs--Standard REMs) is currently under development in partnership of ESA, PSI and Contraves-Space. They will operate both as minimum intrusive monitors, which provide radiation housekeeping data and alert the spacecraft when the radiation level crosses allowed limits and as small scientific devices measuring particle spectra and fluxes. Future missions as e.g. INTEGRAL, STRV-1c and PROBA will be equipped with new SREMs. PMID:11770526

  11. A facility for studying irradiation accelerated corrosion in high temperature water

    NASA Astrophysics Data System (ADS)

    Raiman, Stephen S.; Flick, Alexander; Toader, Ovidiu; Wang, Peng; Samad, Nassim A.; Jiao, Zhijie; Was, Gary S.

    2014-08-01

    A facility for the study of irradiation accelerated corrosion in high temperature water using in situ proton irradiation has been developed and validated. A specially designed beamline and flowing-water corrosion cell added to the 1.7 MV tandem accelerator at the Michigan Ion Beam Laboratory provide the capability to study the simultaneous effects of displacement damage and radiolysis on corrosion. A thin sample serves as both a “window” into the corrosion cell through which the proton beam passes completely, and the sample for assessing irradiation accelerated corrosion. The facility was tested by irradiating stainless steel samples at beam current densities between 0.5 and 10 μA/cm2 in 130 °C and 320 °C deaerated water, and 320 °C water with 3 wppm H2. Increases in the conductivity and dissolved oxygen content of the water varied with the proton beam current, suggesting that proton irradiation was accelerating the corrosion of the sample. Conductivity increases were greatest at 320 °C, while DO increases were highest at 130 °C. The addition of 3 wppm H2 suppressed DO below detectable levels. The facility will enable future studies into the effect of irradiation on corrosion in high temperature water with in situ proton irradiation.

  12. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1: Technical standard

    SciTech Connect

    1998-05-01

    This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities.

  13. Hanford Site existing irradiated fuel storage facilities description

    SciTech Connect

    Willis, W.L.

    1995-01-11

    This document describes facilities at the Hanford Site which are currently storing spent nuclear fuels. The descriptions provide a basis for the no-action alternatives of ongoing and planned National Environmental Protection Act reviews.

  14. A proton irradiation test facility for space research in Ankara, Turkey

    NASA Astrophysics Data System (ADS)

    Gencer, Ayşenur; Yiǧitoǧlu, Merve; Bilge Demirköz, Melahat; Efthymiopoulos, Ilias

    2016-07-01

    Space radiation often affects the electronic components' performance during the mission duration. In order to ensure reliable performance, the components must be tested to at least the expected dose that will be received in space, before the mission. Accelerator facilities are widely used for such irradiation tests around the world. Turkish Atomic Energy Authority (TAEA) has a 15MeV to 30MeV variable proton cyclotron in Ankara and the facility's main purpose is to produce radioisotopes in three different rooms for different target systems. There is also an R&D room which can be used for research purposes. This paper will detail the design and current state of the construction of a beamline to perform Single Event Effect (SEE) tests in Ankara for the first time. ESA ESCC No.25100 Standard Single Event Effect Test Method and Guidelines is being considered for these SEE tests. The proton beam kinetic energy must be between 20MeV and 200MeV according to the standard. While the proton energy is suitable for SEE tests, the beam size must be 15.40cm x 21.55cm and the flux must be between 10 ^{5} p/cm ^{2}/s to at least 10 ^{8} p/cm ^{2}/s according to the standard. The beam size at the entrance of the R&D room is mm-sized and the current is variable between 10μA and 1.2mA. Therefore, a defocusing beam line has been designed to enlarge the beam size and reduce the flux value. The beam line has quadrupole magnets to enlarge the beam size and the collimators and scattering foils are used for flux reduction. This facility will provide proton fluxes between 10 ^{7} p/cm ^{2}/s and 10 ^{10} p/cm ^{2}/s for the area defined in the standard when completed. Also for testing solar cells developed for space, the proton beam energy will be lowered below 10MeV. This project has been funded by Ministry of Development in Turkey and the beam line construction will finish in two years and SEE tests will be performed for the first time in Turkey.

  15. First multicharged ion irradiation results from the CUEBIT facility at Clemson University

    SciTech Connect

    Shyam, R.; Kulkarni, D. D.; Field, D. A.; Srinadhu, E. S.; Harriss, J. E.; Cutshall, D. B.; Harrell, W. R.; Sosolik, C. E.

    2015-01-09

    A new electron beam ion trap (EBIT) based ion source and beamline were recently commissioned at Clemson University to produce decelerated beams of multi- to highly-charged ions for surface and materials physics research. This user facility is the first installation of a DREEBIT-designed superconducting trap and ion source (EBIS-SC) in the U.S. and includes custom-designed target preparation and irradiation setups. An overview of the source, beamline, and other facilities as well as results from first measurements on irradiated targets are discussed here. Results include extracted charge state distributions and first data on a series of irradiated metal-oxide-semiconductor (MOS) device targets. For the MOS devices, we show that voltage-dependent capacitance can serve as a record of the electronic component of ion stopping power for an irradiated, encapsulated oxide target.

  16. Present status of the medical irradiation facility at the Musashi reactor

    SciTech Connect

    Matsumoto, T.; Aizawa, O.; Nozaki, T.; Sato, T. )

    1989-07-01

    Boron neutron capture therapy (BNCT) of malignant brain tumors has been efficiently performed since March 1977, and the first human case of malignant melanoma was also successfully treated on July 1987 in our reactor (Musashi reactor, TRIGA-II, 100 kW). To obtain both good irradiation field characteristics and a better irradiation facility, some tests and developments have been continued in accordance with the study of medical and biological irradiations. The results of these evaluations and a new approach are presented.6 references.

  17. Design and characterization of an irradiation facility with real-time monitoring

    NASA Astrophysics Data System (ADS)

    Braisted, Jonathan David

    Radiation causes performance degradation in electronics by inducing atomic displacements and ionizations. While radiation hardened components are available, non-radiation hardened electronics can be preferable because they are generally more compact, require less power, and less expensive than radiation tolerant equivalents. It is therefore important to characterize the performance of electronics, both hardened and non-hardened, to prevent costly system or mission failures. Radiation effects tests for electronics generally involve a handful of step irradiations, leading to poorly-resolved data. Step irradiations also introduce uncertainties in electrical measurements due to temperature annealing effects. This effect may be intensified if the time between exposure and measurement is significant. Induced activity in test samples also complicates data collection of step irradiated test samples. The University of Texas at Austin operates a 1.1 MW Mark II TRIGA research reactor. An in-core irradiation facility for radiation effects testing with a real-time monitoring capability has been designed for the UT TRIGA reactor. The facility is larger than any currently available non-central location in a TRIGA, supporting testing of larger electronic components as well as other in-core irradiation applications requiring significant volume such as isotope production or neutron transmutation doping of silicon. This dissertation describes the design and testing of the large in-core irradiation facility and the experimental campaign developed to test the real-time monitoring capability. This irradiation campaign was performed to test the real-time monitoring capability at various reactor power levels. The device chosen for characterization was the 4N25 general-purpose optocoupler. The current transfer ratio, which is an important electrical parameter for optocouplers, was calculated as a function of neutron fluence and gamma dose from the real-time voltage measurements. The

  18. New irradiation facility for biomedical applications at the RA-3 reactor thermal column.

    PubMed

    Miller, M; Quintana, J; Ojeda, J; Langan, S; Thorp, S; Pozzi, E; Sztejnberg, M; Estryk, G; Nosal, R; Saire, E; Agrazar, H; Graiño, F

    2009-07-01

    A new irradiation facility has been developed in the RA-3 reactor in order to perform trials for the treatment of liver metastases using boron neutron capture therapy (BNCT). RA-3 is a production research reactor that works continuously five days a week. It had a thermal column with a small cross section access tunnel that was not accessible during operation. The objective of the work was to perform the necessary modifications to obtain a facility for irradiating a portion of the human liver. This irradiation facility must be operated without disrupting the normal reactor schedule and requires a highly thermalized neutron spectrum, a thermal flux of around 10(10) n cm(-2)s(-1) that is as isotropic and uniform as possible, as well as on-line instrumentation. The main modifications consist of enlarging the access tunnel inside the thermal column to the suitable dimensions, reducing the gamma dose rate at the irradiation position, and constructing properly shielded entrance gates enabled by logical control to safely irradiate and withdraw samples with the reactor at full power. Activation foils and a neutron shielded graphite ionization chamber were used for a preliminary in-air characterization of the irradiation site. The constructed facility is very practical and easy to use. Operational authorization was obtained from radioprotection personnel after confirming radiation levels did not significantly increase after the modification. A highly thermalized and homogenous irradiation field was obtained. Measurements in the empty cavity showed a thermal flux near 10(10) n cm(-2)s(-1), a cadmium ratio of 4100 for gold foils and a gamma dose rate of approximately 5 Gy h(-1). PMID:19406651

  19. 36 CFR Appendix A to Part 1234 - Minimum Security Standards for Level III Federal Facilities

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 36 Parks, Forests, and Public Property 3 2012-07-01 2012-07-01 false Minimum Security Standards for Level III Federal Facilities A Appendix A to Part 1234 Parks, Forests, and Public Property NATIONAL ARCHIVES AND RECORDS ADMINISTRATION RECORDS MANAGEMENT FACILITY STANDARDS FOR RECORDS STORAGE FACILITIES Pt. 1234, App. A Appendix A to Part...

  20. Neutron flux assessment of a neutron irradiation facility based on inertial electrostatic confinement fusion.

    PubMed

    Sztejnberg Gonçalves-Carralves, M L; Miller, M E

    2015-12-01

    Neutron generators based on inertial electrostatic confinement fusion were considered for the design of a neutron irradiation facility for explanted organ Boron Neutron Capture Therapy (BNCT) that could be installed in a health care center as well as in research areas. The chosen facility configuration is "irradiation chamber", a ~20×20×40 cm(3) cavity near or in the center of the facility geometry where samples to be irradiated can be placed. Neutron flux calculations were performed to study different manners for improving scattering processes and, consequently, optimize neutron flux in the irradiation position. Flux distributions were assessed through numerical simulations of several models implemented in MCNP5 particle transport code. Simulation results provided a wide spectrum of combinations of net fluxes and energy spectrum distributions. Among them one can find a group that can provide thermal neutron fluxes per unit of production rate in a range from 4.1·10(-4) cm(-2) to 1.6·10(-3) cm(-2) with epithermal-to-thermal ratios between 0.3% and 13% and fast-to-thermal ratios between 0.01% to 8%. Neutron generators could be built to provide more than 10(10) n s(-1) and, consequently, with an arrangement of several generators appropriate enough neutron fluxes could be obtained that would be useful for several BNCT-related irradiations and, eventually, for clinical practice. PMID:26122974

  1. The Advanced Test Reactor Irradiation Capabilities Available as a National Scientific User Facility

    SciTech Connect

    S. Blaine Grover

    2008-09-01

    The Advanced Test Reactor (ATR) is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. The ATR is a very versatile facility with a wide variety of experimental test capabilities for providing the environment needed in an irradiation experiment. These capabilities include simple capsule experiments, instrumented and/or temperature-controlled experiments, and pressurized water loop experiment facilities. Monitoring systems have also been utilized to monitor different parameters such as fission gases for fuel experiments, to measure specimen performance during irradiation. ATR’s control system provides a stable axial flux profile throughout each reactor operating cycle, and allows the thermal and fast neutron fluxes to be controlled separately in different sections of the core. The ATR irradiation positions vary in diameter from 16 mm to 127 mm over an active core height of 1.2 m. This paper discusses the different irradiation capabilities with examples of different experiments and the cost/benefit issues related to each capability. The recent designation of ATR as a national scientific user facility will make the ATR much more accessible at very low to no cost for research by universities and possibly commercial entities.

  2. Irradiation facility at the IBR-2 reactor for investigation of material radiation hardness

    NASA Astrophysics Data System (ADS)

    Bulavin, M.; Cheplakov, A.; Kukhtin, V.; Kulagin, E.; Kulikov, S.; Shabalin, E.; Verkhoglyadov, A.

    2015-01-01

    Description of the irradiation facility and available parameters of the neutron and gamma exposures including the maximal integrated doses are presented in the paper. The research capabilities for radiation hardness tests of materials in high intensity beam of fast neutrons at the IBR-2 reactor of the Joint Institute for Nuclear Research in Dubna (Russia) are outlined.

  3. Irradiation facility at the IBR-2 reactor for investigating material radiation hardness

    NASA Astrophysics Data System (ADS)

    Bulavin, M. V.; Verkhoglyadov, A. E.; Kulikov, S. A.; Kulagin, E. N.; Kukhtin, V. V.; Cheplakov, A. P.; Shabalin, E. P.

    2015-03-01

    A description of the irradiation facility and available parameters of neutron and gamma exposures, including the maximum integrated doses, are presented in the paper. The research capabilities for radiation hardness tests of materials in a high-intensity beam of fast neutrons at the IBR-2 reactor of the Joint Institute for Nuclear Research in Dubna (Russia) are outlined.

  4. The contract facilities for gamma irradiation at Dagneux, France

    NASA Astrophysics Data System (ADS)

    Pellerin, D.; Kavanagh, M. T.

    CONSERVATOME SA have operated a facility at DAGNEUX near LYON, France since 1961. This operation is among the very first of its kind in the entire world. The process is based on gamma rays from Cobalt 60 of which there are three separate units. In addition there is a small experimental unit using Cesium 137. At present CONSERVATOME is owned by TRANSNUCLEAIRE and EPICEA as principal shareholders and so has the support of the French Atomic Energy Commission. This paper describes the larger D3 unit and reviews some of the products treated at DAGNEUX.

  5. Improvement of the High Fluence Irradiation Facility at the University of Tokyo

    NASA Astrophysics Data System (ADS)

    Murakami, Kenta; Iwai, Takeo; Abe, Hiroaki; Sekimura, Naoto

    2016-08-01

    This paper reports the modification of the High Fluence Irradiation Facility at the University of Tokyo (HIT). The HIT facility was severely damaged during the 2011 earthquake, which occurred off the Pacific coast of Tohoku. A damaged 1.0 MV tandem Cockcroft-Walton accelerator was replaced with a 1.7 MV accelerator, which was formerly used in another campus of the university. A decision was made to maintain dual-beam irradiation capability by repairing the 3.75 MV single-ended Van de Graaff accelerator and reconstructing the related beamlines. A new beamline was connected with a 200 kV transmission electron microscope (TEM) to perform in-situ TEM observation under ion irradiation.

  6. 36 CFR Appendix A to Part 1234 - Minimum Security Standards for Level III Federal Facilities

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 36 Parks, Forests, and Public Property 3 2013-07-01 2012-07-01 true Minimum Security Standards for.... 1234, App. A Appendix A to Part 1234—Minimum Security Standards for Level III Federal Facilities Recommended Standards Chart Level III Perimeter Security Parking: Control of facility parking...

  7. Standardization of DOE Disposal Facilities Waste Acceptance Processes

    SciTech Connect

    Shrader, T. A.; Macbeth, P. J.

    2002-02-26

    On February 25, 2000, the U.S. Department of Energy (DOE) issued the Record of Decision (ROD) for the Waste Management Programmatic Environmental Impact Statement (WM PEIS) for low-level and mixed low-level wastes (LLW/ MLLW) treatment and disposal. The ROD designated the disposal sites at Hanford and the Nevada Test Site (NTS) to dispose of LLW/MLLW from sites without their own disposal facilities. DOE's Richland Operations Office (RL) and the National Nuclear Security Administration's Nevada Operations Office (NV) have been charged with effectively implementing the ROD. To accomplish this task NV and RL, assisted by their operating contractors Bechtel Nevada (BN), Fluor Hanford (FH), and Bechtel Hanford (BH) assembled a task team to systematically map out and evaluate the current waste acceptance processes and develop an integrated, standardized process for the acceptance of LLW/MLLW. A structured, systematic, analytical process using the Six Sigma system identified dispos al process improvements and quantified the associated efficiency gains to guide changes to be implemented. The review concluded that a unified and integrated Hanford/NTS Waste Acceptance Process would be a benefit to the DOE Complex, particularly the waste generators. The Six Sigma review developed quantitative metrics to address waste acceptance process efficiency improvements, and provides an initial look at development of comparable waste disposal cost models between the two disposal sites to allow quantification of the proposed improvements.

  8. Standardization of DOE Disposal Facilities Waste Acceptance Process

    SciTech Connect

    SHRADER, T.; MACBETH, P.

    2002-01-01

    On February 25, 2000, the US. Department of Energy (DOE) issued the Record of Decision (ROD) for the Waste Management Programmatic Environmental Impact Statement (WM PEIS) for low-level and mixed low-level wastes (LLW/ MLLW) treatment and disposal. The ROD designated the disposal sites at Hanford and the Nevada Test Site (NTS) to dispose of LLWMLLW from sites without their own disposal facilities. DOE's Richland Operations Office (RL) and the National Nuclear Security Administration's Nevada Operations Office (NV) have been charged with effectively implementing the ROD. To accomplish this task NV and RL, assisted by their operating contractors Bechtel Nevada (BN), Fluor Hanford (FH), and Bechtel Hanford (BH) assembled a task team to systematically map out and evaluate the current waste acceptance processes and develop an integrated, standardized process for the acceptance of LLWMLLW. A structured, systematic, analytical process using the Six Sigma system identified disposal process improvements and quantified the associated efficiency gains to guide changes to be implemented. The review concluded that a unified and integrated Hanford/NTS Waste Acceptance Process would be a benefit to the DOE Complex, particularly the waste generators. The Six Sigma review developed quantitative metrics to address waste acceptance process efficiency improvements, and provides an initial look at development of comparable waste disposal cost models between the two disposal sites to allow quantification of the proposed improvements.

  9. "Toward the development of a diffuse horizontal shortwave irradiance working standard"

    SciTech Connect

    J. Michalsky; R. Dolce; E.G. Dutton; M. Haeffelin; W. Jeffries; T. Stoffel; J. Hickey; A. Los; D. Mathias; L.J.B. McArthur; D. Nelson; R. Philipona; I. Reda; K. Rutledge; G. Zerlaut; B. Forgan; P. Kiedron; C. Long; and C. Gueymard

    2005-04-01

    The first intensive observation period (IOP) to simultaneously measure diffuse horizontal shortwave irradiance (scattered solar radiation that falls on a horizontal surface) with a wide array of shaded pyranometers suggested that a consensus might be reached that would permit the establishment of a standard with a smaller uncertainty than previously achieved. A second IOP has been held to refine the first IOP measurements using a uniform calibration protocol, offset corrections for all instruments and validation of those corrections, improvements in some of the instruments, and better data acquisition. The venue for both IOPs was the Department of Energy's Atmospheric Radiation Measurement (ARM) central facility in northern Oklahoma. The nine days of measurements in October 2003 included a better mixture of clear and overcast conditions than during the first IOP and revealed considerable differences among the instruments responses for different cloud conditions. Four of the 15 instruments were eliminated as candidates to be included in the standard because of noisy signals, inadequate offset correction, or instability with respect to the majority of the measurements. Eight pyranometers agreed to within {+-}2% for clear-sky conditions. Three others have a high bias on clear days relative to these eight, but all eleven agree within {+-}2% on overcast days. The differences and causes of this behavior under clear and cloudy skies are examined.

  10. SATIF-2 shielding aspects of accelerators, targets and irradiation facilities

    SciTech Connect

    1995-12-31

    Particle accelerators have evolved over the last 50 years from simple devices to powerful machines, and will continue to have an important impact on research, technology and lifestyle. Today they cover a wide range of applications, from television and computer displays in households to the investigation of the origin and structure of matter. It has become common practice to use them for material science and medical applications. In recent years, requirements from new technological and research applications have emerged, such as increased particle beams intensities, higher flexibility, etc., giving rise to new radiation shielding aspects and problems. These proceedings review recent progress in radiation shielding of accelerator facilities, and evaluate advancements with respect to international co-operation in this field.

  11. LLNL Fire Protection Engineering Standard 5.8 Facility Survey Program

    SciTech Connect

    Sharry, J A

    2012-01-04

    This standard describes the LLNL Fire Protection Facility Survey Program. The purpose of this standard is to describe the type of facility surveys required to fulfill the requirements of DOE Order 420.1B, Facility Safety. Nothing in this standard is intended to prevent the development of a FHA using alternative approaches. Alternate approaches, including formatting, will be by exception only, and approved by the Fire Marshal/Fire Protection Engineering Subject Matter Expert in advance of their use.

  12. 39 CFR 254.1 - Adoption of U.S. Access Board Standards as Postal Service Standards of Facility Accessibility.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Barriers Act (ABA) “Standards for Facility Accessibility,” the following sections of 36 CFR part 1191: Appendix A to Part 1191, Table of Contents for apps. C, D, and E. Appendix C to Part 1191,...

  13. Design of an irradiation facility with a real-time radiation effects monitoring capability

    NASA Astrophysics Data System (ADS)

    Braisted, J.; Schneider, E.; O'Kelly, S.; van der Hoeven, C.

    2011-12-01

    An in-core irradiation facility for radiation effects testing with a real-time monitoring capability has been designed for the 1.1 MW TRIGA Mark II research reactor at The University of Texas at Austin. The facility is larger than any currently available non-central location in a TRIGA, supporting testing of larger electronic components as well as other in-core irradiation applications requiring significant volume such as isotope production or neutron transmutation doping of silicon. This article presents the layout and characterization of the large in-core irradiation facility and the real-time electronics performance monitoring capability it is designed to support. To demonstrate this capability, an experimental campaign was conducted where the real-time current transfer ratio for 4N25 general-purpose optocouplers was obtained from in-situ voltage measurements. The resultant radiation effects data - current transfer ratio as a function of neutron and gamma dose - was seen to be repeatable and exceptionally finely resolved. Therefore, the real-time capability at UT TRIGA appears competitive with other effects characterization facilities in terms of number and size of testable samples while additionally offering a novel real-time, in-core monitoring capability.

  14. 40 CFR 279.52 - General facility standards.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... occur, recur, or spread to other used oil or hazardous waste at the facility. These measures must... area(s) of the facility: (A) No waste or used oil that may be incompatible with the released material... Section 279.52 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID...

  15. 40 CFR 279.52 - General facility standards.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... occur, recur, or spread to other used oil or hazardous waste at the facility. These measures must... area(s) of the facility: (A) No waste or used oil that may be incompatible with the released material... Section 279.52 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID...

  16. High School Educational Specifications: Facilities Planning Standards. Edition I.

    ERIC Educational Resources Information Center

    Jefferson County School District R-1, Denver, CO.

    The Jefferson County School District (Colorado) has developed a manual of high school specifications for Design Advisory Groups and consultants to use for planning and designing the district's high school facilities. The specifications are provided to help build facilities that best meet the educational needs of the students to be served.…

  17. 40 CFR 63.471 - Facility-wide standards.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... engineering calculations included in the compliance report. (4) Each owner or operator of an affected facility... submit an initial notification report to the Administrator no later than May 3, 2010. This report shall... operator of an affected facility shall submit a solvent emission report every year. This solvent...

  18. Characterization of the neutron irradiation system for use in the Low-Dose-Rate Irradiation Facility at Sandia National Laboratories.

    SciTech Connect

    Franco, Manuel,

    2014-08-01

    The objective of this work was to characterize the neutron irradiation system consisting of americium-241 beryllium (241AmBe) neutron sources placed in a polyethylene shielding for use at Sandia National Laboratories (SNL) Low Dose Rate Irradiation Facility (LDRIF). With a total activity of 0.3 TBq (9 Ci), the source consisted of three recycled 241AmBe sources of different activities that had been combined into a single source. The source in its polyethylene shielding will be used in neutron irradiation testing of components. The characterization of the source-shielding system was necessary to evaluate the radiation environment for future experiments. Characterization of the source was also necessary because the documentation for the three component sources and their relative alignment within the Special Form Capsule (SFC) was inadequate. The system consisting of the source and shielding was modeled using Monte Carlo N-Particle transport code (MCNP). The model was validated by benchmarking it against measurements using multiple techniques. To characterize the radiation fields over the full spatial geometry of the irradiation system, it was necessary to use a number of instruments of varying sensitivities. First, the computed photon radiography assisted in determining orientation of the component sources. With the capsule properly oriented inside the shielding, the neutron spectra were measured using a variety of techniques. A N-probe Microspec and a neutron Bubble Dosimeter Spectrometer (BDS) set were used to characterize the neutron spectra/field in several locations. In the third technique, neutron foil activation was used to ascertain the neutron spectra. A high purity germanium (HPGe) detector was used to characterize the photon spectrum. The experimentally measured spectra and the MCNP results compared well. Once the MCNP model was validated to an adequate level of confidence, parametric analyses was performed on the model to optimize for potential

  19. Design of sample carrier for neutron irradiation facility at TRIGA MARK II nuclear reactor

    NASA Astrophysics Data System (ADS)

    Abdullah, Y.; Hamid, N. A.; Mansor, M. A.; Ahmad, M. H. A. R. M.; Yusof, M. R.; Yazid, H.; Mohamed, A. A.

    2013-06-01

    The objective of this work is to design a sample carrier for neutron irradiation experiment at beam ports of research nuclear reactor, the Reaktor TRIGA PUSPATI (RTP). The sample carrier was designed so that irradiation experiment can be performed safely by researchers. This development will resolve the transferring of sample issues faced by the researchers at the facility when performing neutron irradiation studies. The function of sample carrier is to ensure the sample for the irradiation process can be transferred into and out from the beam port of the reactor safely and effectively. The design model used was House of Quality Method (HOQ) which is usually used for developing specifications for product and develop numerical target to work towards and determining how well we can meet up to the needs. The chosen sample carrier (product) consists of cylindrical casing shape with hydraulic cylinders transportation method. The sample placing can be done manually, locomotion was by wheel while shielding used was made of boron materials. The sample carrier design can shield thermal neutron during irradiation of sample so that only low fluencies fast neutron irradiates the sample.

  20. Radiograaff, a proton irradiation facility for radiobiological studies at a 4 MV Van de Graaff accelerator

    NASA Astrophysics Data System (ADS)

    Constanzo, J.; Fallavier, M.; Alphonse, G.; Bernard, C.; Battiston-Montagne, P.; Rodriguez-Lafrasse, C.; Dauvergne, D.; Beuve, M.

    2014-09-01

    A horizontal beam facility for radiobiological experiments with low-energy protons has been set up at the 4 MV Van de Graaff accelerator of the Institut de Physique Nucléaire de Lyon. A homogeneous irradiation field with a suitable proton flux is obtained by means of two collimators and two Au-scattering foils. A monitoring chamber contains a movable Faraday cup, a movable quartz beam viewer for controlling the intensity and the position of the initial incident beam and four scintillating fibers for beam monitoring during the irradiation of the cell samples. The beam line is ended by a thin aluminized Mylar window (12 μm thick) for the beam extraction in air. The set-up was simulated by the GATE v6.1 Monte-Carlo platform. The measurement of the proton energy distribution, the evaluation of the fluence-homogeneity over the sample and the calibration of the monitoring system were performed using a silicon PIPS detector, placed in air in the same position as the biological samples to be irradiated. The irradiation proton fluence was found to be homogeneous to within ±2% over a circular field of 20 mm diameter. As preliminary biological experiment, two Human Head and Neck Squamous Carcinoma Cell lines (with different radiosensitivities) were irradiated with 2.9 MeV protons. The measured survival curves are compared to those obtained after X-ray irradiation, giving a Relative Biological Efficiency between 1.3 and 1.4.

  1. Spectral Power and Irradiance Responsivity Calibration of InSb Working-Standard Radiometers.

    PubMed

    Eppeldauer, G; Rácz, M

    2000-11-01

    New, improved-performance InSb power-irradiance meters have been developed and characterized to maintain the National Institute of Standards and Technology (NIST) spectral responsivity scale between 2 and 5.1 mum. The InSb radiometers were calibrated against the transfer-standard cryogenic bolometer that is tied to the primary-standard cryogenic radiometer of the NIST. The InSb radiometers serve as easy-to-use working standards for routine spectral power and irradiance responsivity calibrations. The spectral irradiance responsivities were derived from the spectral power responsivities by use of the measured area of the apertures in front of the InSb detectors. PMID:18354571

  2. 25 CFR 170.810 - To what standards must an IRR transportation facility be maintained?

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false To what standards must an IRR transportation facility be maintained? 170.810 Section 170.810 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR LAND AND WATER INDIAN RESERVATION ROADS PROGRAM BIA Road Maintenance § 170.810 To what standards must an IRR transportation facility be maintained?...

  3. 40 CFR 60.5380 - What standards apply to centrifugal compressor affected facilities?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... standards apply to centrifugal compressor affected facilities? You must comply with the standards in paragraphs (a) through (d) of this section for each centrifugal compressor affected facility. (a)(1) You must reduce VOC emissions from each centrifugal compressor wet seal fluid degassing system by 95.0 percent...

  4. 40 CFR 60.5380 - What standards apply to centrifugal compressor affected facilities?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... standards apply to centrifugal compressor affected facilities? You must comply with the standards in paragraphs (a) through (d) of this section for each centrifugal compressor affected facility. (a)(1) You must reduce VOC emissions from each centrifugal compressor wet seal fluid degassing system by 95.0 percent...

  5. New electron beam facility for irradiated plasma facing materials testing in hot cell

    SciTech Connect

    Sakamoto, N.; Kawamura, H.; Akiba, M.

    1995-09-01

    Since plasma facing components such as the first wall and the divertor for the next step fusion reactors are exposed to high heat loads and high energy neutron flux generated by the plasma, it is urgent to develop of plasma facing components which can resist these. Then, we have established electron beam heat facility ({open_quotes}OHBIS{close_quotes}, Oarai Hot-cell electron Beam Irradiating System) at a hot cell in JMTR (Japan Materials Testing Reactor) hot laboratory in order to estimate thermal shock resistivity of plasma facing materials and heat removal capabilities of divertor elements under steady state heating. In this facility, irradiated plasma facing materials (beryllium, carbon based materials and so on) and divertor elements can be treated. This facility consists of an electron beam unit with the maximum beam power of 50kW and the vacuum vessel. The acceleration voltage and the maximum beam current are 30kV (constant) and 1.7A, respectively. The loading time of electron beam is more than 0.1ms. The shape of vacuum vessel is cylindrical, and the mainly dimensions are 500mm in inner diameter, 1000mm in height. The ultimate vacuum of this vessel is 1 x 10{sup -4}Pa. At present, the facility for thermal shock test has been established in a hot cell. And performance estimation on the electron beam is being conducted. Presently, the devices for heat loading tests under steady state will be added to this facility.

  6. 40 CFR 279.52 - General facility standards.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... gas, or dry chemicals), spill control equipment and decontamination equipment; and (iv) Water at... alarm systems, fire protection equipment, spill control equipment, and decontamination equipment, where... control equipment, and decontamination equipment to any area of facility operation in an emergency,...

  7. Standards for material handling and facilities equipment proofload testing

    NASA Technical Reports Server (NTRS)

    Bonn, S. P.

    1970-01-01

    Document provides information on verifying the safety of material handling and facilities equipment /MH/FE/, ranging from monorail systems to ladders and non-powered mobile equipment. Seven catagories of MH/FE equipment are defined.

  8. National Low-Temperature Neutron Irradiation Facility (NLTNIF). The status of development

    SciTech Connect

    Coltman, R.R. Jr.; Kerchner, H.R.; Klabunde, C.E.; Young, F.W. Jr.

    1985-12-01

    In May 1983, the Department of Energy authorized the establishment of a National Low-Temperature Neutron Irradiation Facility (NLTNIF) at ORNL's Bulk Shielding Reactor (BSR). The NLTNIF, which will be available for qualified experiments at no cost to users, will provide a combination of high radiation intensities and special environmental and testing conditions that have not been previously available in the US. Since the DOE authorization, work has proceeded on the design and construction of the new facility without interruption. This report describes the present status of the development of the NLTNIF and the anticipated schedule for completion and performance testing. There is a table of the major specifications and capabilities and a schematic layout of the irradiation cryostate for design and dimensioning of test and experiment assemblies.

  9. Formation of the uniform irradiation of a target in high-power laser facilities

    SciTech Connect

    Garanin, Sergey G; Derkach, Vladimir N; Shnyagin, Roman A

    2004-05-31

    The methods are developed for obtaining highly uniform laser beams for direct irradiation of targets in high-power laser facilities being designed. The methods are based on the optimisation of the mutual arrangement of the beams irradiating a target, the use of stationary phase plates for the formation of the specified radiation intensity distribution on the target, and the employment of the spatiotemporal beam smoothing to suppress small-scale inhomogeneities. The requirements on different systems of the facility are considered which provide the necessary accuracy of the beam steering on a target and the admissible difference in the intensities of the beams. A method is proposed for the spatiotemporal beam smoothing using the nonstationary properties of a laser plasma. The possibilities of this method are studied experimentally. (invited paper)

  10. Characteristics of a contract electron beam and bremsstrahlung (X-ray) irradiation facility of Radia industry

    NASA Astrophysics Data System (ADS)

    Takehisa, Masaaki; Saito, Toshio; Takahashi, Thoru; Sato, Yoshishige; Sato, Toshio

    1993-07-01

    A contract electron beam(EB) and bremsstrahlung(X-ray) facility with use of NHV 5 MeV, 30 mA Cock-Croft Walton machine is operational for EB since April 1991, and X-ray commercial irradiation was started in 1992 summer. The facility is consisted of the EB machine, bremsstrahlung target, chain and roller conveyor, and automatic turnover machine for dual sided irradiation. The operation of the system is fully controlled by LAN of personal computers for client's order, EB characteristics, beam current control proportional to the conveyor speed, turnover of product in processing mid point, and output of processing record to clients. The control and recording systems avoid human errors. This paper mainly discusses X-ray processing.

  11. Monte Carlo dosimetry for targeted irradiation of individual cells using a microbeam facility.

    PubMed

    Incerti, S; Seznec, H; Simon, M; Barberet, Ph; Habchi, C; Moretto, Ph

    2009-01-01

    Microbeam facilities provide a unique opportunity to investigate the effects of ionising radiation on living biological cells with a precise control of the delivered dose. This paper describes dosimetry calculations performed at the single-cell level in the microbeam irradiation facility available at the Centre d'Etudes Nucléaires de Bordeaux-Gradignan in France, using the object-oriented Geant4 Monte Carlo simulation toolkit. The cell geometry model is based on high-resolution three-dimensional voxelised phantoms of a human keratinocyte (HaCaT) cell line. Such phantoms are built from confocal microscopy imaging and from ion beam chemical elemental analysis. Results are presented for single-cell irradiation with 3 MeV incident alpha particles. PMID:19174380

  12. Laser irradiance scaling in polar direct drive implosions on the National Ignition Facility

    NASA Astrophysics Data System (ADS)

    Murphy, T. J.; Krasheninnikova, N. S.; Kyrala, G. A.; Bradley, P. A.; Baumgaertel, J. A.; Cobble, J. A.; Hakel, P.; Hsu, S. C.; Kline, J. L.; Montgomery, D. S.; Obrey, K. A. D.; Shah, R. C.; Tregillis, I. L.; Schmitt, M. J.; Kanzleiter, R. J.; Batha, S. H.; Wallace, R. J.; Bhandarkar, S. D.; Fitzsimmons, P.; Hoppe, M. L.; Nikroo, A.; Hohenberger, M.; McKenty, P. W.; Rinderknecht, H. G.; Rosenberg, M. J.; Petrasso, R. D.

    2015-09-01

    Polar-direct-drive experiments conducted at the National Ignition Facility [E. I. Moses, Fusion Sci. Technol. 54, 361 (2008)] performed at laser irradiance between 1 and 2 × 10 15 W / cm 2 exhibit increased hard x-ray emission, decreased neutron yield, and reduced areal density as the irradiance is increased. Experimental x-ray images at the higher irradiances show x-ray emission at the equator, as well as degraded symmetry, that is not predicted in hydrodynamic simulations using flux-limited energy transport, but that appear when non-local electron transport together with a model to account for cross beam energy transfer (CBET) is utilized. The reduction in laser power for equatorial beams required in the simulations to reproduce the effects of CBET on the observed symmetry also reproduces the yield degradation consistent with experimental data.

  13. Laser irradiance scaling in polar direct drive implosions on the National Ignition Facility

    DOE PAGESBeta

    Murphy, T. J.; Krasheninnikova, N. S.; Kyrala, G. A.; Bradley, P. A.; Baumgaertel, J. A.; Cobble, J. A.; Hakel, P.; Hsu, S. C.; Kline, J. L.; Montgomery, D. S.; et al

    2015-09-17

    Polar-direct-drive experiments conducted at the National Ignition Facility [E. I. Moses, Fusion Sci. Technol. 54, 361 (2008)] performed at laser irradiance between 1 and 2×1015 W/cm2 exhibit increased hard x-ray emission, decreased neutron yield, and reduced areal density as the irradiance is increased. Experimental x-ray images at the higher irradiances show x-ray emission at the equator, as well as degraded symmetry, that is not predicted in hydrodynamic simulations using flux-limited energy transport, but that appear when non-local electron transport together with a model to account for cross beam energy transfer (CBET) is utilized. The reduction in laser power for equatorialmore » beams required in the simulations to reproduce the effects of CBET on the observed symmetry also reproduces the yield degradation consistent with experimental data.« less

  14. Laser irradiance scaling in polar direct drive implosions on the National Ignition Facility

    SciTech Connect

    Murphy, T. J.; Krasheninnikova, N. S.; Kyrala, G. A.; Bradley, P. A.; Baumgaertel, J. A.; Cobble, J. A.; Hakel, P.; Hsu, S. C.; Kline, J. L.; Montgomery, D. S.; Obrey, K. A. D.; Shah, R. C.; Tregillis, I. L.; Schmitt, M. J.; Kanzleiter, R. J.; Batha, S. H.; Wallace, R. J.; Bhandarkar, S. D.; Fitzsimmons, P.; Hoppe, M. L.; Nikroo, A.; Hohenberger, M.; McKenty, P. W.; Rinderknecht, H. G.; Rosenberg, M. J.; Petrasso, R. D.

    2015-09-17

    Polar-direct-drive experiments conducted at the National Ignition Facility [E. I. Moses, Fusion Sci. Technol. 54, 361 (2008)] performed at laser irradiance between 1 and 2×1015 W/cm2 exhibit increased hard x-ray emission, decreased neutron yield, and reduced areal density as the irradiance is increased. Experimental x-ray images at the higher irradiances show x-ray emission at the equator, as well as degraded symmetry, that is not predicted in hydrodynamic simulations using flux-limited energy transport, but that appear when non-local electron transport together with a model to account for cross beam energy transfer (CBET) is utilized. The reduction in laser power for equatorial beams required in the simulations to reproduce the effects of CBET on the observed symmetry also reproduces the yield degradation consistent with experimental data.

  15. Determination of proton and neutron spectra in the LANSCE spallation irradiation facility

    SciTech Connect

    James, M.R.; Maloy, S.A.; Sommer, W.F.; Fowler, M.M.; Dry, D.; Ferguson, P.D.; Mueller, G.; Corzine, R.K.

    1999-06-01

    Materials samples were recently irradiated in the Los Alamos Radiation Effects Facility (LASREF) at the Los Alamos Neutron Science Center (LANSCE) to provide data for the Accelerator Production of Tritium (APT) project on the effect of irradiation on the mechanical and physical properties of materials. The targets were configured to expose samples to a variety of radiation environments including, high-energy protons, mixed protons and high-energy neutrons, and low-energy neutrons. The samples were irradiated for approximately six months during a ten month period using an 800 MeV proton beam with a circular Gaussian shape of approximately 2{sigma} = 3.0 cm. At the end of this period, the samples were extracted and tested. Activation foils were also extracted that had been placed in proximity to the materials samples. These were used to quantify the fluences in various locations.

  16. 39 CFR 254.1 - Adoption of U.S. Access Board Standards as Postal Service Standards of Facility Accessibility.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Barriers Act (ABA) “Standards for Facility Accessibility,” the following sections of 36 CFR part 1191... THE ARCHITECTURAL BARRIERS ACT § 254.1 Adoption of U.S. Access Board Standards as Postal Service... Barriers Act, Scoping (which contains ABA Chapter 1, Application and Administration, and ABA Chapter...

  17. Uncertainty Analysis of Spectral Irradiance Reference Standards Used for NREL Calibrations

    SciTech Connect

    Habte, A.; Andreas, A.; Reda, I.; Campanelli, M.; Stoffel, T.

    2013-05-01

    Spectral irradiance produced by lamp standards such as the National Institute of Standards and Technology (NIST) FEL-type tungsten halogen lamps are used to calibrate spectroradiometers at the National Renewable Energy Laboratory. Spectroradiometers are often used to characterize spectral irradiance of solar simulators, which in turn are used to characterize photovoltaic device performance, e.g., power output and spectral response. Therefore, quantifying the calibration uncertainty of spectroradiometers is critical to understanding photovoltaic system performance. In this study, we attempted to reproduce the NIST-reported input variables, including the calibration uncertainty in spectral irradiance for a standard NIST lamp, and quantify uncertainty for measurement setup at the Optical Metrology Laboratory at the National Renewable Energy Laboratory.

  18. Transmutation behaviour of Eurofer under irradiation in the IFMIF test facility and fusion power reactors

    NASA Astrophysics Data System (ADS)

    Fischer, U.; Simakov, S. P.; Wilson, P. P. H.

    2004-08-01

    The transmutation behaviour of the low activation steel Eurofer was analysed for irradiation simulations in the high flux test module (HFTM) of the International Fusion Material Irradiation Facility (IFMIF) neutron source and the first wall of a typical fusion power reactor (FPR) employing helium cooled lithium lead (HCLL) and pebble bed (HCPB) blankets. The transmutation calculations were conducted with the analytical and laplacian adaptive radioactivity analysis (ALARA) code and IEAF-2001 data for the IFMIF and the EASY-2003 system for the fusion power reactor (FPR) irradiations. The analyses showed that the transmutation of the main constituents of Eurofer, including iron and chromium, is not significant. Minor constituents such as Ti, V and Mn increase by 5-15% per irradiation year in the FPR and by 10-35% in the IFMIF HFTM. Other minor constituents such as B, Ta, and W show a different transmutation behaviour resulting in different elemental compositions of the Eurofer steel after high fluence irradiations in IFMIF and fusion power reactors.

  19. 40 CFR 63.471 - Facility-wide standards.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... total emissions of perchloroethylene (PCE), trichloroethylene (TCE) and methylene chloride (MC) used at... TCE only 14,100 23,500 MC only 60,000 100,000 Multiple solvents—Calculate the MC-weighted emissions..., the facility emissions of PCE and TCE are weighted according to their carcinogenic potency relative...

  20. 49 CFR 37.9 - Standards for accessible transportation facilities.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... requirements set forth in appendices B and D to 36 CFR part 1191, which apply to buildings and facilities... and D to 36 CFR part 1191 and appendix A to this part, if the modifications complied with the Uniform... covering those elements or spaces are contained in UFAS or ANSI A117.1, as applicable. (c) (1)...

  1. 49 CFR 37.9 - Standards for accessible transportation facilities.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... requirements set forth in Appendices B and D to 36 CFR part 1191, which apply to buildings and facilities... and D to 36 CFR part 1191 and Appendix A to this part, if the modifications complied with the Uniform... covering those elements or spaces are contained in UFAS or ANSI A117.1, as applicable. (c) (1)...

  2. 40 CFR 63.471 - Facility-wide standards.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... total emissions of perchloroethylene (PCE), trichloroethylene (TCE) and methylene chloride (MC) used at... TCE only 14,100 23,500 MC only 60,000 100,000 Multiple solvents—Calculate the MC-weighted emissions..., the facility emissions of PCE and TCE are weighted according to their carcinogenic potency relative...

  3. 40 CFR 63.471 - Facility-wide standards.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... total emissions of perchloroethylene (PCE), trichloroethylene (TCE) and methylene chloride (MC) used at... TCE only 14,100 23,500 MC only 60,000 100,000 Multiple solvents—Calculate the MC-weighted emissions..., the facility emissions of PCE and TCE are weighted according to their carcinogenic potency relative...

  4. 40 CFR 63.471 - Facility-wide standards.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... total emissions of perchloroethylene (PCE), trichloroethylene (TCE) and methylene chloride (MC) used at... TCE only 14,100 23,500 MC only 60,000 100,000 Multiple solvents—Calculate the MC-weighted emissions..., the facility emissions of PCE and TCE are weighted according to their carcinogenic potency relative...

  5. Radiation scales on which standard values of the solar constant and solar spectral irradiance are based

    NASA Technical Reports Server (NTRS)

    Thekaekara, M. P.

    1972-01-01

    The question of radiation scales is critically examined. There are two radiation scales which are of fundamental validity and there are several calibration standards and radiation scales which have been set up for practical convenience. The interrelation between these scales is investigated. It is shown that within the limits of accuracy of irradiance measurements in general and solar irradiance measurements in particular, the proposed standard values of the solar constant and solar spectrum should be considered to be on radiation scales of fundamental validity; those based on absolute electrical units and on the thermodynamic Kelvin temperature scale.

  6. Whole-Pin Furnace system: An experimental facility for studying irradiated fuel pin behavior under potential reactor accident conditions

    SciTech Connect

    Liu, Y.Y.; Tsai, H.C.; Donahue, D.A.; Pushis, D.O.; Savoie, F.E.; Holland, J.W.; Wright, A.E.; August, C.; Bailey, J.L.; Patterson, D.R.

    1990-05-01

    The whole-pin furnace system is a new in-cell experimental facility constructed to investigate how irradiated fuel pins may fail under potential reactor accident conditions. Extensive checkouts have demonstrated excellent performance in remote operation, temperature control, pin breach detection, and fission gas handling. The system is currently being used in testing of EBIR-II-irradiated Integral Fast Reactor (IFR) metal fuel pins; future testing will include EBR-II-irradiated mixed-oxide fuel pins. 7 refs., 4 figs.

  7. Jules Horowitz Reactor, a new irradiation facility: Improving dosimetry for the future of nuclear experimentation

    SciTech Connect

    Gregoire, G.; Beretz, D.; Destouches, C.

    2011-07-01

    Document available in abstract form only, full text of document follows: The Jules Horowitz Reactor (JHR) is an experimental reactor under construction at the French Nuclear Energy and Alternative Energies Commission (CEA) facility at Cadarache. It will achieve its first criticality by the end of 2014. Experiments that will be conducted at JHR will deal with fuel, cladding, and material behavior. The JHR will also produce medical radio-isotopes and doped silicon for the electronic industry. As a new irradiation facility, its instrumentation will benefit from recent improvements. Nuclear instrumentation will include reactor dosimetry, as it is a reference technique to determine neutron fluence in experimental devices or characterize irradiation locations. Reactor dosimetry has been improved with the progress of simulation tools and nuclear data, but at the same time the customer needs have increased: Experimental results must have reduced and assessed uncertainties. This is now a necessary condition to perform an experimental irradiation in a test reactor. Items improved, in the framework of a general upgrading of the dosimetry process based on uncertainty minimization, will include dosimeter, nuclear data, and modelling scheme. (authors)

  8. Analyses in support of risk-informed natural gas vehicle maintenance facility codes and standards :

    SciTech Connect

    Ekoto, Isaac W.; Blaylock, Myra L.; LaFleur, Angela Christine; LaChance, Jeffrey L.; Horne, Douglas B.

    2014-03-01

    Safety standards development for maintenance facilities of liquid and compressed gas fueled large-scale vehicles is required to ensure proper facility design and operation envelopes. Standard development organizations are utilizing risk-informed concepts to develop natural gas vehicle (NGV) codes and standards so that maintenance facilities meet acceptable risk levels. The present report summarizes Phase I work for existing NGV repair facility code requirements and highlights inconsistencies that need quantitative analysis into their effectiveness. A Hazardous and Operability study was performed to identify key scenarios of interest. Finally, scenario analyses were performed using detailed simulations and modeling to estimate the overpressure hazards from HAZOP defined scenarios. The results from Phase I will be used to identify significant risk contributors at NGV maintenance facilities, and are expected to form the basis for follow-on quantitative risk analysis work to address specific code requirements and identify effective accident prevention and mitigation strategies.

  9. Design of spectrally tailored fusion reactor materials experiments in the HFIR RB∗ capsule irradiation facility

    NASA Astrophysics Data System (ADS)

    Longest, A. W.; Corum, J. E.; Heatherly, D. W.; Thoms, K. R.

    1988-07-01

    Design of four spectrally tailored capsules to irradiate magnetic fusion energy (MFE) materials specimens in the new High Flux Isotope Reactor (HFIR) removable beryllium (RB∗) facility at temperatures of 60, 200, 330 and 400°C, is described. These designs incorporate provisions for removal, examination and reencapsulation of the specimens at intermediate exposure levels en route to a target exposure level of 30 displacements per atom (dpa). With the exception of the 60°C capsule, where the test specimens are in direct contact with the reactor cooling water, the specimen temperatures (monitored by 21 thermocouples) are controlled by varying the thermal conductance of a small gap region between the specimen holder and the containment tube. Hafnium shields are used to tailor the neutron spectrum to closely match the helium production-to-atom displacement ratio ( {14 appm}/{dpa}) expected in an austenitic stainless steel fusion reactor first wall. These MFE capsule irradiations will begin in early 1988.

  10. Method for Standardizing Sonic-Boom Model Pressure Signatures Measured at Several Wind-Tunnel Facilities

    NASA Technical Reports Server (NTRS)

    Mack, Robert J.

    2007-01-01

    Low-boom model pressure signatures are often measured at two or more wind-tunnel facilities. Preliminary measurements are made at small separation distances in a wind tunnel close at hand, and a second set of pressure signatures is measured at larger separation distances in a wind-tunnel facility with a larger test section. In this report, a method for correcting and standardizing the wind-tunnel-measured pressure signatures obtained in different wind tunnel facilities is presented and discussed.

  11. IFMIF - International Fusion Materials Irradiation Facility Conceptual Design Activity/Interim Report

    SciTech Connect

    Rennich, M.J.

    1995-12-01

    Environmental acceptability, safety, and economic viability win ultimately be the keys to the widespread introduction of fusion power. This will entail the development of radiation- resistant and low- activation materials. These low-activation materials must also survive exposure to damage from neutrons having an energy spectrum peaked near 14 MeV with annual radiation doses in the range of 20 displacements per atom (dpa). Testing of candidate materials, therefore, requires a high-flux source of high energy neutrons. The problem is that there is currently no high-flux source of neutrons in the energy range above a few MeV. The goal, is therefore, to provide an irradiation facility for use by fusion material scientists in the search for low-activation and damage-resistant materials. An accellerator-based neutron source has been established through a number of international studies and workshops` as an essential step for materials development and testing. The mission of the International Fusion Materials Irradiation Facility (IFMIF) is to provide an accelerator-based, deuterium-lithium (D-Li) neutron source to produce high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials up to about a full lifetime of anticipated use in fusion energy reactors. would also provide calibration and validation of data from fission reactor and other accelerator-based irradiation tests. It would generate material- specific activation and radiological properties data, and support the analysis of materials for use in safety, maintenance, recycling, decommissioning, and waste disposal systems.

  12. 36 CFR 1150.2 - Applicability: Buildings and facilities subject to guidelines and standards.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... building or facility may be subject to standards for design, construction, or alteration issued under the... military installation designed and constructed primarily for use by military personnel. (d) Any covered building or facility, as provided in this section, which is designed, constructed, or altered after...

  13. 36 CFR 1150.2 - Applicability: Buildings and facilities subject to guidelines and standards.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... building or facility may be subject to standards for design, construction, or alteration issued under the... military installation designed and constructed primarily for use by military personnel. (d) Any covered building or facility, as provided in this section, which is designed, constructed, or altered after...

  14. 36 CFR 1150.2 - Applicability: Buildings and facilities subject to guidelines and standards.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... building or facility may be subject to standards for design, construction, or alteration issued under the... military installation designed and constructed primarily for use by military personnel. (d) Any covered building or facility, as provided in this section, which is designed, constructed, or altered after...

  15. 76 FR 65544 - Standard Format and Content of License Applications for Mixed Oxide Fuel Fabrication Facilities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-21

    ... issuance of the guide (74 FR 36780). The comment period closed on September 21, 2009. The staff's responses... COMMISSION Standard Format and Content of License Applications for Mixed Oxide Fuel Fabrication Facilities... Format and Content of License Applications for Mixed Oxide Fuel Fabrication Facilities.'' This...

  16. Guidelines and Standards for the Technology Infrastructure of 21st Century Educational Facilities.

    ERIC Educational Resources Information Center

    New York State Education Dept., Albany. Office of Facilities Planning.

    New York State Regents directed that new guidelines and "standards" be developed for technology infrastructures in educational facilities in order to assist administrators and educators in planning technology integration during retrofits, renovations, or new construction of educational facilities. This document provides the first draft of these…

  17. 78 FR 29759 - Chemical Facility Anti-Terrorism Standards Personnel Surety Program

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-21

    ...; Chemical Facility Anti-Terrorism Standards Personnel Surety Program'' at 78 FR 17680. In the March 22, 2013... March 22, 2013, at 78 FR 17680, entitled ``Information Collection Request; Chemical Facility Anti... Program Notice and Request for Comments published on March 22, 2013, at 78 FR 17680, is extended....

  18. 41 CFR 102-74.165 - What energy standards must Federal agencies follow for existing facilities?

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 41 Public Contracts and Property Management 3 2011-01-01 2011-01-01 false What energy standards must Federal agencies follow for existing facilities? 102-74.165 Section 102-74.165 Public Contracts and Property Management Federal Property Management Regulations System (Continued) FEDERAL MANAGEMENT REGULATION REAL PROPERTY 74-FACILITY...

  19. 41 CFR 102-74.165 - What energy standards must Federal agencies follow for existing facilities?

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 41 Public Contracts and Property Management 3 2012-01-01 2012-01-01 false What energy standards must Federal agencies follow for existing facilities? 102-74.165 Section 102-74.165 Public Contracts and Property Management Federal Property Management Regulations System (Continued) FEDERAL MANAGEMENT REGULATION REAL PROPERTY 74-FACILITY...

  20. Assessment of radiation exposure for materials in the LANSCE Spallation Irradiation Facility

    SciTech Connect

    James, M. R.; Maloy, S. A.; Sommer, W. F. , Jr.; Fowler, Malcolm M.; Dry, D. E.; Ferguson, P. D.; Corzine, R. K.; Mueller, G. E.

    2001-01-01

    Materials samples were irradiated in the Los Alamos Radiation Effects Facility (LASREF) at the Los Alamos Neutron Science Center (LANSCE) to provide data for the Accelerator Production of Tritium (APT) project on the changes in mechanical and physical properties of materials in a spallation target environment. The targets were configured to expose samples to a variety of radiation environments including high-energy protons, mixed protons and neutrons, and predominantly neutrons. The irradiation was driven by an 800 MeV 1 mA proton beam with a circular Gaussian shape of approximately 2{sigma} = 3.5 cm. Two irradiation campaigns were conducted in which samples were exposed for approximately six months and two months, respectively. At the end of this period, the samples were extracted and tested. Activation foils that had been placed in proximity to the materials samples were used to quantify the fluences in various locations. The STAYSL2 code was used to estimate the fluences by combining the activation foil data with calculated data from the LAHET Code System (LCS) and MCNPX. The exposure for each sample was determined from the estimated fluences using interpolation based on a mathematical fitting to the fluence results. The final results included displacement damage (dpa) and gas (H, He) production for each sample from the irradiation. Based on the activation foil analysis, samples from several locations in both irradiation campaigns were characterized. The radiation damage to each sample was highly dependent upon location and varied from 0.023 to 13 dpa and was accompanied by high levels of H and He production.

  1. Appointment standardization evaluation in a primary care facility.

    PubMed

    Huang, Yu-Li

    2016-07-11

    Purpose - The purpose of this paper is to evaluate the performance on standardizing appointment slot length in a primary care clinic to understand the impact of providers' preferences and practice differences. Design/methodology/approach - The treatment time data were collected for each provider. There were six patient types: emergency/urgent care (ER/UC), follow-up patient (FU), new patient, office visit (OV), physical exam, and well-child care. Simulation model was developed to capture patient flow and measure patient wait time, provider idle time, cost, overtime, finish time, and the number of patients scheduled. Four scheduling scenarios were compared: scheduled all patients at 20 minutes; scheduled ER/UC, FU, OV at 20 minutes and others at 40 minutes; scheduled patient types on individual provider preference; and scheduled patient types on combined provider preference. Findings - Standardized scheduling among providers increase cost by 57 per cent, patient wait time by 83 per cent, provider idle time by five minutes per patient, overtime by 22 minutes, finish time by 30 minutes, and decrease patient access to care by approximately 11 per cent. An individualized scheduling approach could save as much as 14 per cent on cost and schedule 1.5 more patients. The combined preference method could save about 8 per cent while the number of patients scheduled remained the same. Research limitations/implications - The challenge is to actually disseminate the findings to medical providers and adjust scheduling systems accordingly. Originality/value - This paper concluded standardization of providers' clinic preference and practice negatively impact clinic service quality and access to care. PMID:27298064

  2. 40 CFR 60.5375 - What standards apply to gas well affected facilities?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 40 Protection of Environment 7 2013-07-01 2013-07-01 false What standards apply to gas well... Performance for Crude Oil and Natural Gas Production, Transmission and Distribution § 60.5375 What standards apply to gas well affected facilities? If you are the owner or operator of a gas well affected...

  3. 40 CFR 60.5375 - What standards apply to gas well affected facilities?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 40 Protection of Environment 7 2014-07-01 2014-07-01 false What standards apply to gas well... Performance for Crude Oil and Natural Gas Production, Transmission and Distribution § 60.5375 What standards apply to gas well affected facilities? If you are the owner or operator of a gas well affected...

  4. 45 CFR 205.170 - State standards for office space, equipment, and facilities.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 45 Public Welfare 2 2011-10-01 2011-10-01 false State standards for office space, equipment, and facilities. 205.170 Section 205.170 Public Welfare Regulations Relating to Public Welfare OFFICE OF FAMILY... SERVICES GENERAL ADMINISTRATION-PUBLIC ASSISTANCE PROGRAMS § 205.170 State standards for office...

  5. 45 CFR 205.170 - State standards for office space, equipment, and facilities.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 45 Public Welfare 2 2010-10-01 2010-10-01 false State standards for office space, equipment, and facilities. 205.170 Section 205.170 Public Welfare Regulations Relating to Public Welfare OFFICE OF FAMILY... SERVICES GENERAL ADMINISTRATION-PUBLIC ASSISTANCE PROGRAMS § 205.170 State standards for office...

  6. 49 CFR Appendix A to Part 37 - Modifications to Standards for Accessible Transportation Facilities

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 1 2011-10-01 2011-10-01 false Modifications to Standards for Accessible Transportation Facilities A Appendix A to Part 37 Transportation Office of the Secretary of Transportation TRANSPORTATION SERVICES FOR INDIVIDUALS WITH DISABILITIES (ADA) Pt. 37, App. A Appendix A to Part 37—Modifications to Standards for...

  7. 49 CFR Appendix A to Part 37 - Modifications to Standards for Accessible Transportation Facilities

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 1 2012-10-01 2012-10-01 false Modifications to Standards for Accessible Transportation Facilities A Appendix A to Part 37 Transportation Office of the Secretary of Transportation TRANSPORTATION SERVICES FOR INDIVIDUALS WITH DISABILITIES (ADA) Pt. 37, App. A Appendix A to Part 37—Modifications to Standards for...

  8. 36 CFR 1150.2 - Applicability: Buildings and facilities subject to guidelines and standards.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... ARCHITECTURAL AND TRANSPORTATION BARRIERS COMPLIANCE BOARD PRACTICE AND PROCEDURES FOR COMPLIANCE HEARINGS... provided in paragraph (c) of this section, the standards issued under the Architectural Barriers Act of... building or facility may be subject to standards for design, construction, or alteration issued under...

  9. Implementation of ISO 10110 optics drawing standards for the National Ignition Facility

    SciTech Connect

    English, R.E. Jr.; Aikens, D.M.; Whistler, W.T.

    1995-07-07

    LLNL plans to specify optical components for the National Ignition Facility according to ISO 10110, the new international standard for preparation of optics drawings. The standards have been approved by the international optics community and represent a fairly comprehensive language for describing optical components. We will describe our plan for implementation and experience to date in doing so.

  10. Tomographic imaging of a target directly irradiated in experiments on the Iskra-5 iodine laser facility

    SciTech Connect

    Bondarenko, S V; Garanin, R V; Garanin, Sergey G; Zhidkov, N V; Oreshkov, O V; Potapov, S V; Suslov, N A; Frolova, N V

    2010-12-29

    We set forth the data of experiments involving direct microtarget irradiation by the 12 second-harmonic beams ({lambda} = 0.66 {mu}m) of iodine laser radiation carried out on the Iskra-5 facility. For microtargets we employed glass shells {approx}500 {mu}m in diameter with {approx}1-{mu}m thick walls, which were filled with a DT mixture at a pressure p{sub DT} {approx} 3-4 atm. In one of these experiments, a tomographic image of the microtarget was recorded from the images obtained using pinhole cameras, which were arranged along seven different directions. The pinhole images were acquired in the X-ray radiation with photon energies above 1.5 keV. The procedure used for reconstructing the volume luminosity of the microtarget is described. An analysis of the tomographic image suggests that the compressed microtarget domain possesses a complex asymmetric shape; 20-30 {mu}m sized structural elements being clearly visible. The resultant data set allowed us to estimate the initial nonuniformity of microtarget surface irradiation by the laser radiation. The rms nonuniformity of microtarget irradiance was estimated at {approx}60 %. (interaction of laser radiation with targets)

  11. Development of a facility for high-precision irradiation of cells with carbon ions

    SciTech Connect

    Goethem, Marc-Jan van; Niemantsverdriet, Maarten; Brandenburg, Sytze; Langendijk, Johannes A.; Coppes, Robert P.; Luijk, Peter van

    2011-01-15

    Purpose: Compared to photons, using particle radiation in radiotherapy reduces the dose and irradiated volume of normal tissues, potentially reducing side effects. The biological effect of dose deposited by particles such as carbon ions, however, differs from that of dose deposited by photons. The inaccuracy in models to estimate the biological effects of particle radiation remains the most important source of uncertainties in particle therapy. Improving this requires high-precision studies on biological effects of particle radiation. Therefore, the authors aimed to develop a facility for reproducible and high-precision carbon-ion irradiation of cells in culture. The combined dose nonuniformity in the lateral and longitudinal direction should not exceed {+-}1.5%. Dose to the cells from particles than other carbon ions should not exceed 5%. Methods: A uniform lateral dose distribution was realized using a single scatter foil and quadrupole magnets. A modulator wheel was used to create a uniform longitudinal dose distribution. The choice of beam energy and the optimal design of these components was determined using GEANT4 and SRIM Monte Carlo simulations. Verification of the uniformity of the dose distribution was performed using a scintillating screen (lateral) and a water phantom (longitudinal). The reproducibility of dose delivery between experiments was assessed by repeated measurements of the spatial dose distribution. Moreover, the reproducibility of dose-response measurements was tested by measuring the survival of irradiated HEK293 cells in three independent experiments. Results: The relative contribution of dose from nuclear reaction fragments to the sample was found to be <5% when using 90 MeV/u carbon ions. This energy still allows accurate dosimetry conforming to the IAEA Report TRS-398, facilitating comparison to dose-effect data obtained with other radiation qualities. A 1.3 mm long spread-out Bragg peak with a diameter of 30 mm was created, allowing

  12. Waste encapsulation storage facility (WESF) standards/requirements identification document (S/RIDS)

    SciTech Connect

    Maddox, B.S., Westinghouse Hanford

    1996-07-29

    This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ES{ampersand}H) standards/requirements for the Waste Encapsulation Storage Facility (WESF). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

  13. BUILDING 830 GAMMA IRRADIATION FACILITY EVALUATION OF OPTIONS FOR ITS FUTURE DISPOSITION.

    SciTech Connect

    BOWERMAN,B.; COWGILL,M.; HEISER,J.; MOSKOWITZ,P.

    1998-09-30

    In the spring of 1997, the Suffolk County Department of Health Services audited the BNL site, and identified the Building 830 Gamma Irradiation Facility (GIF) as an underground tank regulated under Suffolk County Health Code, Article 12. As a result of this audit, a project was initiated to review the GIF and to collect information to develop an options list for its future disposition. The overall objective of this task was to evaluate the decontamination and decommissioning (D&D) of the GIF, including the proper disposal of the cobalt-60 sources currently located in the GIF. This objective was accomplished through the performance of the following subtasks. (1) Characterize the GIF and the cobalt-60 sources: (a) Compile available data on the physical and radiological characteristics of the gamma sources; (b) Conduct underwater surveys to verify visually the physical state of the sources, and if possible, their activity levels (curie content); and (c) Prepare the pool, to the extent possible, for removal of the sources. (2) Identify options for future disposition: (a) Contact other gamma facilities and find out their experiences with recycling, disposal, and D&D; and (b) Contact vendors for the disposal or recycling of the cobalt-60 sources. Identify options and factors affecting them, such as costs, regulatory issues, health and safety requirements, equipment availability. This report summarizes the results of these subtasks. The remainder of this introductory section gives a description of the GIF, provides a brief history of the facility, and discusses the applicable Article 12 requirements. Section 2 focuses on the sources themselves, and the current facility configuration. Contacts with other gamma facilities are summarized in Section 3. Section 4 presents the options developed from these contacts and from BNL experience, and their estimated costs. Costs are tabulated and compared in Section 5, and Section 6 presents conclusions.

  14. Disinfestation of packed dates by gamma-radiation using a suitable food irradiation facility

    NASA Astrophysics Data System (ADS)

    Al-Taweel, A. A.; Hameed, A. A.; Ahmed, M. S. H.; Ali, M. A.

    Dosimetric calculations of 15 positions fixed inside a standard carton box (SCB), holding 40 polyethylene-wrapped lunch boxes (CBs) of dates, Zahdi variety, were carried out. They showed that the practical treatment with irradiation for date disinfestation purposes, in a Gammabeam-650 irradiator, is to use a dose of 0.44 ± 0.05 kGy with a rotating turntable. This dose required an exposure time of 29.57 min, where maximum and minimum limits were 0.51 and 0.35 kGy. Consequently, the dose uniformity ratio was 1.47, which lies within the accepted range provided that the limits, rather than the overall average dose, be considered. As a result of irradiating the packed dates with the above-mentioned dose, no live insects could be detected after storing for a period of 185 days. The live insects that were detected after 1 day post-treatment storage proved to be sterile and died within a short period of time.

  15. 41 CFR 102-74.355 - With what accident and fire prevention standards must Federal facilities comply?

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... MANAGEMENT REGULATION REAL PROPERTY 74-FACILITY MANAGEMENT Facility Management Accident and Fire Prevention § 102-74.355 With what accident and fire prevention standards must Federal facilities comply? To the maximum extent feasible, Federal agencies must manage facilities in accordance with the accident and...

  16. 41 CFR 102-74.355 - With what accident and fire prevention standards must Federal facilities comply?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... MANAGEMENT REGULATION REAL PROPERTY 74-FACILITY MANAGEMENT Facility Management Accident and Fire Prevention § 102-74.355 With what accident and fire prevention standards must Federal facilities comply? To the maximum extent feasible, Federal agencies must manage facilities in accordance with the accident and...

  17. 41 CFR 102-74.355 - With what accident and fire prevention standards must Federal facilities comply?

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... MANAGEMENT REGULATION REAL PROPERTY 74-FACILITY MANAGEMENT Facility Management Accident and Fire Prevention § 102-74.355 With what accident and fire prevention standards must Federal facilities comply? To the maximum extent feasible, Federal agencies must manage facilities in accordance with the accident and...

  18. 41 CFR 102-74.355 - With what accident and fire prevention standards must Federal facilities comply?

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... MANAGEMENT REGULATION REAL PROPERTY 74-FACILITY MANAGEMENT Facility Management Accident and Fire Prevention § 102-74.355 With what accident and fire prevention standards must Federal facilities comply? To the maximum extent feasible, Federal agencies must manage facilities in accordance with the accident and...

  19. 41 CFR 102-74.355 - With what accident and fire prevention standards must Federal facilities comply?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... MANAGEMENT REGULATION REAL PROPERTY 74-FACILITY MANAGEMENT Facility Management Accident and Fire Prevention § 102-74.355 With what accident and fire prevention standards must Federal facilities comply? To the maximum extent feasible, Federal agencies must manage facilities in accordance with the accident and...

  20. Installation and first operation of the International Fusion Materials Irradiation Facility injector at the Rokkasho site.

    PubMed

    Gobin, Raphael; Bogard, Daniel; Bolzon, Benoit; Bourdelle, Gilles; Chauvin, Nicolas; Chel, Stéphane; Girardot, Patrick; Gomes, Adelino; Guiho, Patrice; Harrault, Francis; Loiseau, Denis; Lussignol, Yves; Misiara, Nicolas; Roger, Arnaud; Senée, Franck; Valette, Matthieu; Cara, Philippe; Duglué, Daniel; Gex, Dominique; Okumura, Yoshikazu; Ayala, Juan Marcos; Knaster, Juan; Marqueta, Alvaro; Kasugai, Atsushi; O'Hira, Shigeru; Shinto, Katsuhiro; Takahashi, Hiroki

    2016-02-01

    The International Fusion Materials Irradiation Facility (IFMIF) linear IFMIF prototype accelerator injector dedicated to high intensity deuteron beam production has been designed, built, and tested at CEA/Saclay between 2008 and 2012. After the completion of the acceptance tests at Saclay, the injector has been fully sent to Japan. The re-assembly of the injector has been performed between March and May 2014. Then after the check-out phase, the production of the first proton beam occurred in November 2014. Hydrogen and deuteron beam commissioning is now in progress after having proceeded with the final tests on the entire injector equipment including high power diagnostics. This article reports the different phases of the injector installation pointing out the safety and security needs, as well as the first beam production results in Japan and chopper tests. Detailed operation and commissioning results (with H(+) and D(+) 100 keV beams) are reported in a second article. PMID:26931944

  1. Transmutation of Mo, Re, W, Hf, and V in various irradiation test facilities and STARFIRE

    NASA Astrophysics Data System (ADS)

    Greenwood, L. R.; Garner, F. A.

    1994-09-01

    With the exception of V and Cu alloys, the formation of solid transmutants has not been thought to play a large role in the response of metals to irradiation. For a number of refractory elements, however, it appears that very large levels of solid transmutation can occur both in fission and fusion spectra. The phase stability and other properties of alloys can be strong functions of the changing composition. The spectral sensitivity of transmutation also poses some difficulty in correlating data from various neutron spectra. Transmutation of Mo, Re, W, Hf and V have been calculated for the Fast Flux Test Facility (FFTF), the High Flux Isotope Reactor (HFIR), and the STARFIRE fusion reactor. Results show that Re and W undergo sizeable transmutation in these spectra, and may limit the use of these elements in fusion reactor materials. Vanadium and hafnium have high transmutation rates in HFIR and may require spectral tailoring.

  2. Gamma dose measurement in a water phantom irradiated with the BNCT facility at THOR.

    PubMed

    Liu, H M; Hsu, P C; Liaw, T F

    2001-01-01

    It has been proposed that a LiF thermoluminescence dosemeter (TLD) is used as a gamma dosemeter in a water phantom irradiated with the BNCT facility at THOR. Based on the TLD neutron sensitivity and neutron fluxes in the water phantom, which were simulated by the MCNP code, TLD-700 was chosen as a gamma dosemeter in this report. For the correction of the neutron influence on TLD-700, the thermal neutron sensitivity to TLD-700 was investigated with MCNP simulation and the thermal neutron flux was measured with gold foils using the cadmium difference technique. The correction to the neutron influence on the TLD was established on the TLD thermal neutron sensitivity. the thermal neutron flux, and the conversion factor from energy deposition in the TLD to the TLD response. By comparing the experimental data with the thermal neutron influence correction, these data are in very good agreement with the MCNP predictions. PMID:11707034

  3. Installation and first operation of the International Fusion Materials Irradiation Facility injector at the Rokkasho site

    NASA Astrophysics Data System (ADS)

    Gobin, Raphael; Bogard, Daniel; Bolzon, Benoit; Bourdelle, Gilles; Chauvin, Nicolas; Chel, Stéphane; Girardot, Patrick; Gomes, Adelino; Guiho, Patrice; Harrault, Francis; Loiseau, Denis; Lussignol, Yves; Misiara, Nicolas; Roger, Arnaud; Senée, Franck; Valette, Matthieu; Cara, Philippe; Duglué, Daniel; Gex, Dominique; Okumura, Yoshikazu; Marcos Ayala, Juan; Knaster, Juan; Marqueta, Alvaro; Kasugai, Atsushi; O'Hira, Shigeru; Shinto, Katsuhiro; Takahashi, Hiroki

    2016-02-01

    The International Fusion Materials Irradiation Facility (IFMIF) linear IFMIF prototype accelerator injector dedicated to high intensity deuteron beam production has been designed, built, and tested at CEA/Saclay between 2008 and 2012. After the completion of the acceptance tests at Saclay, the injector has been fully sent to Japan. The re-assembly of the injector has been performed between March and May 2014. Then after the check-out phase, the production of the first proton beam occurred in November 2014. Hydrogen and deuteron beam commissioning is now in progress after having proceeded with the final tests on the entire injector equipment including high power diagnostics. This article reports the different phases of the injector installation pointing out the safety and security needs, as well as the first beam production results in Japan and chopper tests. Detailed operation and commissioning results (with H+ and D+ 100 keV beams) are reported in a second article.

  4. Disposal Of Irradiated Cadmium Control Rods From The Plumbrook Reactor Facility

    SciTech Connect

    Posivak, E.J.; Berger, S.R.; Freitag, A.A.

    2008-07-01

    Innovative mixed waste disposition from NASA's Plum Brook Reactor Facility was accomplished without costly repackaging. Irradiated characteristic hardware with contact dose rates as high as 8 Sv/hr was packaged in a HDPE overpack and stored in a Secure Environmental Container during earlier decommissioning efforts, awaiting identification of a suitable pathway. WMG obtained regulatory concurrence that the existing overpack would serve as the macro-encapsulant per 40CFR268.45 Table 1.C. The overpack vent was disabled and the overpack was placed in a stainless steel liner to satisfy overburden slumping requirements. The liner was sealed and placed in shielded shoring for transport to the disposal site in a US DOT Type A cask. Disposition via this innovative method avoided cost, risk, and dose associated with repackaging the high dose irradiated characteristic hardware. In conclusion: WMG accomplished what others said could not be done. Large D and D contractors advised NASA that the cadmium control rods could only be shipped to the proposed Yucca mountain repository. NASA management challenged MOTA to find a more realistic alternative. NASA and MOTA turned to WMG to develop a methodology to disposition the 'hot and nasty' waste that presumably had no path forward. Although WMG lead a team that accomplished the 'impossible', the project could not have been completed with out the patient, supportive management by DOE-EM, NASA, and MOTA. (authors)

  5. Sterilization of allograft bone: is 25 kGy the gold standard for gamma irradiation?

    PubMed

    Nguyen, Huynh; Morgan, David A F; Forwood, Mark R

    2007-01-01

    For several decades, a dose of 25 kGy of gamma irradiation has been recommended for terminal sterilization of medical products, including bone allografts. Practically, the application of a given gamma dose varies from tissue bank to tissue bank. While many banks use 25 kGy, some have adopted a higher dose, while some choose lower doses, and others do not use irradiation for terminal sterilization. A revolution in quality control in the tissue banking industry has occurred in line with development of quality assurance standards. These have resulted in significant reductions in the risk of contamination by microorganisms of final graft products. In light of these developments, there is sufficient rationale to re-establish a new standard dose, sufficient enough to sterilize allograft bone, while minimizing the adverse effects of gamma radiation on tissue properties. Using valid modifications, several authors have applied ISO standards to establish a radiation dose for bone allografts that is specific to systems employed in bone banking. These standards, and their verification, suggest that the actual dose could be significantly reduced from 25 kGy, while maintaining a valid sterility assurance level (SAL) of 10(-6). The current paper reviews the methods that have been used to develop radiation doses for terminal sterilization of medical products, and the current trend for selection of a specific dose for tissue banks. PMID:16821106

  6. 40 CFR 60.5401 - What are the exceptions to the equipment leak standards for affected facilities at onshore...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... equipment leak standards for affected facilities at onshore natural gas processing plants? 60.5401 Section...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Standards of Performance for Crude Oil and Natural Gas... for affected facilities at onshore natural gas processing plants? (a) You may comply with...

  7. 40 CFR 60.5401 - What are the exceptions to the equipment leak standards for affected facilities at onshore...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... equipment leak standards for affected facilities at onshore natural gas processing plants? 60.5401 Section...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Standards of Performance for Crude Oil and Natural Gas... for affected facilities at onshore natural gas processing plants? (a) You may comply with...

  8. A novel facility for 3D micro-irradiation of living cells in a controlled environment by MeV ions

    NASA Astrophysics Data System (ADS)

    Mäckel, V.; Meissl, W.; Ikeda, T.; Clever, M.; Meissl, E.; Kobayashi, T.; Kojima, T. M.; Imamoto, N.; Ogiwara, K.; Yamazaki, Y.

    2014-01-01

    We present a novel facility for micro-irradiation of living targets with ions from a 1.7 MV tandem accelerator. We show results using 1 MeV protons and 2 MeV He2+. In contrast to common micro-irradiation facilities, which use electromagnetic or electrostatic focusing and specially designed vacuum windows, we employ a tapered glass capillary with a thin end window, made from polystyrene with a thickness of 1-2 μm, for ion focusing and extraction. The capillary is connected to a beamline tilted vertically by 45°, which allows for easy immersion of the extracted ions into liquid environment within a standard cell culture dish. An inverted microscope is used for simultaneously observing the samples as well as the capillary tip, while a stage-top incubator provides an appropriate environment for the samples. Furthermore, our setup allows to target volumes in cells within a μm3 resolution, while monitoring the target in real time during and after irradiation.

  9. A novel facility for 3D micro-irradiation of living cells in a controlled environment by MeV ions

    SciTech Connect

    Mäckel, V. Meissl, W.; Ikeda, T.; Meissl, E.; Kobayashi, T.; Kojima, T. M.; Ogiwara, K.; Yamazaki, Y.; Clever, M.; Imamoto, N.

    2014-01-15

    We present a novel facility for micro-irradiation of living targets with ions from a 1.7 MV tandem accelerator. We show results using 1 MeV protons and 2 MeV He{sup 2+}. In contrast to common micro-irradiation facilities, which use electromagnetic or electrostatic focusing and specially designed vacuum windows, we employ a tapered glass capillary with a thin end window, made from polystyrene with a thickness of 1–2 μm, for ion focusing and extraction. The capillary is connected to a beamline tilted vertically by 45°, which allows for easy immersion of the extracted ions into liquid environment within a standard cell culture dish. An inverted microscope is used for simultaneously observing the samples as well as the capillary tip, while a stage-top incubator provides an appropriate environment for the samples. Furthermore, our setup allows to target volumes in cells within a μm{sup 3} resolution, while monitoring the target in real time during and after irradiation.

  10. IFMIF, International Fusion Materials Irradiation Facility conceptual design activity cost report

    SciTech Connect

    Rennich, M.J.

    1996-12-01

    This report documents the cost estimate for the International Fusion Materials Irradiation Facility (IFMIF) at the completion of the Conceptual Design Activity (CDA). The estimate corresponds to the design documented in the Final IFMIF CDA Report. In order to effectively involve all the collaborating parties in the development of the estimate, a preparatory meeting was held at Oak Ridge National Laboratory in March 1996 to jointly establish guidelines to insure that the estimate was uniformly prepared while still permitting each country to use customary costing techniques. These guidelines are described in Section 4. A preliminary cost estimate was issued in July 1996 based on the results of the Second Design Integration Meeting, May 20--27, 1996 at JAERI, Tokai, Japan. This document served as the basis for the final costing and review efforts culminating in a final review during the Third IFMIF Design Integration Meeting, October 14--25, 1996, ENEA, Frascati, Italy. The present estimate is a baseline cost estimate which does not apply to a specific site. A revised cost estimate will be prepared following the assignment of both the site and all the facility responsibilities.

  11. Measurements of X-ray spectra from irradiated gold foils at the OMEGA Laser facility

    NASA Astrophysics Data System (ADS)

    Davis, Joshua; Keiter, Paul; Drake, Paul; Klein, Sallee; Fein, Jeff

    2014-10-01

    In many HED systems high intensity x-rays can be used to measure plasma properties such as density and temperature. At the OMEGA laser facility, these X-rays are produced by irradiating a metal foil with high-intensity lasers, which heats the foil and causes it to act as a quasi-continuum x-ray source for radiography or absorption spectroscopy. As this emission is quasi-continuous and the transmission of x-rays through a material varies with photon energy a well-characterized x-ray source is vital. Therefore, in order to optimize diagnostics reliant upon x-rays it is necessary to gain a better understanding of how the x-ray emission from these targets varies over time and varying beam energy. We will present experimental results studying the effect that beam energy and pulse length have on M-band and sub-keV x-ray emission generated from a 5 μm thick gold disk using time-resolved spectroscopy and a Henway crystal spectrometer. This work is funded by the U.S. Department of Energy, through the NNSA-DS and SC-OFES Joint Program in High-Energy-Density Laboratory Plasmas, Grant Number DE-NA0001840, and the National Laser User Facility Program, Grant Number DE-NA0000850, and through the Laboratory for Laser Energetics, University of Rochester by the NNSA/OICF under Cooperative Agreement No. DE-FC52-08NA28302.

  12. Three-dimensional symmetry analysis of a direct-drive irradiation scheme for the laser megajoule facility

    SciTech Connect

    Ramis, R.; Temporal, M.; Canaud, B.; Brandon, V.

    2014-08-15

    The symmetry of a Direct-Drive (DD) irradiation scheme has been analyzed by means of three-dimensional (3D) simulations carried out by the code MULTI (R. Ramis et al., Comput. Phys. Commun. 49, 475 (1988)) that includes hydrodynamics, heat transport, and 3D laser ray-tracing. The implosion phase of a target irradiated by the Laser Megajoule (LMJ) facility in the context of the Shock Ignition scheme has been considered. The LMJ facility has been designed for Indirect-Drive, and by this reason that the irradiation scheme must be modified when used for DD. Thus, to improve the implosion uniformity to acceptable levels, the beam centerlines should be realigned and the beam power balance should be adjusted. Several alternatives with different levels of complexity are presented and discussed.

  13. 33 CFR 157.304 - Shore-based reception facility: standards.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false Shore-based reception facility: standards. 157.304 Section 157.304 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) POLLUTION RULES FOR THE PROTECTION OF THE MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING OIL IN BULK Exemption From...

  14. 33 CFR 157.304 - Shore-based reception facility: standards.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false Shore-based reception facility: standards. 157.304 Section 157.304 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) POLLUTION RULES FOR THE PROTECTION OF THE MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING OIL IN BULK Exemption From...

  15. 33 CFR 157.304 - Shore-based reception facility: standards.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Shore-based reception facility: standards. 157.304 Section 157.304 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) POLLUTION RULES FOR THE PROTECTION OF THE MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING OIL IN BULK Exemption From...

  16. AMERICAN STANDARD SPECIFICATIONS FOR MAKING BUILDINGS AND FACILITIES ACCESSIBLE TO, AND USABLE BY, THE PHYSICALLY HANDICAPPED.

    ERIC Educational Resources Information Center

    National Easter Seal Society for Crippled Children and Adults, Chicago, IL.

    THIS STANDARD IS INTENDED TO PROVIDE MINIMUM REQUIREMENTS TO BE USED IN THE CONSTRUCTION OF ALL BUILDINGS AND FACILITIES AND FOR ADOPTION AND ENFORCEMENT BY ADMINISTRATIVE AUTHORITIES IN ORDER TO ALLOW INDIVIDUALS WITH PERMANENT PHYSICAL DISABILITIES TO PURSUE THEIR INTERESTS AND ASPIRATIONS, DEVELOP THEIR TALENTS, AND EXERCISE THEIR SKILLS.…

  17. 36 CFR 1150.2 - Applicability: Buildings and facilities subject to guidelines and standards.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 36 Parks, Forests, and Public Property 3 2010-07-01 2010-07-01 false Applicability: Buildings and facilities subject to guidelines and standards. 1150.2 Section 1150.2 Parks, Forests, and Public Property ARCHITECTURAL AND TRANSPORTATION BARRIERS COMPLIANCE BOARD PRACTICE AND PROCEDURES FOR COMPLIANCE HEARINGS General Information §...

  18. 9 CFR 354.210 - Minimum standards for sanitation, facilities, and operating procedures in official plants.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Minimum standards for sanitation, facilities, and operating procedures in official plants. 354.210 Section 354.210 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY ORGANIZATION AND TERMINOLOGY; MANDATORY MEAT AND POULTRY PRODUCTS...

  19. 78 FR 16698 - Chemical Facility Anti-Terrorism Standards (CFATS) Chemical-Terrorism Vulnerability Information...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-18

    ... Information (CVI) for an additional 30 days for public comments. \\1\\ See 77 FR 74685. The 60-day Federal... statutory mandate at 72 FR 17688. Section 550 of the Homeland Security Appropriations Act of 2007 requires a... SECURITY Chemical Facility Anti-Terrorism Standards (CFATS) Chemical- Terrorism Vulnerability...

  20. 40 CFR 267.18 - What are the standards for selecting the location of my facility?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... demonstrating compliance with this standard are specified in 40 CFR 270.14(b)(11). Facilities which are located in political jurisdictions other than those listed in appendix VI of 40 CFR part 264, are assumed to... greater chance of flooding in any given year from any source. (2) “Washout” means the movement...

  1. 40 CFR 267.18 - What are the standards for selecting the location of my facility?

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... demonstrating compliance with this standard are specified in 40 CFR 270.14(b)(11). Facilities which are located in political jurisdictions other than those listed in appendix VI of 40 CFR part 264, are assumed to... greater chance of flooding in any given year from any source. (2) “Washout” means the movement...

  2. 40 CFR 267.18 - What are the standards for selecting the location of my facility?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... demonstrating compliance with this standard are specified in 40 CFR 270.14(b)(11). Facilities which are located in political jurisdictions other than those listed in appendix VI of 40 CFR part 264, are assumed to... greater chance of flooding in any given year from any source. (2) “Washout” means the movement...

  3. 40 CFR 267.18 - What are the standards for selecting the location of my facility?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... demonstrating compliance with this standard are specified in 40 CFR 270.14(b)(11). Facilities which are located in political jurisdictions other than those listed in appendix VI of 40 CFR part 264, are assumed to... greater chance of flooding in any given year from any source. (2) “Washout” means the movement...

  4. 40 CFR 267.18 - What are the standards for selecting the location of my facility?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... demonstrating compliance with this standard are specified in 40 CFR 270.14(b)(11). Facilities which are located in political jurisdictions other than those listed in appendix VI of 40 CFR part 264, are assumed to... greater chance of flooding in any given year from any source. (2) “Washout” means the movement...

  5. 34 CFR 75.683 - Health or safety standards for facilities.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 34 Education 1 2013-07-01 2013-07-01 false Health or safety standards for facilities. 75.683 Section 75.683 Education Office of the Secretary, Department of Education DIRECT GRANT PROGRAMS What Conditions Must Be Met by a Grantee? Other Requirements for Certain Projects § 75.683 Health or...

  6. 34 CFR 75.683 - Health or safety standards for facilities.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 34 Education 1 2012-07-01 2012-07-01 false Health or safety standards for facilities. 75.683 Section 75.683 Education Office of the Secretary, Department of Education DIRECT GRANT PROGRAMS What Conditions Must Be Met by a Grantee? Other Requirements for Certain Projects § 75.683 Health or...

  7. 34 CFR 75.683 - Health or safety standards for facilities.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 34 Education 1 2014-07-01 2014-07-01 false Health or safety standards for facilities. 75.683 Section 75.683 Education Office of the Secretary, Department of Education DIRECT GRANT PROGRAMS What Conditions Must Be Met by a Grantee? Other Requirements for Certain Projects § 75.683 Health or...

  8. 34 CFR 75.683 - Health or safety standards for facilities.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 34 Education 1 2011-07-01 2011-07-01 false Health or safety standards for facilities. 75.683 Section 75.683 Education Office of the Secretary, Department of Education DIRECT GRANT PROGRAMS What Conditions Must Be Met by a Grantee? Other Requirements for Certain Projects § 75.683 Health or...

  9. 34 CFR 75.683 - Health or safety standards for facilities.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 34 Education 1 2010-07-01 2010-07-01 false Health or safety standards for facilities. 75.683 Section 75.683 Education Office of the Secretary, Department of Education DIRECT GRANT PROGRAMS What Conditions Must Be Met by a Grantee? Other Requirements for Certain Projects § 75.683 Health or...

  10. Effects of Aerospace MACT Standard on coating operations at DoD facilities

    SciTech Connect

    Pelton, D.J.; Narayanan, R.

    1997-12-31

    DoD facilities that are a major source of HAPs and that manufacture, repair or rework any aerospace vehicle will have to contend with the aerospace National Emission Standard for Hazardous Air Pollutants (NESHAP). The rule which becomes effective September 1, 1998 requires reductions in volatile organic compounds (VOC) and organic hazardous air pollutants (HAP). Reductions will be achieved by use of primers and topcoats that meet regulatory limits for VOC or organic HAP or using air pollution control systems. At some DoD facilities preparations have been made to comply with the standard when the standard is in effect. The requirements of 40 CFR Part 63 Subpart GG (aerospace NESHAP) are briefly summarized. The impacts that have been experienced at an Air Force base that is currently practicing most of the NESHAP requirements in order to comply with existing state requirements are discussed.

  11. PV Standards Work: Photovoltaic System and Component Certification, Test Facility Accreditation, and Solar Photovoltaic Energy Systems International Standards

    SciTech Connect

    Basso, T. S.; Chalmers, S.; Barikmo, H. O.

    2005-11-01

    This paper discusses efforts led by two companies (PowerMark Corporation and Sunset Technologies Inc.) to support both U.S. domestic and international photovoltaic (PV) system and component certification and test facility accreditation programs and the operation of the International Electrotechnical Commission (IEC) Technical Committee 82 (TC-82) Photovoltaic Energy Systems. International and national PV certification/accreditation programs are successfully facilitating entry of only the highest quality PV products into the marketplace. Standards also continue to be a cornerstone for assuring global PV product conformity assessment, reducing non-tariff trade barriers, and ultimately improving PV products while lowering cost.

  12. Properties of a Cold-Neutron Irradiation Facility for In Vitro Research on Boron Neutron Capture Therapy at the Geesthacht Neutron Facility

    SciTech Connect

    Luedemann, L.; Kampmann, R.; Sosaat, W.; Staron, P.; Wille, P.

    2000-05-15

    A new irradiation facility, GBET (basic research on boron neutron capture therapy), especially designed for in vitro experiments on boron neutron capture therapy was put into operation at the Geesthacht Neutron Facility of the GKSS Research Center. Its location at a cold-neutron guide without direct view of the reactor core has two advantages: First, contamination of the primary beam with fast neutrons or photons is negligible. Second, GBET yields a high cold-neutron flux of 1.4 x 10{sup 8}/(cm{sup 2}.s) over an area of 3 x 4 cm. As a result of the energy dependence of the neutron absorption cross section of boron, this corresponds to a higher effective thermal flux of 4.7 x 10{sup 8}/(cm{sup 2}.s). This effect is used to reduce the irradiation times by a factor of 3.32.The effective flux is sufficient for irradiation of thin samples like cell monolayers in conventional culture flasks. For such in vitro irradiations, a survival fraction of 1% is achieved at a homogeneous boron concentration of 100 ppm {sup 10}B within {approx}20 min. Furthermore, the beam can be used for boron radiography. The respective experimental conditions are discussed, especially the neutron flux distribution, available for these different types of samples.

  13. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    SciTech Connect

    1998-05-01

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

  14. AC-3-irradiation test of sphere-pac and pellet (U,Pu)C fuel in the US Fast Flux Test Facility

    NASA Astrophysics Data System (ADS)

    Bart, G.; Botta, F. B.; Hoth, C. W.; Ledergerber, G.; Mason, R. E.; Stratton, R. W.

    2008-05-01

    The objective of the AC-3 bundle experiment in the Fast Flux Test Facility (FFTF) was to evaluate a fuel fabrication method by 'direct conversion' of nitrate solutions into spherical uranium-plutonium carbide particles and to compare the irradiation performance of 'sphere-pac' fuel pins prepared at Paul Scherrer Institute (PSI) with standard pellet fuel pins fabricated at Los Alamos National Laboratory (LANL). The irradiation and post test examination results show that mixed carbide pellet fuel produced by powder methods and sphere-pac particle fuel developed by internal gelation techniques are both valuable advanced fuel candidates for liquid metal reactors. The PSI fabrication process with direct conversion of actinide nitrate solutions into various sizes of fuel spheres by internal gelation and direct filling of spheres into cladding tubes is seen as more easily transferable to remote operation, showing a significant reduction of process steps. The process is also adaptable for the fabrication of carbonitrides and nitrides (still based on a uranium matrix), as well as for actinides diluted in a (uranium-free) yttrium stabilized zirconium oxide matrix. The AC-3 fuel bundle was irradiated in the Fast Flux Test Facility (FFTF) during the years 1986-1988 for 630 full power days to a peak burn up of ˜8 at.% fissile material. All of the pins, irradiated at linear powers of up to 84 kW/m, with cladding outer temperatures of 465 °C appeared to be in good condition when removed from the assembly. The rebirth of interest for fast reactor systems motivated the earlier teams to report about the excellent, still perfectly relevant results reached; this paper focusing on the sphere-pac fuel behaviour.

  15. Fabrication of (U, Zr) C-fueled/tungsten-clad specimens for irradiation in the Plum Brook Reactor Facility

    NASA Technical Reports Server (NTRS)

    1972-01-01

    Fuel samples, 90UC - 10 ZrC, and chemically vapor deposited tungsten fuel cups were fabricated for the study of the long term dimensional stability and compatibility of the carbide-tungsten fuel-cladding systems under irradiation. These fuel samples and fuel cups were assembled into the fuel pins of two capsules, designated as V-2E and V-2F, for irradiation in NASA Plum Brook Reactor Facility at a fission power density of 172 watts/c.c. and a miximum cladding temperature of 1823 K. Fabrication methods and characteristics of the fuel samples and fuel cups prepared are described.

  16. Development and characteristics of the HANARO neutron irradiation facility for applications in the boron neutron capture therapy field

    NASA Astrophysics Data System (ADS)

    Kim, Myong-Seop; Lee, Byung-Chul; Hwang, Sung-Yul; Kim, Heonil; Jun, Byung-Jin

    2007-05-01

    The HANARO neutron irradiation facility for various applications in the boron neutron capture therapy (BNCT) field was developed, and its characteristics were investigated. In order to obtain the sufficient thermal neutron flux with a low level of contamination by fast neutrons and gamma rays, a radiation filtering method was adopted. The radiation filter was designed by using a silicon single crystal, cooled by liquid nitrogen, and a bismuth crystal. The installation of the main components of the irradiation facility and the irradiation room was finished. Neutron beam characteristics were measured by using bare and cadmium-covered gold foils and wires. The in-phantom neutron flux distribution was measured for flux mapping inside the phantom. The gamma-ray dose was determined by using TLD-700 thermoluminescence dosimeters. The thermal and fast neutron fluxes and the gamma-ray dose were calculated by using the MCNP code, and they were compared with experimental data. The thermal neutron flux and Cd ratio available at this facility were confirmed to be 1.49 × 109 n cm-2 s-1 and 152, respectively. The maximum neutron flux inside the phantom was measured to be 2.79 × 109 n cm-2 s-1 at a depth of 3 mm in the phantom. The two-dimensional in-phantom neutron flux distribution was determined, and significant neutron irradiation was observed within 20 mm from the phantom surface. The gamma-ray dose rate for the free beam condition was expected to be about 80 cGy h-1. These experimental results were reasonably well supported by calculation using the facility design code. This HANARO thermal neutron facility can be used not only for clinical trials, but also for various pre-clinical studies in the BNCT field.

  17. Development and characteristics of the HANARO neutron irradiation facility for applications in the boron neutron capture therapy field.

    PubMed

    Kim, Myong-Seop; Lee, Byung-Chul; Hwang, Sung-Yul; Kim, Heonil; Jun, Byung-Jin

    2007-05-01

    The HANARO neutron irradiation facility for various applications in the boron neutron capture therapy (BNCT) field was developed, and its characteristics were investigated. In order to obtain the sufficient thermal neutron flux with a low level of contamination by fast neutrons and gamma rays, a radiation filtering method was adopted. The radiation filter was designed by using a silicon single crystal, cooled by liquid nitrogen, and a bismuth crystal. The installation of the main components of the irradiation facility and the irradiation room was finished. Neutron beam characteristics were measured by using bare and cadmium-covered gold foils and wires. The in-phantom neutron flux distribution was measured for flux mapping inside the phantom. The gamma-ray dose was determined by using TLD-700 thermoluminescence dosimeters. The thermal and fast neutron fluxes and the gamma-ray dose were calculated by using the MCNP code, and they were compared with experimental data. The thermal neutron flux and Cd ratio available at this facility were confirmed to be 1.49 x 10(9) n cm(-2) s(-1) and 152, respectively. The maximum neutron flux inside the phantom was measured to be 2.79 x 10(9) n cm(-2) s(-1) at a depth of 3 mm in the phantom. The two-dimensional in-phantom neutron flux distribution was determined, and significant neutron irradiation was observed within 20 mm from the phantom surface. The gamma-ray dose rate for the free beam condition was expected to be about 80 cGy h(-1). These experimental results were reasonably well supported by calculation using the facility design code. This HANARO thermal neutron facility can be used not only for clinical trials, but also for various pre-clinical studies in the BNCT field. PMID:17440252

  18. 20 CFR 1001.121 - Performance standard on facilities and support for Veterans' Employment and Training Service...

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 20 Employees' Benefits 3 2011-04-01 2011-04-01 false Performance standard on facilities and support for Veterans' Employment and Training Service (VETS) staff. 1001.121 Section 1001.121 Employees... Eligible Persons § 1001.121 Performance standard on facilities and support for Veterans' Employment...

  19. Standard format and content for emergency plans for fuel cycle and materials facilities

    SciTech Connect

    Not Available

    1990-09-01

    This regulatory guides is being developed to provide guidance acceptable to the NRC staff on the information to be included in emergency plans and to establish a format for presenting the information. Use of a standard format will help ensure uniformity and completeness in the preparation of emergency plans. An acceptable emergency plan should describe the licensed activities conducted at the facility and the types of accidents that might occur. It should provide information on classifying postulated accidents and the licensee's procedures for notifying and coordinating with offsite authorities. The plan should provide information on emergency response measures that might be necessary, the equipment and facilities available to respond to an emergency, and how the licensee will maintain emergency preparedness capability. It should describe the records and reports that will be maintained. There should also be a section on recovery after an accident and plans for restoring the facility to a safe condition. 4 refs.

  20. Standardized Mapping of Nursing Assessments across 59 U.S. Military Treatment Facilities

    PubMed Central

    Harman, Tiffany L.; Seeley, Rachael A.; Oliveira, Ivete M.; Sheide, Amy; Kartchner, Tosh; Woolstenhulme, R. Dean; Wilson, Patricia S.; Lau, Lee Min; Matney, Susan A.

    2012-01-01

    OBJECTIVE: Create an interoperable set of nursing flowsheet assessment measures within military treatment facility electronic health records using the 3M Healthcare Data Dictionary (HDD). DESIGN: The project comprised three phases: 1) discovery included an in-depth analysis of the Essentris data to be mapped in the HDD; 2) mapping encompassed the creation of standard operating procedures, mapping heuristics, and the development of mapping tools; and 3) quality assurance incorporated validation of mappings using inter-rater agreement. RESULTS: Of 569,073 flowsheet concepts, 92% were mapped to the HDD. Of these, 31.5% represented LOINC concepts, 15% represented SNOMED CT and 1% represented both. 52.5% were mapped to HDD concepts with no standardized terminology representations. CONCLUSIONS: Nursing flowsheet data can be mapped to standard terminologies but there is not the breadth of coverage necessary to represent nursing assessments. Future work is necessary to develop a standard information model for the nursing process. PMID:23304303

  1. Pollution control system design for achieving stringent emissions standards on waste incineration facilities -- a case study

    SciTech Connect

    Weaver, E.H.; Bourgoin, S.

    1998-12-31

    In Germany, environmental standards for non-municipal waste incineration are set to not only achieve very low emissions to the atmosphere, but to also ensure that the solid residues generated are of acceptable quality for final disposal and that no liquid effluent is discharged from the system. In order to control pollution from these facilities, an integrated system is required to address the air, liquid and solid regulatory issues. This paper examines one recent facility installed in Germany which incorporates all of the design features required to comply with those standards. The facility examined is an industrial waste incineration facility located at an oil refinery in northeastern Germany. Equipped with a spray dryer absorber, fabric filter, and wet scrubber, the system is designed to achieve HCl emissions of less than 10 mg/Nm{sup 3} and SO{sub 2} emissions of less than 50 mg/Nm{sup 3}. Particulate emissions must be below 10 mg/Nm{sup 3}. The limit for mercury emissions is 50 ug/Nm{sup 3}, while dioxin emissions must be below 0.10 ng/Nm{sup 3}. Purge water from the wet scrubbing system containing salts is dried in the spray dryer absorber and collected as a dry waste in the fabric filter following the spray dryer absorber. The detailed design of the pollution control system is discussed, along with considerations to ensure continuous compliance with allowable emission levels. Operation of the facility is discussed, along with special operating issues that have been encountered since startup. Finally, performance tests and emissions data are presented to illustrate the actual performance level of the facility.

  2. The Case for Standard Irradiated Accretion Disks in Active Galactic Nuclei

    NASA Astrophysics Data System (ADS)

    Chelouche, Doron

    2013-07-01

    We analyze the broadband photometric light curves of Seyfert 1 galaxies from the Sergeev et al. sample and find that (1) perturbations propagating across the continuum emitting region are a general phenomenon securely detected in most cases, (2) it is possible to obtain reliable time delays between continuum emission in different wavebands, which are not biased by the contribution of broad emission lines to the signal, and (3) such lags are consistent with the predictions of standard irradiated accretion disk models, given the optical luminosity of the sources. These findings provide new and independent support for standard accretion disks being responsible for the bulk of the (rest) optical emission in low-luminosity active galactic nuclei (AGNs). We interpret our lag measurements in individual objects within the framework of this model and estimate the typical mass accretion rate to be <~ 0.1 M ⊙ yr&-1, with little dependence on the black hole mass. Assuming bolometric corrections typical of type I sources, we find tentative evidence for the radiative efficiency of accretion flows being a rising function of the black hole mass. With upcoming surveys that will regularly monitor the sky, we may be able to better quantify possible departures from standard self-similar models, and identify other modes of accretion in AGNs.

  3. NOTE: A method for determining the alignment accuracy of the treatment table axis at an isocentric irradiation facility

    NASA Astrophysics Data System (ADS)

    Karger, Christian P.; Hartmann, Günther H.; Heeg, Peter; Jäkel, Oliver

    2001-01-01

    At an isocentric irradiation facility, the rotation axis of the treatment table has to be accurately aligned in vertical orientation to the isocentre, which is usually marked by three perpendicular laser planes. In particular, high precision radiotherapy techniques, such as radiosurgery or intensity modulated radiotherapy, require a higher alignment accuracy of the table axis than routinely specified by the manufacturers. A simple and efficient method is presented to measure the direction and the size of the displacement of the table axis from the isocentre as marked by the lasers. In addition, the inclination of the table axis against the vertical direction can be determined. The measured displacement and inclination provide the required data to correct for possible misalignments of the treatment table axis and to maintain its alignment. Measurements were performed over a period of two years for a treatment table located at the German heavy ion therapy facility. The mean radial distance between the table axis and the isocentre was found to be 0.25±0.25 mm. The mean inclination of the table axis in the XZ- and YZ-planes was measured to be -0.03±0.02° and -0.04±0.01°, respectively. The measurements demonstrate the good alignment of the treatment table over the analysed time period. The described method can be applied to any isocentric irradiation facility, especially including isocentric linear accelerators used for radiosurgery or other high precision irradiation techniques.

  4. Preliminary results from Charpy impact testing of irradiated JPDR weld metal and commissioning of a facility for machining of irradiated materials

    SciTech Connect

    Iskander, S.K.; Hutton, J.T.; Creech, L.E.; Nanstad, R.K.; Manneschmidt, E.T.; Rosseel, T.M.; Bishop, P.S.

    1999-09-01

    Forty two full-size Charpy specimens were machined from eight trepans that originated from the Japan Power Demonstration Reactor (JPDR). They were also successfully tested and the preliminary results are presented in this report. The trends appear to be reasonable with respect to the location of the specimens with regards to whether they originated from the beltline or the core regions of the vessel, and also whether they were from the inside or outside regions of the vessel wall. A short synopsis regarding commissioning of the facility to machine irradiated materials is also provided.

  5. The Constitution, waste facility performance standards, and radioactive waste classification: Is equal protection possible?

    SciTech Connect

    Eye, R.V.

    1993-03-01

    The process for disposal of so-called low-level radioactive waste is deadlocked at present. Supporters of the proposed near-surface facilities assert that their designs will meet minimum legal and regulatory standards currently in effect. Among opponents there is an overarching concern that the proposed waste management facilities will not isolate radiation from the biosphere for an adequate length of time. This clash between legal acceptability and a perceived need to protect the environment and public health by requiring more than the law demand sis one of the underlying reasons why the process is deadlocked. Perhaps the most exhaustive public hearing yet conducted on low-level radioactive waste management has recently concluded in Illinois. The Illinois Low-Level Radioactive Waste Disposal Facility Sitting Commission conducted 71 days of fact-finding hearings on the safety and suitability of a site near Martinsville, Illinois, to serve as a location for disposition of low-level radioactive waste. Ultimately, the siting commission rejected the proposed facility site for several reasons. However, almost all the reasons were related, to the prospect that, as currently conceived, the concrete barrier/shallow-land burial method will not isolate radioactive waste from the biosphere. This paper reviews the relevant legal framework of the radioactive waste classification system and will argue that it is inadequate for long-lived radionuclides. Next, the paper will present a case for altering the classification system based on high-level waste regulatory considerations.

  6. Facility for high heat flux testing of irradiated fusion materials and components using infrared plasma arc lamps

    SciTech Connect

    Sabau, Adrian S; Ohriner, Evan Keith; Kiggans, Jim; Harper, David C; Snead, Lance Lewis; Schaich, Charles Ross

    2014-01-01

    A new high-heat flux testing facility using water-wall stabilized high-power high-pressure argon Plasma Arc Lamps (PALs) has been developed for fusion applications. It can handle irradiated plasma facing component materials and mock-up divertor components. Two PALs currently available at ORNL can provide maximum incident heat fluxes of 4.2 and 27 MW/m2 over a heated area of 9x12 and 1x10 cm2, respectively, which are fusion-prototypical steady state heat flux conditions. The facility will be described and the main differences between the photon-based high-heat flux testing facilities, such as PALs, and the e-beam and particle beam facilities more commonly used for fusion HHF testing are discussed. The components of the test chamber were designed to accommodate radiation safety and materials compatibility requirements posed by high-temperature exposure of low levels irradiated tungsten articles. Issues related to the operation and temperature measurements during testing are presented and discussed.

  7. The OSU Hydro-Mechanical Fuel Test Facility: Standard Fuel Element Testing

    SciTech Connect

    Wade R. Marcum; Brian G. Woods; Ann Marie Phillips; Richard G. Ambrosek; James D. Wiest; Daniel M. Wachs

    2001-10-01

    Oregon State University (OSU) and the Idaho National Laboratory (INL) are currently collaborating on a test program which entails hydro-mechanical testing of a generic plate type fuel element, or standard fuel element (SFE), for the purpose of qualitatively demonstrating mechanical integrity of uranium-molybdenum monolithic plates as compared to that of uranium aluminum dispersion, and aluminum fuel plates due to hydraulic forces. This test program supports ongoing work conducted for/by the fuel development program and will take place at OSU in the Hydro-Mechanical Fuel Test Facility (HMFTF). Discussion of a preliminary test matrix, SFE design, measurement and instrumentation techniques, and facility description are detailed in this paper.

  8. Implant breast reconstruction followed by radiotherapy: Can helical tomotherapy become a standard irradiation treatment?

    SciTech Connect

    Massabeau, Carole; Fournier-Bidoz, Nathalie; Wakil, Georges; Castro Pena, Pablo; Viard, Romain; Zefkili, Sofia; Reyal, Fabien; Campana, Francois; Fourquet, Alain; Kirova, Youlia M.

    2012-01-01

    To evaluate the benefits and limitations of helical tomotherapy (HT) for loco-regional irradiation of patients after a mastectomy and immediate implant-based reconstruction. Ten breast cancer patients with retropectoral implants were randomly selected for this comparative study. Planning target volumes (PTVs) 1 (the volume between the skin and the implant, plus margin) and 2 (supraclavicular, infraclavicular, and internal mammary nodes, plus margin) were 50 Gy in 25 fractions using a standard technique and HT. The extracted dosimetric data were compared using a 2-tailed Wilcoxon matched-pair signed-rank test. Doses for PTV1 and PTV2 were significantly higher with HT (V95 of 98.91 and 97.91%, respectively) compared with the standard technique (77.46 and 72.91%, respectively). Similarly, the indexes of homogeneity were significantly greater with HT (p = 0.002). HT reduced ipsilateral lung volume that received {>=}20 Gy (16.7 vs. 35%), and bilateral lungs (p = 0.01) and neighboring organs received doses that remained well below tolerance levels. The heart volume, which received 25 Gy, was negligible with both techniques. HT can achieve full target coverage while decreasing high doses to the heart and ipsilateral lung. However, the low doses to normal tissue volumes need to be reduced in future studies.

  9. The EB10 10 MeV, 30 kW electron irradiation facility

    NASA Astrophysics Data System (ADS)

    Karlsson, Mikael

    An irradiation plant including a 10 MeV, 30 kW electron accelerator is described. The accelerator is a four stage linac of standing wave type. Using a 90 degrees bending magnet for energy definition it irradiates boxes on a conveyor from below. The system design emphasizes the necessity for documentation of absorbed dose for each irradiated box by continuous monitoring and recording of the beam process parameters. This makes the system well suitable for irradiation sterilization. A magnet at the exit window corrects for the divergent field introduced by the scanning magnet, giving vertical electrons over the full scanning width. This feature provides more uniform irradiation and it also increases the efficiency of the unit by almost 20 %.

  10. National Institute of Standards and Technology Synchrotron Radiation Facilities for Materials Science

    PubMed Central

    Long, Gabrielle G.; Allen, Andrew J.; Black, David R.; Burdette, Harold E.; Fischer, Daniel A.; Spal, Richard D.; Woicik, Joseph C.

    2001-01-01

    Synchrotron Radiation Facilities, supported by the Materials Science and Engineering Laboratory of the National Institute of Standards and Technology, include beam stations at the National Synchrotron Light Source at Brookhaven National Laboratory and at the Advanced Photon Source at Argonne National Laboratory. The emphasis is on materials characterization at the microstructural and at the atomic and molecular levels, where NIST scientists, and researchers from industry, universities and government laboratories perform state-of-the-art x-ray measurements on a broad range of materials.

  11. Facile and fast synthesis of graphene oxide nanosheets via bath ultrasonic irradiation.

    PubMed

    Esmaeili, A; Entezari, M H

    2014-10-15

    For the first time, this work reports a facile sonochemical route in the synthesis of graphene oxide nanosheets (GO) via oxidation of graphite (G). The synthesis of GO was carried out in a fast way under ultrasonic bath irradiation (GO-U). In comparison, the synthesis of GO via classical method (GO-C) was done under the same conditions as ultrasonic method. The products were completely different and the oxidation did not happen the same as way as ultrasonic method. Furthermore, GO was synthesized based on classical approach that most commonly used (GO-C'), not under the same conditions as ultrasonic method. The GO sheets were characterized using UV-Vis, Fourier transform infrared (FT-IR), X-ray diffraction (XRD), transmission electron microscope (TEM), thermal gravimetry (TG), and Raman spectroscopy techniques. The XRD confirms that the spaces between GO-U and GO-C' sheets were higher than graphite. Also, XRD indicated that the GO-U has fewer sheets rather than GO-C'. The TEM observations were confirmed the synthesis of nanosheets. The UV-Vis results were shown the absorption peaks at 230nm for GO-U and GO-C', at 245nm for GO-C, and at 255nm for G. The blue shift in GO-U with respect to G and GO-C can be interpreted based on the higher character of sp(3)/sp(2) in GO-U than G and GO-C. The FT-IR presents the oxygenated functional groups on graphene oxide sheets. A reduction in size of the in-plane sp(2) domains was observed by Raman spectrum. The BET analysis for G, GO-U and GO-C' confirmed that GO-U has a highest specific surface area among all the samples. Therefore, the ultrasonic bath method even with low intensity has a fundamental role in the synthesis of graphene oxide nanosheets and it is relatively fast, simple, cost-effective and efficient as compared to the classical method. PMID:25046404

  12. Construction of a Post-Irradiated Fuel Examination Shielded Enclosure Facility

    SciTech Connect

    Michael A. Lehto, Ph.D.; Boyd D. Christensen

    2008-05-01

    The U.S. Department of Energy (DOE) has committed to provide funding to the Idaho National Laboratory (INL) for new post-irradiation examination (PIE) equipment in support of advanced fuels development. This equipment will allow researchers at the INL to accurately characterize the behavior of experimental test fuels after they are removed from an experimental reactor also located at the INL. The accurate and detailed characterization of the fuel from the reactor, when used in conjunction with computer modeling, will allow DOE to more quickly understand the behavior of the fuel and to guide further development activities consistent with the missions of the INL and DOE. Due to the highly radioactive nature of the specimen samples that will be prepared and analyzed by the PIE equipment, shielded enclosures are required. The shielded cells will be located in the existing Analytical Laboratory (AL) basement (Rooms B-50 and B-51) at the INL Material and Fuels Complex (MFC). AL Rooms B-50 and B-51 will be modified to establish an area where sample containment and shielding will be provided for the analysis of radioactive fuels and materials while providing adequate protection for personnel and the environment. The area is comprised of three separate shielded cells for PIE instrumentation. Each cell contains an atmosphere interface enclosure (AIE) for contamination containment. The shielding will provide a work area consistent with the as-low-as-reasonably-achievable (ALARA) concept, assuming a source term of 10 samples in each of the three shielded areas. Source strength is assumed to be a maximum of 3 Ci at 0.75 MeV gamma for each sample. Each instrument listed below will be installed in an individual shielded enclosure: Shielded electron probe micro-analyzer (EPMA) Focused ion beam instrument (FIB) Micro-scale x-ray diffractometer (MXRD). The project is designed and expected to be built incrementally as funds are allocated. The initial phase will be to fund the

  13. 40 CFR 63.11601 - What are the standards for new and existing paints and allied products manufacturing facilities?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... existing paints and allied products manufacturing facilities? 63.11601 Section 63.11601 Protection of... Hazardous Air Pollutants for Area Sources: Paints and Allied Products Manufacturing Standards, Monitoring... products manufacturing facilities? (a) For each new and existing affected source, you must comply with...

  14. 40 CFR 124.202 - How do I as a facility owner or operator apply for a standardized permit?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 21 2010-07-01 2010-07-01 false How do I as a facility owner or... Permit Applying for A Standardized Permit § 124.202 How do I as a facility owner or operator apply for a standardized permit? (a) You must follow the requirements in this subpart as well as those in § 124.31, 40...

  15. Simulated Irradiation of Samples in HFIR for use as Possible Test Materials in the MPEX (Material Plasma Exposure Experiment) Facility

    SciTech Connect

    Ellis, Ronald James; Rapp, Juergen

    2014-01-01

    The importance of Plasma Material Interaction (PMI) is a major concern in fusion reactor design and analysis. The Material-Plasma Exposure eXperiment (MPEX) facility will explore PMI under fusion reactor plasma conditions. Samples with accumulated displacements per atom (DPA) damage produced by irradiations in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) will be studied in the MPEX facility. The project presented in this paper involved performing assessments of the induced radioactivity and resulting radiation fields of a variety of potential fusion reactor materials. The scientific code packages MCNP and SCALE were used to simulate irradiation of the samples in HFIR; generation and depletion of nuclides in the material and the subsequent composition, activity levels, gamma radiation fields, and resultant dose rates as a function of cooling time. These state-of-the-art simulation methods were used in addressing the challenge of the MPEX project to minimize the radioactive inventory in the preparation of the samples for inclusion in the MPEX facility.

  16. Facility for high-heat flux testing of irradiated fusion materials and components using infrared plasma arc lamps

    NASA Astrophysics Data System (ADS)

    Sabau, Adrian S.; Ohriner, Evan K.; Kiggans, Jim; Harper, David C.; Snead, Lance L.; Schaich, Charles R.

    2014-04-01

    A new high-heat flux testing (HHFT) facility using water-wall stabilized high-power high-pressure argon plasma arc lamps (PALs) has been developed for fusion applications. It can accommodate irradiated plasma facing component materials and sub-size mock-up divertor components. Two PALs currently available at Oak Ridge National Laboratory can provide maximum incident heat fluxes of 4.2 and 27 MW m-2, which are prototypic of fusion steady state heat flux conditions, over a heated area of 9 × 12 and 1 × 10 cm2, respectively. The use of PAL permits the heat source to be environmentally separated from the components of the test chamber, simplifying the design to accommodate safe testing of low-level irradiated articles and materials under high-heat flux. Issues related to the operation and temperature measurements during testing of tungsten samples are presented and discussed. The relative advantages and disadvantages of this photon-based HHFT facility are compared to existing e-beam and particle beam facilities used for similar purposes.

  17. Reconstitution and Upgrade of the Thermal Neutron Irradiation Facility in the Basement Medical Room of the MIT Research Reactor

    SciTech Connect

    Harling, Otto, K.; Riley, Kent, J.; Binns, Peter J.

    2004-12-31

    The M-011 thermal neutron beam has been reconstituted and upgraded to provide a high intensity and high quality facility for preclinical and certain clinical studies. Intensities of thermal neutrons in the beam range from 5.0-8.5 x 109 n cm-2 s-1. Beam contamination is at a low level where it has no practical influence on beam performance. New computer controlled dose and beam monitoring systems have been implemented which assure precise dose delivery and redundant safety interlocks. An additional beam shutter and massive shielding in the back of the medical room have been added which significantly reduce room background and now permit staff entry without the necessity for lowering the reactor power. This system is needed for BNCT research by the MIT group as well as other US groups. This need became acute with the closure of the BMRR which previously had the only high quality thermal neutron irradiation facility for BNCT in the USA.

  18. Development of an ASTM standard guide on performing vulnerability assessments for nuclear facilities

    SciTech Connect

    Wilkey, D.D.

    1995-09-01

    This paper describes an effort undertaken by subcommittee C26.12 (Safeguards) of the American Society for Testing and Materials (ASTM) to develop a standard guide for performing vulnerability assessments (VAs). VAs are performed to determine the effectiveness of safeguards and security systems for both domestic and international nuclear facilities. These assessments address a range of threats, including theft of nuclear material and sabotage, and use an array of methods. The approach to performing and documenting VAs is varied and is largely dependent upon the tools used to perform them. This diversity can lead to tools being misused, making validation of VAs more difficult. The development of a standard guide for performing VAs would, if generally accepted, alleviate these concerns. ASTM provides a forum for developing guides that includes a high level of peer review to assure that the result is acceptable to all potential users. Additionally, the ASTM is widely recognized for setting standards, and endorsement by the Society may increase the likelihood of acceptance by the nuclear community. The goal of this work is to develop a guide that is independent of the tools being used to perform the VA and applicable to the spectrum of threats described above.

  19. Development of an ASTM standard guide on performing vulnerability assessment for nuclear facilities

    SciTech Connect

    Wilkey, D.D.

    1995-12-31

    This paper describes an effort undertaken by subcommittee C26.12 (Safeguards) of the American Society for Testing and Materials (ASTM) to develop a standard guide for performing vulnerability assessments (VAs). VAs are performed to determine the effectiveness of safeguards and security systems for both domestic and international nuclear facilities. These assessments address a range of threats, including theft of nuclear material and sabotage, and use an array of methods. The approach to performing and documenting VAs is varied and is largely dependent upon the tools used to perform them. Ibis diversity can lead to tools being misused, making validation of VAs more difficult. The development of a standard guide for performing VAs would, if generally accepted, alleviate these concerns. ASTM provides a forum for developing guides that includes a high level of peer review to assure that the result is acceptable to all potential users. Additionally, the ASTM is widely recognized for setting standards, and endorsement by the Society may increase the likelihood of acceptance by the nuclear community. The goal of this work is to develop a guide that is independent of the tools being used to perform the VA and applicable to the spectrum of threats described above.

  20. Pain management in a long-term care facility: compliance with JCAHO standards.

    PubMed

    Mullins, Craig R; Wild, Teresa L

    2003-01-01

    An analysis of the treatment of nonmalignant pain in the elderly at a long-term facility was conducted to allow development of a pain management program that complies with both JCAHO guidelines for pain management and with the Tennessee Medicaid (TennCare) reimbursement schedule, and to determine if tramadol can meet the standards of pain management under these new guidelines. Inclusion criteria were residence in our long-term care facility; a pain intensity score > 4 on a modified Wong Baker Pain Scale; the patient having prescription orders for one or more of the following drugs: propoxyphene, meperidine, or high dosages of acetaminophen (approaching 4 g/day); suspected neuropathic or mixed nociceptive/neuropathic pain; and/or a diagnosis of diabetes, osteoarthritis, or degenerative joint disease. Exclusion criteria were history of seizures, history of opioid or alcohol abuse, and demonstrated hypersensitivity to tramadol or opioids. Tramadol administration began at a dose of 25 mg/day titrated up to a maximum of 300 mg/day over a 16-day period. Data were collected from computer records, dispensing reports, medication administration reports (MARs), current federal minimum data set (MDS) data, and weekly care plan meetings. Data were tabulated at baseline and 4-6 weeks after a stable dose of tramadol had been established. Fourteen residents (mean age 85 years, 1 male, 13 female) met the criteria and received tramadol up to 300 mg/day (qid). Tramadol reduced the residents' pain scores from an average of 6 to 2 using the Modified Wong Baker Pain Scale, reduced the percentage of residents taking propoxyphene from 50% to 14%, and reduced those taking high doses of APAP or APAP products from 43% to 14%. Tramadol reduced the percentage of residents falling, losing weight, showing no change or decline in activities in daily living (ADLs), displaying inappropriate behavioral symptoms, suffering depression, and/or taking psychotropic medications. In the state of Tennessee

  1. Shielding design of a treatment room for an accelerator-based epithermal neutron irradiation facility for BNCT.

    PubMed

    Evans, J F; Blue, T E

    1996-11-01

    Protecting the facility personnel and the general public from radiation exposure is a primary safety concern of an accelerator-based epithermal neutron irradiation facility. This work makes an attempt at answering the questions "How much?" and "What kind?" of shielding will meet the occupational limits of such a facility. Shielding effectiveness is compared for ordinary and barytes concretes in combination with and without borated polyethylene. A calculational model was developed of a treatment room , patient "scatterer," and the epithermal neutron beam. The Monte Carlo code, MCNP, was used to compute the total effective dose equivalent rates at specific points of interest outside of the treatment room. A conservative occupational effective dose rate limit of 0.01 mSv h-1 was the guideline for this study. Conservative Monte Carlo calculations show that constructing the treatment room walls with 1.5 m of ordinary concrete, 1.2 m of barytes concrete, 1.0 m of ordinary concrete preceded by 10 cm of 5% boron-polyethylene, or 0.8 m of barytes concrete preceded by 10 cm of 5% boron-polyethylene will adequately protect facility personnel. PMID:8887513

  2. Shielding design of a treatment room for an accelerator-based epithermal neutron irradiation facility for BNCT

    SciTech Connect

    Evans, J.F.; Blue, T.E.

    1996-11-01

    Protecting the facility personnel and the general public from radiation exposure is a primary safety concern of an accelerator-based epithermal neutron irradiation facility. This work makes an attempt at answering the questions {open_quotes}How much?{close_quotes} and {open_quotes}What kind?{close_quotes} of shielding will meet the occupational limits of such a facility. Shielding effectiveness is compared for ordinary and barytes concretes in combination with and without borated polyethylene. A calculational model was developed of a treatment room, patient {open_quotes}scatterer,{close_quotes} and the epithermal neutron beam. The Monte Carlo code, MCNP, was used to compute the total effective dose equivalent rates at specific points of interest outside of the treatment room. A conservative occupational effective dose rate limit of 0.01 mSv h{sup {minus}1} was the guideline for this study. Conservative Monte Carlo calculations show that constructing the treatment room walls with 1.5 m of ordinary concrete, 1.2 m of barytes concrete, 1.0 m of ordinary concrete preceded by 10 cm of 5% boron-polyethylene, or 0.8 m of barytes concrete preceded by 10 cm of 5% boron-polyethylene will adequately protect facility personnel. 20 refs., 8 figs., 2 tabs.

  3. Standard Operating Procedures for Maintaining Cleanliness in a Novel Compact Facility for Breeding SPF Mice

    PubMed Central

    Sakuma, Kenji; Hayashi, Susumu; Otokuni, Keiko; Matsumoto, Izumi; Matsuoka, Hideaki; Saito, Mikako

    2013-01-01

    A compact facility for SPF mice that was not equipped with a large autoclave used disposable mouse cages instead. The SPF clean room was 5.7 × 8.1 × 2.7 m3, with a breeding capacity of 1008 cages (168 cages on each of 6 racks). We evaluated cleanliness in the SPF clean room under the conditions of an occupation rate of 60% to 70% and typically 1 to 3 personnel (maximum, 4 to 6) daily on weekdays. Personnel were taught standard procedures and received training beforehand. During the 15-mo study period, the maximal concentration of airborne particles 0.5 μm or larger was 1.0 × 104 particles/m3 and that of particles 5.0 μm or larger was 5.0 × 102 particles/m3—well below the maximal permissible concentrations of 3.52 × 105 and 2.93 × 103 particles/m3, respectively. During the study period, no mice exhibited clinical symptoms of infection. Testing of 2 representative, overtly healthy mice for 16 pathogens including Staphylococcus aureus, Pseudomonas aeruginosa, and Helicobacter bilis failed to detect any of the target agents. The current study demonstrates the feasibility of the compact facility for breeding SPF mice in the academic environment. PMID:24351759

  4. 76 FR 60390 - Irradiation Treatment; Location of Facilities in the Southern United States

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-29

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF AGRICULTURE... (APHIS) of the U.S. Department of Agriculture administers these regulations. Irradiation Treatment in... of tropical fruits from Thailand in either Thailand or the United States. Fruit from India...

  5. RELAP5 Model of a Two-phase ThermoSyphon Experimental Facility for Fuels and Materials Irradiation

    SciTech Connect

    Carbajo, Juan J; McDuffee, Joel Lee

    2013-01-01

    The High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) does not have a separate materials-irradiation flow loop and requires most materials and all fuel experiments to be placed inside a containment. This is necessary to ensure that internal contaminants such as fission products cannot be released into the primary coolant. As part of the safety basis justification, HFIR also requires that all experiments be able to withstand various accident conditions (e.g., loss of coolant) without generating vapor bubbles on the surface of the experiment in the primary coolant. As with any parallel flow system, HFIR is vulnerable to flow excursion events when vapor is generated in one of those flow paths. The effects of these requirements are to artificially increase experiment temperatures by introducing a barrier between the experimental materials and the HFIR coolant and to reduce experiment heat loads to ensure boiling doesn t occur. A new experimental facility for materials irradiation and testing in the HFIR is currently being developed to overcome these limitations. The new facility is unique in that it will have its own internal cooling flow totally independent of the reactor primary coolant and boiling is permitted. The reactor primary coolant will cool the outside of this facility without contacting the materials inside. The ThermoSyphon Test Loop (TSTL), a full scale prototype of the proposed irradiation facility to be tested outside the reactor, is being designed and fabricated (Ref. 1). The TSTL is a closed system working as a two-phase thermosyphon. A schematic is shown in Fig. 1. The bottom central part is the boiler/evaporator and contains three electric heaters. The vapor generated by the heaters will rise and be condensed in the upper condenser, the condensate will drain down the side walls and be circulated via a downcomer back into the bottom of the boiler. An external flow system provides coolant that simulates the HFIR primary coolant

  6. Energy spectra of the pneumatically positioned neutron sources at LLNL's Hazards control standards and calibration facility

    SciTech Connect

    Thorngate, J.H.

    1987-06-15

    The Hazards Control Department of Lawrence Livermore National Laboratory maintains a Standards and Calibration Laboratory that includes three neutron sources (two /sup 252/Cf and one /sup 238/PuBe that can be positioned pneumatically for irradiations. Ten moderators exist to modify the neutron energy spectra produced by these sources. The thicknesses and materials of these moderators are: 25-cm water; 5-, 10-, 15-, and 25-cm heavy water; 20-cm aluminum; and 2-, 5-, 10-, and 15-cm polyethylene. We used a multisphere spectrometer to measure the neutron spectra at 2 m from both the PuBe source and the smaller Cf source, with the sources bare, and in all of the moderators. These data were reduced in 25 energy groups ranging from 0.25 eV to 16 MeV. Except for the 15-m polyethylene moderator, we also made measurements using a liquid-scintillator fast-neutron spectrometer. These data were reduced in 0.1-MeV increments from 0.5 to 12.5 MeV. Spectra from the measurements and from independent calculations are presented in tabular and graphic form. Dosimetric values, calculated from both the measured and calculated spectra, are also presented.

  7. MCNP study for epithermal neutron irradiation of an isolated liver at the Finnish BNCT facility.

    PubMed

    Kotiluoto, P; Auterinen, I

    2004-11-01

    A successful boron neutron capture treatment (BNCT) of a patient with multiple liver metastases has been first given in Italy, by placing the removed organ into the thermal neutron column of the Triga research reactor of the University of Pavia. In Finland, FiR 1 Triga reactor with an epithermal neutron beam well suited for BNCT has been extensively used to irradiate patients with brain tumors such as glioblastoma and recently also head and neck tumors. In this work we have studied by MCNP Monte Carlo simulations, whether it would be beneficial to treat an isolated liver with epithermal neutrons instead of thermal ones. The results show, that the epithermal field penetrates deeper into the liver and creates a build-up distribution of the boron dose. Our results strongly encourage further studying of irradiation arrangement of an isolated liver with epithermal neutron fields. PMID:15308144

  8. Preliminary results of proton beam characterization for a facility of broad beam in vitro cell irradiation

    NASA Astrophysics Data System (ADS)

    Wéra, A.-C.; Donato, K.; Michiels, C.; Jongen, Y.; Lucas, S.

    2008-05-01

    The interaction of charged particles with living matter needs to be well understood for medical applications. Particularly, it is useful to study how ion beams interact with tissues in terms of damage, dose released and dose rate. One way to evaluate the biological effects induced by an ion beam is by the irradiation of cultured cells at a particle accelerator, where cells can be exposed to different ions at different energies and flux. In this paper, we report the first results concerning the characterization of a broad proton beam obtained with our 2 MV tandem accelerator. For broad beam in vitro cell irradiation, the beam has to be stable over time, uniform over a ∼0.5 cm2 surface, and a dose rate ranging from 0.1 to 10 Gy/min must be achievable. Results concerning the level of achievement of these requirements are presented in this paper for a 1 MeV proton beam.

  9. Facile Synthesis of Silver Nanoparticles Under {gamma}-Irradiation: Effect of Chitosan Concentration

    SciTech Connect

    Huang, N. M.; Radiman, S.; Ahmad, A.; Idris, H.; Lim, H. N.; Khiew, P. S.; Chiu, W. S.; Tan, T. K.

    2009-06-01

    In the present study, a biopolymer, low molecular weight chitosan had been utilized as a 'green' stabilizing agent for the synthesis of silver nanoparticles under {gamma}-irradiation. The as-synthesized silver nanoparticles have particle diameters in the range of 5 nm-30 nm depending on the percentage of chitosan used (0.1 wt%, 0.5 wt%, 1.0 wt% and 2.0 wt%). It was found that the yield of the silver nanoparticles was in accordance with the concentration of chitosan presence in the solution due to the reduction by the chitosan radical during irradiation. The highly stable chitosan encapsulated silver nanoparticles were characterized using transmission electron microscopy (TEM), UV-Visible spectrophotometer (UV-VIS) and X-ray diffraction spectroscopy (XRD)

  10. CSER-98-002: Criticality analysis for the storage of special nuclear material sources and standards in the WRAP facility

    SciTech Connect

    GOLDBERG, H.J.

    1999-05-18

    The Waste Receiving and Processing (WRAP) Facility will store uranium and transuranic (TRU) sources and standards for certification that WRAP meets the requirements of the Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP). In addition, WRAP must meet internal requirements for testing and validation of measuring instruments for nondestructive assay (NDA). In order to be certified for WIPP, WRAP will participate in the NDA Performance Demonstration Program (PDP). This program is a blind test of the NDA capabilities for TRU waste. It is intended to ensure that the NDA capabilities of this facility satisfy the requirements of the quality assurance program plan for the WIPP. The PDP standards have been provided by the Los Alamos National Laboratory (LANL) for this program. These standards will be used in the WRAP facility.

  11. Safety Basis Requirements for Nonnuclear Facilities at Lawrence Livermore National Laboratory Site-Specific Work Smart Standards Revision 1

    SciTech Connect

    Beach, R; Brereton, S; Failor, R; Hildum, S; Spagnolo, S; Van Warmerdam, C

    2003-02-24

    This standard establishes requirements that, when coupled with Lawrence Livermore National Laboratory's (LLNL's) Integrated Safety Management System (ISMS) methods and other Work Smart Standards for assuring worker safety, assure that the impacts of nonnuclear operations authorized in LLNL facilities are well understood and controlled in a manner that protects the health of workers, the public, and the environment. All LLNL facilities shall be classified based on potential for adverse impact of operations to the health of co-located (i.e., nearby) workers and the public in accordance with this standard, Title 10 Code of Federal Regulations (10 CFR) 830, Subpart B, and Department of Energy Order (DOE O) 420.2A. This standard provides information on: Objectives; Applicability; Safety analysis requirements; Control selection and maintenance; Documentation requirements; Safety basis review, approval, and renewal; and Safety basis implementation.

  12. Facility for fast neutron irradiation tests of electronics at the ISIS spallation neutron source

    SciTech Connect

    Andreani, C.; Pietropaolo, A.; Salsano, A.; Gorini, G.; Tardocchi, M.; Paccagnella, A.; Gerardin, S.; Frost, C. D.; Ansell, S.; Platt, S. P.

    2008-03-17

    The VESUVIO beam line at the ISIS spallation neutron source was set up for neutron irradiation tests in the neutron energy range above 10 MeV. The neutron flux and energy spectrum were shown, in benchmark activation measurements, to provide a neutron spectrum similar to the ambient one at sea level, but with an enhancement in intensity of a factor of 10{sup 7}. Such conditions are suitable for accelerated testing of electronic components, as was demonstrated here by measurements of soft error rates in recent technology field programable gate arrays.

  13. Measurement of ion species in high current ECR H+/D+ ion source for IFMIF (International Fusion Materials Irradiation Facility)

    NASA Astrophysics Data System (ADS)

    Shinto, K.; Senée, F.; Ayala, J.-M.; Bolzon, B.; Chauvin, N.; Gobin, R.; Ichimiya, R.; Ihara, A.; Ikeda, Y.; Kasugai, A.; Kitano, T.; Kondo, K.; Marqueta, A.; Okumura, Y.; Takahashi, H.; Valette, M.

    2016-02-01

    Ion species ratio of high current positive hydrogen/deuterium ion beams extracted from an electron-cyclotron-resonance ion source for International Fusion Materials Irradiation Facility accelerator was measured by the Doppler shift Balmer-α line spectroscopy. The proton (H+) ratio at the middle of the low energy beam transport reached 80% at the hydrogen ion beam extraction of 100 keV/160 mA and the deuteron (D+) ratio reached 75% at the deuterium ion beam extraction of 100 keV/113 mA. It is found that the H+ ratio measured by the spectroscopy gives lower than that derived from the phase-space diagram measured by an Allison scanner type emittance monitor. The H+/D+ ratio estimated by the emittance monitor was more than 90% at those extraction currents.

  14. Facile synthesis of Ag/ZnO heterostructures assisted by UV irradiation: Highly photocatalytic property and enhanced photostability

    SciTech Connect

    Yang, Zhongmei; Zhang, Ping; Ding, Yanhuai; Jiang, Yong; Long, Zhilin; Dai, Wenli

    2011-10-15

    Highlights: {yields} Fabrication of Ag/ZnO heterostructure between the two incompatible phases is realized under UV irradiation in the absence of surfactant. {yields} The synthetic method is facile, low cost, and low carbon, which depends on the photogenerated electrons produced by ZnO under UV light. {yields} Photocatalytic property of the as-synthesized samples is 3.0 times as good as the pure ZnO synthesized under the same condition or the commercial TiO{sub 2} (Degussa, P-25). {yields} The heterostructures exhibit good durability without significant change in the activity even after the third cycle compared to the pure ZnO. -- Abstract: We report a new method to synthesize Ag/ZnO heterostructures assisted by UV irradiation. The formation of Ag/ZnO heterostructures depends on photogenerated electrons produced by ZnO under UV light to reduce high valence silver. Functional property of the Ag/ZnO heterostructures is evaluated by photodegradation of methylene blue (MB) under UV illumination. Results of photodegradation tests reveal that the optimal photocatalytic activity of as-syntheszied samples is about 1.5 times higher than the pure ZnO synthesized in the same condition or commercial TiO{sub 2} (P-25), showing the advantage of the unique structure in the Ag/ZnO heterostructure. Besides, due to the reduced activation of surface oxygen atom, photocatalytic activity of the photocatalysts has no evident decrease even after three recycles.

  15. Irradiation Test Plan for the ATR National Scientific User Facility - University of Wisconsin Pilot Project

    SciTech Connect

    Heather J. MacLean; Kumar Sridharan; Timothy A. Hyde

    2008-06-01

    The performance of advanced nuclear systems critically relies on the performance of the materials used for cladding, duct, and other structural components. In many proposed advanced systems, the reactor design pushes the temperature and the total radiation dose higher than typically seen in a light water reactor. Understanding the stability of these materials under radiation is critical. There are a large number of materials or material systems that have been developed for greater high temperature or high dose performance for which little or no information on radiation response exists. The goal of this experiment is to provide initial data on the radiation response of these materials. The objective of the UW experiment is to irradiate materials of interest for advanced reactor applications at a variety of temperatures (nominally 300°C, 400°C, 500°C, and 700°C) and total dose accumulations (nominally 3 dpa and 6 dpa). Insertion of this irradiation test is proposed for September 2008 (ATR Cycle 143A).

  16. Irradiation performance of Fast Flux Test Facility drivers using D9 alloy

    SciTech Connect

    Pitner, A.L.; Gneiting, B.C.; Bard, F.E.

    1994-06-01

    Six test assemblies similar in design to the FFTF driver assembly but employing the advanced alloy D9 in place of Type 316 stainless steel for duct, cladding, and wire wrap material were irradiated to demonstrate the improved performance and lifetime capability of this design. A single pinhole-type breach was incurred in one of the high exposure tests after a peak fuel burnup of 155 MWd/kgM and peak fast neutron fluence of 25 {times} 10{sup 22} n/cm{sup 2} (E > 0.1 MeV). Postirradiation examinations were performed on four of the test assemblies and measured results were compared to analytical evaluations. A revised swelling correlation for D9 Alloy was developed to provide improved agreement between calculated and measured cladding deformation results. A fuel pin lifetime design criterion of 5% calculated hoop strain was derived. Alternatively, fuel pin lifetimes were developed for two irradiation parameters using statistical failure analyses. For a 99.99% reliability, the analyses indicated a peak fast fluence lifetime of 21.0 {times} 10{sup 22} n/cm{sup 2}, or a peak fuel burnup greater than 120 MWd/kgM. The extended lifetime capability of this design would reduce fuel supply requirements for the FFTF by a third relative to the reference driver design.

  17. A state-of-the-art epithermal neutron irradiation facility for neutron capture therapy.

    PubMed

    Riley, K J; Binns, P J; Harling, O K

    2004-08-21

    At the Massachusetts Institute of Technology (MIT) the first fission converter-based epithermal neutron beam (FCB) has proven suitable for use in clinical trials of boron neutron capture therapy (BNCT). The modern facility provides a high intensity beam together with low levels of contamination that is ideally suited for use with future, more selective boron delivery agents. Prescriptions for normal tissue tolerance doses consist of 2 or 3 fields lasting less than 10 min each with the currently available beam intensity, that are administered with an automated beam monitoring and control system to help ensure safety of the patient and staff alike. A quality assurance program ensures proper functioning of all instrumentation and safety interlocks as well as constancy of beam output relative to routine calibrations. Beam line shutters and the medical room walls provide sufficient shielding to enable access and use of the facility without affecting other experiments or normal operation of the multipurpose research reactor at MIT. Medical expertise and a large population in the greater Boston area are situated conveniently close to the university, which operates the research reactor 24 h a day for approximately 300 days per year. The operational characteristics of the facility closely match those established for conventional radiotherapy, which together with a near optimum beam performance ensure that the FCB is capable of determining whether the radiobiological promise of NCT can be realized in routine practice. PMID:15446801

  18. 7 CFR 353.9 - Standards for accreditation of non-government facilities to perform laboratory seed health...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 5 2010-01-01 2010-01-01 false Standards for accreditation of non-government facilities to perform laboratory seed health testing and seed crop phytosanitary inspection. 353.9 Section 353.9 Agriculture Regulations of the Department of Agriculture (Continued) ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE...

  19. 7 CFR 353.9 - Standards for accreditation of non-government facilities to perform laboratory seed health...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 7 Agriculture 5 2014-01-01 2014-01-01 false Standards for accreditation of non-government facilities to perform laboratory seed health testing and seed crop phytosanitary inspection. 353.9 Section 353.9 Agriculture Regulations of the Department of Agriculture (Continued) ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE...

  20. 7 CFR 353.9 - Standards for accreditation of non-government facilities to perform laboratory seed health...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 7 Agriculture 5 2013-01-01 2013-01-01 false Standards for accreditation of non-government facilities to perform laboratory seed health testing and seed crop phytosanitary inspection. 353.9 Section 353.9 Agriculture Regulations of the Department of Agriculture (Continued) ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE...

  1. 7 CFR 353.9 - Standards for accreditation of non-government facilities to perform laboratory seed health...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 7 Agriculture 5 2012-01-01 2012-01-01 false Standards for accreditation of non-government facilities to perform laboratory seed health testing and seed crop phytosanitary inspection. 353.9 Section 353.9 Agriculture Regulations of the Department of Agriculture (Continued) ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE...

  2. A Guide for Developing Standard Operating Job Procedures for the Screening & Grinding Process Wastewater Treatment Facility. SOJP No. 1.

    ERIC Educational Resources Information Center

    Deal, Gerald A.; Montgomery, James A.

    This guide describes standard operating job procedures for the screening and grinding process of wastewater treatment facilities. The objective of this process is the removal of coarse materials from the raw waste stream for the protection of subsequent equipment and processes. The guide gives step-by-step instructions for safety inspection,…

  3. A Guide for Developing Standard Operating Job Procedures for the Sludge Thickening Process Wastewater Treatment Facility. SOJP No. 9.

    ERIC Educational Resources Information Center

    Schwing, Carl M.

    This guide describes standard operating job procedures for the screening and grinding process of wastewater treatment facilities. The objective of this process is the removal of coarse materials from the raw waste stream for the protection of subsequent equipment and processes. The guide gives step-by-step instructions for safety inspection,…

  4. A Guide for Developing Standard Operating Job Procedures for the Sludge Conditioning & Dewatering Process Wastewater Treatment Facility. SOJP No. 11.

    ERIC Educational Resources Information Center

    Schwing, Carl M.

    This guide describes standard operating job procedures for the sludge conditioning and dewatering process of wastewater treatment facilities. In this process, sludge is treated with chemicals to make the sludge coagulate and give up its water more easily. The treated sludge is then dewatered using a vacuum filter. The guide gives step-by-step…

  5. 41 CFR 102-76.65 - What standards must facilities subject to the Architectural Barriers Act meet?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... CFR part 1191 (ABA Chapters 1 and 2, and Chapters 3 through 10) as the Architectural Barriers Act... REGULATION REAL PROPERTY 76-DESIGN AND CONSTRUCTION Architectural Barriers Act § 102-76.65 What standards... facilities subject to the Architectural Barriers Act meet? 102-76.65 Section 102-76.65 Public Contracts...

  6. 41 CFR 102-76.65 - What standards must facilities subject to the Architectural Barriers Act meet?

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... CFR part 1191 (ABA Chapters 1 and 2, and Chapters 3 through 10) as the Architectural Barriers Act... REGULATION REAL PROPERTY 76-DESIGN AND CONSTRUCTION Architectural Barriers Act § 102-76.65 What standards... facilities subject to the Architectural Barriers Act meet? 102-76.65 Section 102-76.65 Public Contracts...

  7. 41 CFR 102-76.65 - What standards must facilities subject to the Architectural Barriers Act meet?

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... CFR part 1191 (ABA Chapters 1 and 2, and Chapters 3 through 10) as the Architectural Barriers Act... REGULATION REAL PROPERTY 76-DESIGN AND CONSTRUCTION Architectural Barriers Act § 102-76.65 What standards... facilities subject to the Architectural Barriers Act meet? 102-76.65 Section 102-76.65 Public Contracts...

  8. 41 CFR 102-76.65 - What standards must facilities subject to the Architectural Barriers Act meet?

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... CFR part 1191 (ABA Chapters 1 and 2, and Chapters 3 through 10) as the Architectural Barriers Act... REGULATION REAL PROPERTY 76-DESIGN AND CONSTRUCTION Architectural Barriers Act § 102-76.65 What standards... facilities subject to the Architectural Barriers Act meet? 102-76.65 Section 102-76.65 Public Contracts...

  9. A Guide for Developing Standard Operating Job Procedures for the Digestion Process Wastewater Treatment Facility. SOJP No. 10.

    ERIC Educational Resources Information Center

    Schwing, Carl M.

    This guide describes standard operating job procedures for the digestion process of wastewater treatment facilities. This process is for reducing the volume of sludge to be treated in subsequent units and to reduce the volatile content of sludge. The guide gives step-by-step instructions for pre-startup, startup, continuous operating, shutdown,…

  10. 30 CFR 941.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 30 Mineral Resources 3 2014-07-01 2014-07-01 false Special performance standards-coal processing plants and support facilities not located at or near the minesite or not within the permit area for a mine. 941.827 Section 941.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR...

  11. 40 CFR 60.5400 - What equipment leak standards apply to affected facilities at an onshore natural gas processing...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... affected facilities at an onshore natural gas processing plant? 60.5400 Section 60.5400 Protection of... NEW STATIONARY SOURCES Standards of Performance for Crude Oil and Natural Gas Production, Transmission... natural gas processing plant? This section applies to the group of all equipment, except...

  12. 40 CFR 60.5400 - What equipment leak standards apply to affected facilities at an onshore natural gas processing...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... affected facilities at an onshore natural gas processing plant? 60.5400 Section 60.5400 Protection of... NEW STATIONARY SOURCES Standards of Performance for Crude Oil and Natural Gas Production, Transmission... natural gas processing plant? This section applies to the group of all equipment, except...

  13. Irradiation facility at the TRIGA Mainz for treatment of liver metastases.

    PubMed

    Hampel, G; Wortmann, B; Blaickner, M; Knorr, J; Kratz, J V; Lizón Aguilar, A; Minouchehr, S; Nagels, S; Otto, G; Schmidberger, H; Schütz, C; Vogtländer, L

    2009-07-01

    The TRIGA Mark II reactor at the University of Mainz provides ideal conditions for duplicating BNCT treatment as performed in Pavia, Italy, in 2001 and 2003 [Pinelli, T., Zonta, A., Altieri, S., Barni, S., Braghieri, A., Pedroni, P., Bruschi, P., Chiari, P., Ferrari, C., Fossati, F., Nano, R., Ngnitejeu Tata, S., Prati, U., Ricevuti, G., Roveda, L., Zonta, C., 2002. TAOrMINA: from the first idea to the application to the human liver. In: Sauerwein et al. (Eds.), Research and Development in Neutron Capture Therapy. Proceedings of the 10th International Congress on Neutron Capture Therapy, Monduzzi editore, Bologna, pp. 1065-1072]. In order to determine the optimal parameters for the planned therapy and therefore for the design of the thermal column, calculations were conducted using the MCNP-code and the transport code ATTILA. The results of the parameter study as well as a possible configuration for the irradiation of the liver are presented. PMID:19394836

  14. Development of an x-ray irradiation port for biomedical applications at the CUEBIT facility

    NASA Astrophysics Data System (ADS)

    Medlin, D.; Heffron, W.; Siegel, A.; Wilson, K.; Klingenberger, A.; Gall, A.; Rusin, M.; Dean, D.; Takacs, E.

    2015-01-01

    Because of the importance of x-ray interactions in modern medicine, efforts must be made to combine the fields of biology and physics. This paper reviews the development of an x-ray irradiation port that allows us to study the interaction of x-rays generated by highly charged ions with biological material, such as stem and cancer cells. Our goal is to better understand these interactions in order to improve the techniques of x-ray therapy by narrowing and specifically selecting the range of radiation energies applied. Using the Clemson University Electron Beam Ion Trap (CUEBIT), the generation of quasi-monochromatic x- rays from highly charged ions is possible. In order to maintain the integrity of the cells being studied, the cell culture needs to be oriented horizontally during the irradiation process. This poses a problem, as the highly charged ion beam generated at the CUEBIT is also oriented horizontally. Therefore, we have designed a system that employs a quadrupole bender that directs the ion beam vertically, which allows for the production of x-rays directly under the cell culture. The experimental station consists of a vacuum chamber that attaches to the end of the beam line. This chamber houses the quadrupole bender, a beryllium window for generating x-rays, and the interface between the beryllium window and the cell culture. X-rays must transmit through the bottom of a flask before they interact with the cells. Hence, we implement a procedure to replace the bottom of the flask with a thin layer of Mylar, allowing x-rays to penetrate through easily. We will use this system to study the effects of monochromatic x- rays on stem cells, cancer cells, and their associated proteins.

  15. Improving measurement quality assurance for photon irradiations at Department of Energy facilities. Final technical report

    SciTech Connect

    1996-05-01

    For radiation-instrument calibration to be generally acceptable throughout the US, direct or indirect traceability to a primary standard is required. In most instances, one of the primary standards established at NIST is employed for this purpose. The Department of Energy Laboratory Accreditation Program (DOELAP) is an example of a program employing dosimetry based on the NIST primary photon-, beta particle- and neutron-dosimetry standards. The NIST primary dosimetry standards for bremsstrahlung were first established in the 1950s. They have been updated since then on several occasions. In the 1970s, Technical Committee 85 of the International Standards Organization (ISO) started its work on establishing sets of internationally acceptable, well-characterized photon beams for the calibration of radiation-protection instruments. It is the intent of this paper to make a detailed comparison between the current NIST and the most up-to-date ISO techniques. At present, 41 bremsstrahlung techniques are specified in ISO 4037 while NIST supports a total of 32 techniques. Given the existing equivalences, it makes sense to try to extend the NIST techniques to cover more of the ISO Narrow Spectrum and High Air-Kerma Rate Series. These extensions will also allow the possibility for use of ISO beam techniques in future revisions of the DOELAP standard, which has been suggested by DOE. To this end, NIST was funded by DOE to procure material and make adaptations to the existing NIST x-ray calibration ranges to allow NIST to have the capability of producing all the ISO bremsstrahlung techniques. The following sections describe the steps that were taken to achieve this.

  16. Streaked radiography of an irradiated foam sample on the National Ignition Facility

    SciTech Connect

    Cooper, A. B. R.; Schneider, M. B.; MacLaren, S. A.; Young, P. E.; Hsing, W. W.; Seugling, R.; Foord, M. E.; Sain, J. D.; May, M. J.; Marrs, R. E.; Maddox, B. R.; Lu, K.; Dodson, K.; Smalyuk, V.; Moore, A. S.; Graham, P.; Foster, J. M.; Back, C. A.; Hund, J. F.

    2013-03-15

    Streaked x-ray radiography images of annular patterns in an evolving tantalum oxide foam under the influence of a driven, subsonic radiation wave were obtained on the National Ignition Facility. This is the first successful radiography measurement of the evolution of well-defined foam features under a driven, subsonic wave in the diffusive regime. A continuous record of the evolution was recorded on an x-ray streak camera, using a slot-apertured point-projection backlighter with an 8 ns nickel source (7.9 keV). Radiography images were obtained for four different annular patterns, which were corrected using a source-dependent flat-field image. The evolution of the foam features was well-modeled using the 3D KULL radiation hydrodynamics code. This experimental and modeling platform can be modified for scaled high-energy-density laboratory astrophysics experiments.

  17. Effects On Beam Alignment Due To Neutron-Irradiated CCD Images At The National Ignition Facility

    SciTech Connect

    Awwal, A; Manuel, A; Datte, P; Burkhart, S

    2011-02-28

    The 192 laser beams in the National Ignition Facility (NIF) are automatically aligned to the target-chamber center using images obtained through charged coupled device (CCD) cameras. Several of these cameras are in and around the target chamber during an experiment. Current experiments for the National Ignition Campaign are attempting to achieve nuclear fusion. Neutron yields from these high energy fusion shots expose the alignment cameras to neutron radiation. The present work explores modeling and predicting laser alignment performance degradation due to neutron radiation effects, and demonstrates techniques to mitigate performance degradation. Camera performance models have been created based on the measured camera noise from the cumulative single-shot fluence at the camera location. We have found that the effect of the neutron-generated noise for all shots to date have been well within the alignment tolerance of half a pixel, and image processing techniques can be utilized to reduce the effect even further on the beam alignment.

  18. Spectral Irradiance Calibration in the Infrared 11: Comparison of (alpha) Boo and 1 Ceres with a Laboratory Standard

    NASA Technical Reports Server (NTRS)

    Witteborn, Fred C.; Cohen, Martin; Bregman, Jess D.; Wooden, Diane; Heere, Karen; Shirley, Eric L.

    1998-01-01

    Infrared spectra of two celestial objects frequently used as flux standards are calibrated against an absolute laboratory flux standard at a spectral resolving power of 100 to 200. The spectrum of the K1.5III star, alpha Boo, is measured from 3 microns to 30 microns and that of the C-type asteroid, 1 Ceres, from 5 microns to 30 microns. While these 'standard' spectra do not have the apparent precision of those based on calculated models, they do not require the assumptions involved in theoretical models of stars and asteroids. Specifically they provide a model-independent means of calibrating celestial flux in the spectral range from 12 microns to 30 microns where accurate absolute photometry is not available. The agreement found between the spectral shapes of alpha Boo and Ceres based on laboratory standards, and those based on observed ratios to alpha CMa (Sirius) and alpha Lyr (Vega), flux calibrated by theoretical modeling of these hot stars strengthens our confidence in the applicability of the stellar models as primary irradiance standards.

  19. Spectral Irradiance Calibration in the Infrared. 11; Comparison of (alpha) Bootis and 1 Ceres with a Laboratory Standard

    NASA Technical Reports Server (NTRS)

    Witteborn, Fred C.; Cohen, Martin; Bregman, Jesse D.; Wooden, Diane H.; Heere, Karen; Shirley, Eric L.

    1999-01-01

    Infrared spectra of two celestial objects frequently used as flux standards are calibrated against an absolute laboratory flux standard at a spectral resolving power of 100 to 200. The spectrum of the KI.5 III star alpha Boo is measured from 3 to 30 microns, and that of the C-type asteroid 1 Ceres from 5 to 30 microns. While these "standard" spectra do not have the apparent precision of those based on calculated models, they do not require the assumptions involved in theoretical models of stars and asteroids. Specifically, they provide a model-independent means of calibrating celestial flux in the spectral range from 12 to 30 microns, where accurate absolute photometry is not available. The agreement found between the spectral shapes of alpha Boo and Ceres based on laboratory standards and those based on observed ratios to alpha CMa (Sirius) and alpha Lyr (Vega), flux-calibrated by theoretical modeling of these hot stars, strengthens our confidence in the applicability of the stellar models as primary irradiance standards.

  20. 41 CFR 102-81.20 - Are the security standards for new Federally owned and leased facilities the same as the...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 41 Public Contracts and Property Management 3 2011-01-01 2011-01-01 false Are the security standards for new Federally owned and leased facilities the same as the standards for existing Federally owned and leased facilities? 102-81.20 Section 102-81.20 Public Contracts and Property Management Federal Property Management Regulations System...

  1. Proposed Reference Spectral Irradiance Standards to Improve Photovoltaic Concentrating System Design and Performance Evaluation: Preprint

    SciTech Connect

    Myers, D. R.; Emery, K. E.; Gueymard, C.

    2002-05-01

    This conference paper describes the American Society for Testing and Materials (ASTM), the International Electrotechnical Commission (IEC), and the International Standards Organization (ISO) standard solar terrestrial spectra (ASTM G-159, IEC-904-3, ISO 9845-1) provide standard spectra for photovoltaic performance applications. Modern terrestrial spectral radiation models and knowledge of atmospheric physics are applied to develop suggested revisions to update the reference spectra. We use a moderately complex radiative transfer model (SMARTS2) to produce the revised spectra. SMARTS2 has been validated against the complex MODTRAN radiative transfer code and spectral measurements. The model is proposed as an adjunct standard to reproduce the reference spectra. The proposed spectra represent typical clear sky spectral conditions associated with sites representing reasonable photovoltaic energy production and weathering and durability climates. The proposed spectra are under consideration by ASTM.

  2. 41 CFR 102-74.165 - What energy standards must Federal agencies follow for existing facilities?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... meet the energy standards prescribed by the American Society of Heating, Refrigerating, and Air Conditioning Engineers and the Illuminating Engineering Society of North American in ASHRAE/IES Standard...

  3. 9 CFR 166.5 - Licensed garbage-treatment facility standards.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... this section. (a) Insects and animals shall be controlled. Accumulation of any material at the facility where insects and rodents may breed is prohibited. (b) Equipment used for handling untreated...

  4. 9 CFR 166.5 - Licensed garbage-treatment facility standards.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... this section. (a) Insects and animals shall be controlled. Accumulation of any material at the facility where insects and rodents may breed is prohibited. (b) Equipment used for handling untreated...

  5. Santa Fe Public Schools Facilities Master Plan. Elementary School Planning Standards.

    ERIC Educational Resources Information Center

    Santa Fe Public Schools, NM.

    This document contains policies and standards to guide the design and evaluation of elementary schools in the Santa Fe Public School District. These policies and standards can be used for a variety of purposes: to serve as a checklist to evaluate existing schools, to identify capital outlay needs to bring all schools to minimum standards, and to…

  6. Hypofractionated whole breast irradiation: new standard in early breast cancer after breast-conserving surgery

    PubMed Central

    Kim, Kyung Su; Shin, Kyung Hwan; Choi, Noorie; Lee, Sea-Won

    2016-01-01

    Hypofractionated whole breast irradiation (HF-WBI) has been proved effective and safe and even better for late or acute radiation toxicity for early breast cancer. Moreover, it improves patient convenience, quality of life and is expected to be advantageous in the medical care system by reducing overall cost. In this review, we examined key randomized trials of HF-WBI, focusing on adequate patient selection as suggested by the American Society of Therapeutic Radiology and Oncology (ASTRO) guideline and the radiobiologic aspects of HF-WBI in relation to its adoption into clinical settings. Further investigation to identify the current practice pattern or cost effectiveness is warranted under the national health insurance service system in Korea. PMID:27306774

  7. Modification of a standard cobalt-60 unit for total body irradiation at 150 cm SSD

    SciTech Connect

    Peters, V.G.; Herer, A.S.

    1984-06-01

    A cobalt-60 teletherapy unit has been modified to permit total body irradiation (TBI) with a vertical beam in a conventional treatment room. This technique has been implemented at low cost using a few easily made accessories. Removal of the adjustable collimator assembly provides a field 2.3 meters in diameter at 150 cm SSD. A copper flattening filter has been constructed to improve beam uniformity and remove electron contamination. Machine set up time for TBI requires less than 15 minutes and does not affect the routine clinical use of the unit. A dose rate of 32 cGy per minute (midplane) is attainable in a 20 cm thick patient. The dosimetry and technical aspects are presented in this paper.

  8. Craniospinal Irradiation Techniques: A Dosimetric Comparison of Proton Beams With Standard and Advanced Photon Radiotherapy

    SciTech Connect

    Yoon, Myonggeun; Shin, Dong Ho; Kim, Jinsung; Kim, Jong Won; Kim, Dae Woong; Park, Sung Yong; Lee, Se Byeong; Kim, Joo Young; Park, Hyeon-Jin; Park, Byung Kiu; Shin, Sang Hoon

    2011-11-01

    Purpose: To evaluate the dosimetric benefits of advanced radiotherapy techniques for craniospinal irradiation in cancer in children. Methods and Materials: Craniospinal irradiation (CSI) using three-dimensional conformal radiotherapy (3D-CRT), tomotherapy (TOMO), and proton beam treatment (PBT) in the scattering mode was planned for each of 10 patients at our institution. Dosimetric benefits and organ-specific radiation-induced cancer risks were based on comparisons of dose-volume histograms (DVHs) and on the application of organ equivalent doses (OEDs), respectively. Results: When we analyzed the organ-at-risk volumes that received 30%, 60%, and 90% of the prescribed dose (PD), we found that PBT was superior to TOMO and 3D-CRT. On average, the doses delivered by PBT to the esophagus, stomach, liver, lung, pancreas, and kidney were 19.4 Gy, 0.6 Gy, 0.3 Gy, 2.5 Gy, 0.2 Gy, and 2.2 Gy for the PD of 36 Gy, respectively, which were significantly lower than the doses delivered by TOMO (22.9 Gy, 4.5 Gy, 6.1 Gy, 4.0 Gy, 13.3 Gy, and 4.9 Gy, respectively) and 3D-CRT (34.6 Gy, 3.6 Gy, 8.0 Gy, 4.6 Gy, 22.9 Gy, and 4.3 Gy, respectively). Although the average doses delivered by PBT to the chest and abdomen were significantly lower than those of 3D-CRT or TOMO, these differences were reduced in the head-and-neck region. OED calculations showed that the risk of secondary cancers in organs such as the stomach, lungs, thyroid, and pancreas was much higher when 3D-CRT or TOMO was used than when PBT was used. Conclusions: Compared with photon techniques, PBT showed improvements in most dosimetric parameters for CSI patients, with lower OEDs to organs at risk.

  9. Controllability of depth dose distribution for neutron capture therapy at the Heavy Water Neutron Irradiation Facility of Kyoto University Research Reactor.

    PubMed

    Sakurai, Yoshinori; Kobayashi, Tooru

    2002-10-01

    The updating construction of the Heavy Water Neutron Irradiation Facility of the Kyoto University Research Reactor has been performed from November 1995 to March 1996 mainly for the improvement in neutron capture therapy. On the performance, the neutron irradiation modes with the variable energy spectra from almost pure thermal to epi-thermal neutrons became available by the control of the heavy-water thickness in the spectrum shifter and by the open-and-close of the cadmium and boral thermal neutron filters. The depth distributions of thermal, epi-thermal and fast neutron fluxes were measured by activation method using gold and indium, and the depth distributions of gamma-ray absorbed dose rate were measured using thermo-luminescent dosimeter of beryllium oxide for the several irradiation modes. From these measured data, the controllability of the depth dose distribution using the spectrum shifter and the thermal neutron filters was confirmed. PMID:12408308

  10. 76 FR 34720 - Chemical Facility Anti-Terrorism Standards Personnel Surety Program

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-14

    ... for comments was previously published in the Federal Register on June 10, 2009, at 74 FR 27555. A 30-day public notice for comments was published in the Federal Register on April 13, 2010, at 75 FR 18850... Terrorist Screening Records System, 72 FR 47073 (August 22, 2007). High-risk chemical facilities must...

  11. 'BioQuaRT' project: design of a novel in situ protocol for the simultaneous visualisation of chromosomal aberrations and micronuclei after irradiation at microbeam facilities.

    PubMed

    Patrono, C; Monteiro Gil, O; Giesen, U; Langner, F; Pinto, M; Rabus, H; Testa, A

    2015-09-01

    The aim of the 'BioQuaRT' (Biologically weighted Quantities in RadioTherapy) project is to develop measurement techniques for characterising charged particle track structure on different length scales, and to correlate at the cellular level the track structure properties with the biological effects of radiation. This multi-scale approach will allow characterisation of the radiation qualities used in radiotherapy and the related biological effects. Charged-particle microbeam facilities were chosen as the platforms for all radiobiology experiments in the 'BioQuaRT' project, because they allow targeting single cells (or compartments of a cell) with a predefined number of ionising particles and correlating the cell-by-cell induced damage with type and energy of the radiation and with the number of ions per cell. Within this project, a novel in situ protocol was developed for the analysis of the misrepaired and/or unrepaired chromosome damage induced by charged-particle irradiations at the Physikalisch-Technische Bundesanstalt (PTB) ion microbeam facility. Among the cytogenetic biomarkers to detect and estimate radiation-induced DNA damage in radiobiology, chromosomal aberrations and micronuclei were chosen. The characteristics of the PTB irradiation system required the design of a special in situ assay: specific irradiation dishes with a base made from a biofoil 25-µm thick and only 3000-4000 cells seeded and irradiated per dish. This method was developed on Chinese hamster ovary (CHO) cells, one of the most commonly used cell lines in radiobiology in vitro experiments. The present protocol allows the simultaneous scoring of chromosome aberrations and micronuclei on the same irradiated dish. Thanks to its versatility, this method could also be extended to other radiobiological applications besides the single-ion microbeam irradiations. PMID:25877532

  12. Accurate Determination of the TOA Solar Spectral NIR Irradiance Using a Primary Standard Source and the Bouguer-Langley Technique

    NASA Astrophysics Data System (ADS)

    Bolsée, D.; Pereira, N.; Decuyper, W.; Gillotay, D.; Yu, H.; Sperfeld, P.; Pape, S.; Cuevas, E.; Redondas, A.; Hernandéz, Y.; Weber, M.

    2014-07-01

    We describe an instrument dedicated to measuring the top of atmosphere (TOA) solar spectral irradiance (SSI) in the near-infrared (NIR) between 600 nm and 2300 nm at a resolution of 10 nm. Ground-based measurements are performed through atmospheric NIR windows and the TOA SSI values are extrapolated using the Bouguer-Langley technique. The interest in this spectral range arises because it plays a main role in the Earth's radiative budget and also because it is employed to validate models used in solar physics. Moreover, some differences were observed between recent ground-based and space-based instruments that take measurements in the NIR and the reference SOLSPEC(ATLAS3) spectrum. In the 1.6 μm region, the deviations vary from 6 % to 10 %. Our measuring system named IRSPERAD has been designed by Bentham (UK) and has been radiometrically characterized and absolutely calibrated against a blackbody at the Belgian Institute for Space Aeronomy and at the Physikalisch-Technische Bundesanstalt (Germany), respectively. A four-month measurement campaign was carried out at the Izaña Atmospheric Observatory (Canary Islands, 2367 m a.s.l.). A set of top-quality solar measurements was processed to obtain the TOA SSI in the NIR windows. We obtained an average standard uncertainty of 1 % for 0.8 μm< λ<2.3 μm. At 1.6 μm, corresponding to the minimum opacity of the solar photosphere, we obtained an irradiance of 234.31±1.29 mWm-2 nm-1. Between 1.6 μm and 2.3 μm, our measurements show a disagreement varying from 6 % to 8 % relative to ATLAS3, which is not explained by the declared standard uncertainties of the two experiments.

  13. Development of a frit 202 analytic standard for the Defense Waste Processing Facility

    SciTech Connect

    Schumacher, R.F.; Hardy, B.J.; Sproull, J.F.

    1997-03-30

    During the qualification of Frit 202 samples for the `DWPF Cold Runs`, the need for a reliable chemical frit standard became apparent. A standard was prepared by obtaining a quantity of Frit 202 and grinding into a fine powder. This material was homogenized as one slurry material volume, spray dried to prevent segregation, and hydraulically pressed into discs. These discs were fired and packaged into eleven sub-lots containing approximately 2,000 discs per sub-lot. A number of samples were obtained and analyzed by two analytic laboratories. The chemical analyses were carefully reviewed and evaluated by several statistical means. While there were several statistically significant variations between the sub-lots, it is believed that those variations are partially caused by the variability of the analytic method. These discs should provide a reliable standard for future chemical analyses of DWPF Frits similar in comparison to Frit 202. It is recommended that these discs be used as a standard material included with the representative frit sample to the independent chemical analysis laboratory, and the order of use of these standards be from sub-lot eleven to sub-lot four. It is further recommended that the NIST standard material (93a) be employed along with the 202 standard until confidence in the new standard is gained. The NIST standard should also be used when initial use of a new sub-lot is begun. this procedure should continue to the end of the DWPF program or such time as the chemical composition of the frit is extensively modified.

  14. A new facility to realize a nanonewton force standard based on electrostatic methods

    NASA Astrophysics Data System (ADS)

    Nesterov, V.; Mueller, M.; Frumin, L. L.; Brand, U.

    2009-06-01

    A new differential nanoforce facility, based on a disc-pendulum with electrostatic stiffness reduction and an electrostatic force compensation for the measurement of horizontal forces in the range below 1 µN, is presented. First measurements in air over an averaging time of 50 s show a noise level of the facility of 42 pN. The method and the results of measuring the light pressure of a red He-Ne laser with a power of 7 mW (FL = 47 pN) are presented. The force measurement uncertainty of the device is below 5%, for a force to be measured of 1 nN and a measuring duration of 50 s.

  15. Standard design for National Ignition Facility x-ray streak and framing cameras

    SciTech Connect

    Kimbrough, J. R.; Bell, P. M.; Bradley, D. K.; Holder, J. P.; Kalantar, D. K.; MacPhee, A. G.; Telford, S.

    2010-10-15

    The x-ray streak camera and x-ray framing camera for the National Ignition Facility were redesigned to improve electromagnetic pulse hardening, protect high voltage circuits from pressure transients, and maximize the use of common parts and operational software. Both instruments use the same PC104 based controller, interface, power supply, charge coupled device camera, protective hermetically sealed housing, and mechanical interfaces. Communication is over fiber optics with identical facility hardware for both instruments. Each has three triggers that can be either fiber optic or coax. High voltage protection consists of a vacuum sensor to enable the high voltage and pulsed microchannel plate phosphor voltage. In the streak camera, the high voltage is removed after the sweep. Both rely on the hardened aluminum box and a custom power supply to reduce electromagnetic pulse/electromagnetic interference (EMP/EMI) getting into the electronics. In addition, the streak camera has an EMP/EMI shield enclosing the front of the streak tube.

  16. Standard design for National Ignition Facility x-ray streak and framing camerasa)

    NASA Astrophysics Data System (ADS)

    Kimbrough, J. R.; Bell, P. M.; Bradley, D. K.; Holder, J. P.; Kalantar, D. K.; MacPhee, A. G.; Telford, S.

    2010-10-01

    The x-ray streak camera and x-ray framing camera for the National Ignition Facility were redesigned to improve electromagnetic pulse hardening, protect high voltage circuits from pressure transients, and maximize the use of common parts and operational software. Both instruments use the same PC104 based controller, interface, power supply, charge coupled device camera, protective hermetically sealed housing, and mechanical interfaces. Communication is over fiber optics with identical facility hardware for both instruments. Each has three triggers that can be either fiber optic or coax. High voltage protection consists of a vacuum sensor to enable the high voltage and pulsed microchannel plate phosphor voltage. In the streak camera, the high voltage is removed after the sweep. Both rely on the hardened aluminum box and a custom power supply to reduce electromagnetic pulse/electromagnetic interference (EMP/EMI) getting into the electronics. In addition, the streak camera has an EMP/EMI shield enclosing the front of the streak tube.

  17. Radial fast-neutron fluence gradients during rotating 40Ar/39Ar sample irradiation recorded with metallic fluence monitors and geological age standards

    NASA Astrophysics Data System (ADS)

    Rutte, Daniel; Pfänder, Jörg A.; Koleška, Michal; Jonckheere, Raymond; Unterricker, Sepp

    2015-01-01

    the neutron-irradiation parameter J is one of the major uncertainties in 40Ar/39Ar dating. The associated uncertainty of the individual J-value for a sample of unknown age depends on the accuracy of the age of the geological standards, the fast-neutron fluence distribution in the reactor, and the distances between standards and samples during irradiation. While it is generally assumed that rotating irradiation evens out radial neutron fluence gradients, we observed axial and radial variations of the J-values in sample irradiations in the rotating channels of two reactors. To quantify them, we included three-dimensionally distributed metallic fast (Ni) and thermal- (Co) neutron fluence monitors in three irradiations and geological age standards in three more. Two irradiations were carried out under Cd shielding in the FRG1 reactor in Geesthacht, Germany, and four without Cd shielding in the LVR-15 reactor in Řež, Czech Republic. The 58Ni(nf,p)58Co activation reaction and γ-spectrometry of the 811 keV peak associated with the subsequent decay of 58Co to 58Fe allow one to calculate the fast-neutron fluence. The fast-neutron fluences at known positions in the irradiation container correlate with the J-values determined by mass-spectrometric 40Ar/39Ar measurements of the geological age standards. Radial neutron fluence gradients are up to 1.8 %/cm in FRG1 and up to 2.2 %/cm in LVR-15; the corresponding axial gradients are up to 5.9 and 2.1 %/cm. We conclude that sample rotation might not always suffice to meet the needs of high-precision dating and gradient monitoring can be crucial.

  18. Test Standard Revision Update: JESD57, "Procedures for the Measurement of Single-Event Effects in Semiconductor Devices from Heavy-Ion Irradiation"

    NASA Technical Reports Server (NTRS)

    Lauenstein, Jean-Marie

    2015-01-01

    The JEDEC JESD57 test standard, Procedures for the Measurement of Single-Event Effects in Semiconductor Devices from Heavy-Ion Irradiation, is undergoing its first revision since 1996. In this talk, we place this test standard into context with other relevant radiation test standards to show its importance for single-event effect radiation testing for space applications. We show the range of industry, government, and end-user party involvement in the revision. Finally, we highlight some of the key changes being made and discuss the trade-space in which setting standards must be made to be both useful and broadly adopted.

  19. 25 CFR 10.6 - How is the BIA assured that the policies and standards are being applied uniformly and facilities...

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR LAW AND ORDER INDIAN COUNTRY DETENTION FACILITIES AND PROGRAMS...-mandatory detention standards and will document progress on uniform reporting. The BIA Office of Law Enforcement Services will conduct periodic operational evaluations for oversight....

  20. 25 CFR 10.6 - How is the BIA assured that the policies and standards are being applied uniformly and facilities...

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR LAW AND ORDER INDIAN COUNTRY DETENTION FACILITIES AND...-mandatory detention standards and will document progress on uniform reporting. The BIA Office of Law Enforcement Services will conduct periodic operational evaluations for oversight....

  1. 25 CFR 10.6 - How is the BIA assured that the policies and standards are being applied uniformly and facilities...

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR LAW AND ORDER INDIAN COUNTRY DETENTION FACILITIES AND...-mandatory detention standards and will document progress on uniform reporting. The BIA Office of Law Enforcement Services will conduct periodic operational evaluations for oversight....

  2. 25 CFR 10.6 - How is the BIA assured that the policies and standards are being applied uniformly and facilities...

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR LAW AND ORDER INDIAN COUNTRY DETENTION FACILITIES AND...-mandatory detention standards and will document progress on uniform reporting. The BIA Office of Law Enforcement Services will conduct periodic operational evaluations for oversight....

  3. 25 CFR 10.6 - How is the BIA assured that the policies and standards are being applied uniformly and facilities...

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR LAW AND ORDER INDIAN COUNTRY DETENTION FACILITIES AND...-mandatory detention standards and will document progress on uniform reporting. The BIA Office of Law Enforcement Services will conduct periodic operational evaluations for oversight....

  4. 76 FR 23690 - Version One Regional Reliability Standards for Facilities Design, Connections, and Maintenance...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-28

    ... Establishment, Approval, and Enforcement of Electric Reliability Standards, Order No. 672, 71 FR 8662 (Feb. 17, 2006), FERC Stats. & Regs. ] 31,204, at P 290, order on reh'g, Order No. 672-A, 71 FR 19814 (Apr. 18... Maintenance; Protection and Control; and Voltage and Reactive, Notice of Proposed Rulemaking, 75 FR...

  5. 77 FR 75676 - Standard Review Plan for Review of Fuel Cycle Facility License Applications

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-21

    ... Regulatory Commission. ACTION: NUREG revision; extension of comment period. SUMMARY: On December 7, 2012 (77 FR 73060), the U.S. Nuclear Regulatory Commission (NRC), solicited comments on the proposed changes to NUREG- 1520, Revision 1, ``Standard Review Plan (SRP) for the Review of a License Application...

  6. 77 FR 73060 - Standard Review Plan for Review of Fuel Cycle Facility License Applications

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-07

    ... (75 FR 30864), which is also available under ADAMS Accession No. ML101390110. The 2010 SRP revisions... Regulatory Commission. ACTION: NUREG revision; request for comments. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is planning to revise NUREG-1520, Revision 1, ``Standard Review Plan (SRP) for the Review...

  7. Standard design for National Ignition Facility x-ray streak and framing cameras.

    PubMed

    Kimbrough, J R; Bell, P M; Bradley, D K; Holder, J P; Kalantar, D K; MacPhee, A G; Telford, S

    2010-10-01

    The x-ray streak camera and x-ray framing camera for the National Ignition Facility were redesigned to improve electromagnetic pulse hardening, protect high voltage circuits from pressure transients, and maximize the use of common parts and operational software. Both instruments use the same PC104 based controller, interface, power supply, charge coupled device camera, protective hermetically sealed housing, and mechanical interfaces. Communication is over fiber optics with identical facility hardware for both instruments. Each has three triggers that can be either fiber optic or coax. High voltage protection consists of a vacuum sensor to enable the high voltage and pulsed microchannel plate phosphor voltage. In the streak camera, the high voltage is removed after the sweep. Both rely on the hardened aluminum box and a custom power supply to reduce electromagnetic pulse/electromagnetic interference (EMP/EMI) getting into the electronics. In addition, the streak camera has an EMP/EMI shield enclosing the front of the streak tube. PMID:21034058

  8. Method for the calibration of the spectral irradiance of tungsten filament transfer standard sources traceable to synchrotron radiation.

    PubMed

    Anevsky, Sergey; Krutikov, Vladimir; Minaeva, Olga; Minaev, Roman; Senin, Dmitriy; Hollandt, Jörg; Taubert, Dieter R

    2013-07-20

    The spectral irradiance calibration of tungsten strip and spiral filament lamps applying synchrotron radiation revealed that the spectral irradiance in the wavelength range from 280 to 400 nm can be well approximated by blackbody radiation according to Planck's law. Consequently, the spectral irradiance of the filament lamp can then be described by an effective irradiance temperature, which would be beneficial for practical measurements. Including the emissivity of tungsten into the approximation, the model can be expanded to visible and near-infrared wavelength regions. The effective irradiance temperature dependence of the lamp current was investigated and appeared to be close to linear. PMID:23872760

  9. Measurement of the 6Li(n,α) neutron standard cross-section at the GELINA facility

    NASA Astrophysics Data System (ADS)

    Jansson, Kaj; Al-Adili, Ali; Bevilacqua, Riccardo; Gustavsson, Cecilia; Hambsch, Franz-Josef; Pomp, Stephan; Vidali, Marzio

    2016-06-01

    The 6Li(n,α) reaction cross-section is commonly used as a reference cross section. However, it is only considered a neutron standard up to 1MeV. For higher energies, there are discrepancies of several per cents between recent measurements and evaluated data files. In order to extend and establish 6Li(n,α) as a neutron standard above 1MeV these discrepancies must be resolved. Our measurement at the GELINA facility at JRC-IRMM in Geel, Belgium is ongoing. We are using a double twin Frisch-grid setup to detect both α-particles from two 6Li targets and fission products from two 235U reference targets. Our targets have thick backings but are employed in pairs, one forward facing and one backward facing. In this way we still cover, in principle, a solid angle of 4π. We present some preliminary results showing that the existing cross-section data is well reproduced around the resonance at 240 keV. The final data taking will start in the beginning of 2016, when the GELINA facility goes online again after a few months of shut down.

  10. Characterization of the Defense Waste Processing Facility (DWPF) Environmental Assessment (EA) glass Standard Reference Material. Revision 1

    SciTech Connect

    Jantzen, C.M.; Bibler, N.E.; Beam, D.C.; Crawford, C.L.; Pickett, M.A.

    1993-06-01

    Liquid high-level nuclear waste at the Savannah River Site (SRS) will be immobilized by vitrification in borosilicate glass. The glass will be produced and poured into stainless steel canisters in the Defense Waste Processing Facility (DWPF). Other waste form producers, such as West Valley Nuclear Services (WVNS) and the Hanford Waste Vitrification Project (HWVP), will also immobilize high-level radioactive waste in borosilicate glass. The canistered waste will be stored temporarily at each facility for eventual permanent disposal in a geologic repository. The Department of Energy has defined a set of requirements for the canistered waste forms, the Waste Acceptance Product Specifications (WAPS). The current Waste Acceptance Primary Specification (WAPS) 1.3, the product consistency specification, requires the waste form producers to demonstrate control of the consistency of the final waste form using a crushed glass durability test, the Product Consistency Test (PCI). In order to be acceptable, a waste glass must be more durable during PCT analysis than the waste glass identified in the DWPF Environmental Assessment (EA). In order to supply all the waste form producers with the same standard benchmark glass, 1000 pounds of the EA glass was fabricated. The chemical analyses and characterization of the benchmark EA glass are reported. This material is now available to act as a durability and/or redox Standard Reference Material (SRM) for all waste form producers.

  11. 75 FR 80397 - Version One Regional Reliability Standards for Facilities Design, Connections, and Maintenance...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-22

    ... Standards, Order No. 672, 71 FR 8662 (Feb. 17, 2006), FERC Stats. & Regs. ] 31,204, at P 290, order on reh'g, Order No. 672-A, 71 FR 19814 (Apr. 18, 2006), FERC Stats. & Regs. ] 31,212 (2006). As a general matter... Regarding Automatic Time Error Corr., Order No. 723, 74 FR 25442 (May 28, 2009), 127 FERC ] 61,176, at P...

  12. Standard for metal/nonmetal mining and metal mineral processing facilities. 2004 ed.

    SciTech Connect

    2004-07-01

    This standard addresses the protection of diesel-powered equipment and the storage and handling of flammable and combustible liquids at these specialized sites. The 2004 edition consolidates requirements from NFPA 122 and 121 : Standard on Fire Protection for Self-Propelled and Mobile Surface Mining Equipment. Major changes include a new chapter on fire protection of surface metal mineral processing plants. The Standard is also revised to emphasize the use of a fire risk assessment when determining fire protection criteria. Chapter headings are: Administration; Referenced publications; Definitions; General; Fire risk assessment and risk reduction; Fire detection and suppression equipment; Fire protection for diesel-powered equipment in underground mines; Transfer of flammable or combustible liquids in underground mines; Flammable liquid storage in underground mines; Combustible liquid storage in underground mines; Fire suppression for flammable or combustible liquid storage areas in underground mines; Fire protection of surface mobile and self-propelled equipment; and Fire protection of surface metal mineral processing plants. 3 annexes.

  13. Distribution of radionuclides in an iron calibration standard for a free release measurement facility.

    PubMed

    Hult, Mikael; Stroh, Heiko; Marissens, Gerd; Tzika, Faidra; Lutter, Guillaume; Šurán, Jiri; Kovar, Petr; Skala, Lukas; Sud, Jaromír

    2016-03-01

    A Europallet-sized calibration standard composed of 12 grey cast iron tubes contaminated with (60)Co and (110m)Ag with a mass of 246kg was developed. As the tubes were produced through centrifugal casting it was of particular concern to study the distribution of radionuclides in the radial direction of the tubes. This was done by removing 72 small samples (swarf) of ~0.3g each on both the inside and outside of the tubes. All of the samples were measured in the underground laboratory HADES. PMID:26597655

  14. Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins

    NASA Astrophysics Data System (ADS)

    Carmack, W. J.; Chichester, H. M.; Porter, D. L.; Wootan, D. W.

    2016-05-01

    The Mechanistic Fuel Failure (MFF) series of metal fuel irradiations conducted in the Fast Flux Test Facility (FFTF) provides an important comparison between data generated in the Experimental Breeder Reactor (EBR-II) and that expected in a larger-scale fast reactor. The MFF fuel operated with a peak cladding temperature at the top of the fuel column, but developed peak burnup at the centerline of the core. This places the peak fuel temperature midway between the core center and the top of fuel, lower in the fuel column than in EBR-II experiments. Data from the MFF-3 and MFF-5 assemblies are most comparable to the data obtained from the EBR-II X447 experiment. The two X447 pin breaches were strongly influenced by fuel/cladding chemical interaction (FCCI) at the top of the fuel column. Post irradiation examination data from MFF-3 and MFF-5 are presented and compared to historical EBR-II data.

  15. 40 CFR 60.5415 - How do I demonstrate continuous compliance with the standards for my gas well affected facility...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ..., my storage vessel affected facility, and my affected facilities at onshore natural gas processing... Oil and Natural Gas Production, Transmission and Distribution § 60.5415 How do I demonstrate... affected facility, my storage vessel affected facility, and my affected facilities at onshore natural...

  16. 40 CFR 60.5415 - How do I demonstrate continuous compliance with the standards for my gas well affected facility...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ..., my storage vessel affected facility, and my affected facilities at onshore natural gas processing... Oil and Natural Gas Production, Transmission and Distribution § 60.5415 How do I demonstrate... affected facility, my storage vessel affected facility, and my affected facilities at onshore natural...

  17. SECONDARY STANDARD CALIBRATION, MEASUREMENT AND IRRADIATION CAPABILITIES OF THE INDIVIDUAL MONITORING SERVICE AT THE HELMHOLTZ ZENTRUM MÜNCHEN: ASPECTS OF UNCERTAINTY AND AUTOMATION.

    PubMed

    Greiter, M B; Denk, J; Hoedlmoser, H

    2016-09-01

    The individual monitoring service at the Helmholtz Zentrum München has adopted the recommendations of the ISO 4037 and 6980 standards series as base of its dosimetric systems for X-ray, gamma and beta dosimetry. These standards define technical requirements for radiation spectra and measurement processes, but leave flexibility in the implementation of irradiations as well as in the resulting uncertainty in dose or dose rate. This article provides an example for their practical implementation in the Munich IAEA/WHO secondary standard dosimetry laboratory. It focusses on two aspects: automation issues and uncertainties in calibration. PMID:26838065

  18. 48 CFR 9904.414 - Cost accounting standard-cost of money as an element of the cost of facilities capital.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 48 Federal Acquisition Regulations System 7 2010-10-01 2010-10-01 false Cost accounting standard-cost of money as an element of the cost of facilities capital. 9904.414 Section 9904.414 Federal Acquisition Regulations System COST ACCOUNTING STANDARDS BOARD, OFFICE OF FEDERAL PROCUREMENT POLICY, OFFICE OF MANAGEMENT AND BUDGET...

  19. Safety analysis report for the National Low-Temperature Neutron Irradiation Facility (NLTNIF) at the ORNL Bulk Shielding Reactor (BSR)

    SciTech Connect

    Coltman, R.R. Jr.; Kerchner, H.R.; Klabunde, C.E.; Richardson, S.A.

    1986-06-01

    This report provides information concerning: the experiment facility; experiment assembly; instrumentation and controls; materials; radioactivity; shielding; thermodynamics; estimated or measured reactivity effects; procedures; hazards; and quality assurance. (JDB)

  20. ORNL necessary and sufficient standards for environment, safety, and health. Final report of the Identification Team for other industrial, radiological, and non-radiological hazard facilities

    SciTech Connect

    1998-07-01

    This Necessary and Sufficient (N and S) set of standards is for Other Industrial, Radiological, and Non-Radiological Hazard Facilities at Oak Ridge National Laboratory (ORNL). These facility classifications are based on a laboratory-wide approach to classify facilities by hazard category. An analysis of the hazards associated with the facilities at ORNL was conducted in 1993. To identify standards appropriate for these Other Industrial, Radiological, and Non-Radiological Hazard Facilities, the activities conducted in these facilities were assessed, and the hazards associated with the activities were identified. A preliminary hazards list was distributed to all ORNL organizations. The hazards identified in prior hazard analyses are contained in the list, and a category of other was provided in each general hazard area. A workshop to assist organizations in properly completing the list was held. Completed hazard screening lists were compiled for each ORNL division, and a master list was compiled for all Other Industrial, Radiological Hazard, and Non-Radiological facilities and activities. The master list was compared against the results of prior hazard analyses by research and development and environment, safety, and health personnel to ensure completeness. This list, which served as a basis for identifying applicable environment, safety, and health standards, appears in Appendix A.

  1. Managing emissions of active pharmaceutical ingredients from manufacturing facilities: an environmental quality standard approach.

    PubMed

    Murray-Smith, Richard J; Coombe, Vyvyan T; Grönlund, Marie Haag; Waern, Fredrik; Baird, James A

    2012-04-01

    Active pharmaceutical ingredient (API) residues have been found to be widespread in the aquatic environment, albeit in most cases at trace levels, with the route to the environment predominantly being via therapeutic use and subsequent excretion to sewer. Although manufacturing discharges may be a low overall contributor to environmental concentrations, they need to be managed effectively so that they do not adversely affect the local receiving environment. In order to achieve this, a risk-based approach is proposed that identifies the long-term and short-term concentrations, referred to as environmental reference concentrations (ERCs) and maximum tolerable concentrations (MTCs), respectively, of an API which should not be exceeded in the aquatic environment receiving effluent from pharmaceutical manufacturing sites. The ERC approach is based on established environmental quality standard concepts currently used in much national and international legislation. Building on these concepts, the approach takes into account indirect exposure of potential consumers such as fish-eating mammals and humans, as well as primary producers (e.g., algae) and primary and secondary consumers (e.g., invertebrates and fish). Although chronic toxicity data are preferred for ERC derivation, acute data, with appropriate considerations of uncertainty, may be used when chronic data are not available. This approach takes all available information into account, particularly for older established medicines that may predate current regulatory requirements for environmental data, and consequently helps prioritize resources for environmental testing. The ERC approach has been applied to 30 of AstraZeneca's APIs. Merits of the approach are discussed together with opportunities for potential future refinement. PMID:22057894

  2. Fat Necrosis After Partial-Breast Irradiation With Brachytherapy or Electron Irradiation Versus Standard Whole-Breast Radiotherapy-4-Year Results of a Randomized Trial

    SciTech Connect

    Loevey, Katalin Fodor, Janos; Major, Tibor; Szabo, Eva; Orosz, Zsolt; Sulyok, Zoltan; Janvary, Levente; Froehlich, Georgina; Kasler, Miklos; Polgar, Csaba

    2007-11-01

    Purpose: To examine the incidence and clinical relevance of fat necrosis after accelerated partial-breast irradiation (PBI) using interstitial high-dose-rate brachytherapy (HDR-BT) in comparison with partial-breast electron irradiation (ELE) and whole-breast irradiation (WBI). Methods and Materials: Between 1998 and 2004, 258 early-stage breast cancer patients were randomized to receive 50 Gy WBI (n = 130) or PBI (n = 128). The latter consisted of either 7 x 5.2 Gy HDR-BT (n = 88) or 50 Gy ELE (n = 40). The incidence of fat necrosis, its impact on cosmetic outcome, accompanying radiologic features, and clinical symptoms were evaluated. Results: The 4-year actuarial rate of fat necrosis was 31.1% for all patients, and 31.9%, 36.5%, and 17.7% after WBI, HDR-BT and ELE, respectively (p{sub WBI/HDR-BT} = 0.26; p{sub WBI/ELE} = 0.11; p{sub ELE/HDR-BT} = 0.025). The respective rate of asymptomatic fat necrosis was 20.2%, 25.3%, and 10% of patients. The incidence of symptomatic fat necrosis was not significantly different after WBI (8.5%), HDR-BT (11.4%), and ELE (7.5%). Symptomatic fat necrosis was significantly associated with a worse cosmetic outcome, whereas asymptomatic fat necrosis was not. Fat necrosis was detectable with mammography and/or ultrasound in each case. Additional imaging examinations were required in 21% of cases and aspiration cytology in 42%. Conclusions: Asymptomatic fat necrosis is a common adverse event of breast-conserving therapy, having no significant clinical relevance in the majority of the cases. The incidence of both symptomatic and asymptomatic fat necrosis is similar after conventional WBI and accelerated partial-breast HDR-BT.

  3. Study of pixel damages in CCD cameras irradiated at the neutron tomography facility of IPEN-CNEN/SP

    NASA Astrophysics Data System (ADS)

    Pugliesi, R.; Andrade, M. L. G.; Dias, M. S.; Siqueira, P. T. D.; Pereira, M. A. S.

    2015-12-01

    A methodology to investigate damages in CCD sensors caused by radiation beams of neutron tomography facilities is proposed. This methodology has been developed in the facility installed at the nuclear research reactor of IPEN-CNEN/SP, and the damages were evaluated by counting of white spots in images. The damage production rate at the main camera position was evaluated to be in the range between 0.008 and 0.040 damages per second. For this range, only 4 to 20 CCD pixels are damaged per tomography, assuring high quality images for hundreds of tomographs. Since the present methodology is capable of quantifying the damage production rate for each type of radiation, it can also be used in other facilities to improve the radiation shielding close of the CCD sensors.

  4. Facile synthesis of TiO2/microcrystalline cellulose nanocomposites: photocatalytically active material under visible light irradiation

    EPA Science Inventory

    Doped TiO2 nanocomposites were prepared in situ by a facile and simple synthesis utilizing benign and renewable precursors such as microcrystalline cellulose (MC) and TiCl4 through hydrolysis in alkaline medium without the addition of organic solvents. The as-prepared nanocompos...

  5. Facile fabrication of an efficient BiVO4 thin film electrode for water splitting under visible light irradiation.

    PubMed

    Jia, Qingxin; Iwashina, Katsuya; Kudo, Akihiko

    2012-07-17

    An efficient BiVO(4) thin film electrode for overall water splitting was prepared by dipping an F-doped SnO(2) (FTO) substrate electrode in an aqueous nitric acid solution of Bi(NO(3))(3) and NH(4)VO(3), and subsequently calcining it. X-ray diffraction of the BiVO(4) thin film revealed that a photocatalytically active phase of scheelite-monoclinic BiVO(4) was obtained. Scanning electron microscopy images showed that the surface of an FTO substrate was uniformly coated with the BiVO(4) film with 300-400 nm of the thickness. The BiVO(4) thin film electrode gave an excellent anodic photocurrent with 73% of an IPCE at 420 nm at 1.0 V vs. Ag/AgCl. Modification with CoO on the BiVO(4) electrode improved the photoelectrochemical property. A photoelectrochemical cell consisting of the BiVO(4) thin film electrode with and without CoO, and a Pt counter electrode was constructed for water splitting under visible light irradiation and simulated sunlight irradiation. Photocurrent due to water splitting to form H(2) and O(2) was confirmed with applying an external bias smaller than 1.23 V that is a theoretical voltage for electrolysis of water. Water splitting without applying external bias under visible light irradiation was demonstrated using a SrTiO(3)Rh photocathode and the BiVO(4) photoanode. PMID:22699499

  6. Facile fabrication of an efficient BiVO4 thin film electrode for water splitting under visible light irradiation

    PubMed Central

    Jia, Qingxin; Iwashina, Katsuya; Kudo, Akihiko

    2012-01-01

    An efficient BiVO4 thin film electrode for overall water splitting was prepared by dipping an F-doped SnO2 (FTO) substrate electrode in an aqueous nitric acid solution of Bi(NO3)3 and NH4VO3, and subsequently calcining it. X-ray diffraction of the BiVO4 thin film revealed that a photocatalytically active phase of scheelite-monoclinic BiVO4 was obtained. Scanning electron microscopy images showed that the surface of an FTO substrate was uniformly coated with the BiVO4 film with 300–400 nm of the thickness. The BiVO4 thin film electrode gave an excellent anodic photocurrent with 73% of an IPCE at 420 nm at 1.0 V vs. Ag/AgCl. Modification with CoO on the BiVO4 electrode improved the photoelectrochemical property. A photoelectrochemical cell consisting of the BiVO4 thin film electrode with and without CoO, and a Pt counter electrode was constructed for water splitting under visible light irradiation and simulated sunlight irradiation. Photocurrent due to water splitting to form H2 and O2 was confirmed with applying an external bias smaller than 1.23 V that is a theoretical voltage for electrolysis of water. Water splitting without applying external bias under visible light irradiation was demonstrated using a SrTiO3∶Rh photocathode and the BiVO4 photoanode. PMID:22699499

  7. Measurement of ion species in high current ECR H⁺/D⁺ ion source for IFMIF (International Fusion Materials Irradiation Facility).

    PubMed

    Shinto, K; Senée, F; Ayala, J-M; Bolzon, B; Chauvin, N; Gobin, R; Ichimiya, R; Ihara, A; Ikeda, Y; Kasugai, A; Kitano, T; Kondo, K; Marqueta, A; Okumura, Y; Takahashi, H; Valette, M

    2016-02-01

    Ion species ratio of high current positive hydrogen/deuterium ion beams extracted from an electron-cyclotron-resonance ion source for International Fusion Materials Irradiation Facility accelerator was measured by the Doppler shift Balmer-α line spectroscopy. The proton (H(+)) ratio at the middle of the low energy beam transport reached 80% at the hydrogen ion beam extraction of 100 keV/160 mA and the deuteron (D(+)) ratio reached 75% at the deuterium ion beam extraction of 100 keV/113 mA. It is found that the H(+) ratio measured by the spectroscopy gives lower than that derived from the phase-space diagram measured by an Allison scanner type emittance monitor. The H(+)/D(+) ratio estimated by the emittance monitor was more than 90% at those extraction currents. PMID:26931945

  8. Laser stand for irradiation of targets by laser pulses from the Iskra-5 facility at a repetition rate of 100 MHz

    SciTech Connect

    Annenkov, V I; Garanin, Sergey G; Eroshenko, V A; Zhidkov, N V; Zubkov, A V; Kalipanov, S V; Kalmykov, N A; Kovalenko, V P; Krotov, V A; Lapin, S G; Martynenko, S P; Pankratov, V I; Faizullin, V S; Khrustalev, V A; Khudikov, N M; Chebotar, V S

    2009-08-31

    A train of a few tens of high-power subnanosecond laser pulses with a repetition period of 10 ns is generated in the Iskra-5 facility. The laser pulse train has an energy of up to 300 J and contains up to 40 pulses (by the 0.15 intensity level), the single pulse duration in the train being {approx}0.5 ns. The results of experiments on conversion of a train of laser pulses to a train of X-ray pulses are presented. Upon irradiation of a tungsten target, a train of X-ray pulses is generated with the shape of an envelope in the spectral band from 0.18 to 0.28 keV similar to that of the envelope of the laser pulse train. The duration of a single X-ray pulse in the train is equal to that of a single laser pulse. (lasers)

  9. National Fire Codes. A Compilation of NFPA Codes, Standards, Recommended Practices, and Manuals. Volume 4: Building Construction and Facilities. 1969-70.

    ERIC Educational Resources Information Center

    National Fire Protection Association, Boston, MA.

    A selected group of NFPA codes and standards pertaining to building construction and facilities is presented. The recommendations are phrased in terms of performance or objectives, the intent being to permit the utilization of any methods, devices or materials which will produce the desired results. The major topics included are--(1) building…

  10. A Guide for Developing Standard Operating Job Procedures for the Activated Sludge - Aeration & Sedimentation Process Wastewater Treatment Facility. SOJP No. 5.

    ERIC Educational Resources Information Center

    Mason, George J.

    This guide for developing standard operating job procedures for wastewater treatment facilities is devoted to the activated sludge aeration and sedimentation process. This process is for conversion of nonsettleable and nonfloatable materials in wastewater to settleable, floculated biological groups and separation of the settleable solids from the…

  11. Guidelines for Development of Standards for Public School Facilities in the State of Arizona. Research Reports on Educational Administration Volume VI, Number 5.

    ERIC Educational Resources Information Center

    Deever, R. Merwin; Shockley, H. Allen

    The goal of the doctoral dissertation summarized here was to develop a set of recommended guidelines to be used in developing standards and procedures for elementary and secondary public school facility construction in Arizona. The study focuses on determining the essential elements of these guidelines and on determining which of these elements…

  12. International Fusion Materials Irradiation Facility injector acceptance tests at CEA/Saclay: 140 mA/100 keV deuteron beam characterization.

    PubMed

    Gobin, R; Bogard, D; Cara, P; Chauvin, N; Chel, S; Delferrière, O; Harrault, F; Mattei, P; Mosnier, A; Senée, F; Shidara, H; Okumura, Y

    2014-02-01

    In the framework of the ITER broader approach, the International Fusion Materials Irradiation Facility (IFMIF) deuteron accelerator (2 × 125 mA at 40 MeV) is an irradiation tool dedicated to high neutron flux production for future nuclear plant material studies. During the validation phase, the Linear IFMIF Prototype Accelerator (LIPAc) machine will be tested on the Rokkasho site in Japan. This demonstrator aims to produce 125 mA/9 MeV deuteron beam. Involved in the LIPAc project for several years, specialists from CEA/Saclay designed the injector based on a SILHI type ECR source operating at 2.45 GHz and a 2 solenoid low energy beam line to produce such high intensity beam. The whole injector, equipped with its dedicated diagnostics, has been then installed and tested on the Saclay site. Before shipment from Europe to Japan, acceptance tests have been performed in November 2012 with 100 keV deuteron beam and intensity as high as 140 mA in continuous and pulsed mode. In this paper, the emittance measurements done for different duty cycles and different beam intensities will be presented as well as beam species fraction analysis. Then the reinstallation in Japan and commissioning plan on site will be reported. PMID:24593497

  13. Facile synthesis of lead iodide nanostructures by microwave irradiation technique and their structural, morphological, photoluminescence and dielectric studies

    NASA Astrophysics Data System (ADS)

    Shkir, Mohd.; Yahia, I. S.; AlFaify, S.; Abutalib, M. M.; Muhammad, Shabbir

    2016-04-01

    Lead iodide (PbI2) nanostructures have been synthesized by co-precipitation, hydrothermal and rapidly by microwave irradiation techniques. SEM analysis indicated the formation of well aligned nanocrystals and nanorods of average diameter between 100 nm and 400 nm. The powder X-ray diffraction and FT-Raman spectroscopic analysis confirms the formation of a 2H-PbI2 polytypic predominantly. These studies also show that there is no extra phase due to impurity in the synthesized nanostructures. The optical energy band gap of nanostructures prepared by co-precipitation, hydrothermal and microwave irradiation techniques were found to be 2.283, 2.493, 2.542 eV and 2.331. 2.350, 2.375 eV calculated from UV-Vis absorption and diffuse reflectance data, respectively, which shows a clear blue shift in the wavelength due to confinement effect. Photoluminescence spectrum was recorded at different excitation wavelengths and shows clear blue shift in the emission peak which is due to the recombination of free excitons with band to band type transition and also may be due to confinement effect. Further the dielectric studies have been performed and a good enhancement in the dielectric constant has been observed due to small size of the fabricated nanostructures in comparison to bulk material.

  14. Safety Basis Requirements for Nonnuclear Facilities at Lawrence Livermore National Laboratory Site-Specific Work Smart Standard Revision 3 December 2006

    SciTech Connect

    Beach, D; Brereton, S; Failor, R; Hildum, J; Ingram, C; Spagnolo, S; van Warmerdam, C

    2007-06-07

    This standard establishes requirements that, when coupled with Lawrence Livermore National Laboratory's (LLNL's) Integrated Safety Management System (ISMS) methods and other Work Smart Standards for assuring worker safety, assure that the impacts of nonnuclear operations authorized in LLNL facilities are well understood and controlled in a manner that protects the health of workers, the public, and the environment. All LLNL facilities shall be classified based on potential for adverse impact of operations to the health of co-located (i.e., nearby) workers and the public in accordance with this standard, Title 10 Code of Federal Regulations (10 CFR) 830, Subpart B, and Department of Energy Order (DOE O) 420.2A.

  15. The AMINO experiment: methane photolysis under Solar VUV irradiation on the EXPOSE-R facility of the International Space Station

    NASA Astrophysics Data System (ADS)

    Carrasco, Nathalie; Cottin, Hervé; Cloix, Mégane; Jérome, Murielle; Bénilan, Yves; Coll, Patrice; Gazeau, Marie-Claire; Raulin, François; Saiagh, Kafila; Chaput, Didier

    2015-01-01

    The scientific aim of the present campaign is to study the whole chain of methane photo-degradation, as initiated by Solar vacuum-ultraviolet irradiation in Titan's atmosphere. For this purpose, the AMINO experiment on the EXPOSE-R mission has loaded closed cells for gas-phase photochemistry in space conditions. Two different gas mixtures have been exposed, named Titan 1 and Titan 2, involving both N2-CH4 gas mixtures, without and with CO2, respectively. CO2 is added as a source of reactive oxygen in the cells. The cell contents were analysed thanks to infrared absorption spectroscopy, gas chromatography and mass spectrometry. Methane consumption leads to the formation of saturated hydrocarbons, with no detectable influence of CO2. This successful campaign provides a first benchmark for characterizing the whole methane photochemical system in space conditions. A thin film of tholin-like compounds appears to form on the cell walls of the exposed cells.

  16. Contributed Review: Absolute spectral radiance calibration of fiber-optic shock-temperature pyrometers using a coiled-coil irradiance standard lamp

    NASA Astrophysics Data System (ADS)

    Fat'yanov, O. V.; Asimow, P. D.

    2015-10-01

    We describe an accurate and precise calibration procedure for multichannel optical pyrometers such as the 6-channel, 3-ns temporal resolution instrument used in the Caltech experimental geophysics laboratory. We begin with a review of calibration sources for shock temperatures in the 3000-30 000 K range. High-power, coiled tungsten halogen standards of spectral irradiance appear to be the only practical alternative to NIST-traceable tungsten ribbon lamps, which are no longer available with large enough calibrated area. However, non-uniform radiance complicates the use of such coiled lamps for reliable and reproducible calibration of pyrometers that employ imaging or relay optics. Careful analysis of documented methods of shock pyrometer calibration to coiled irradiance standard lamps shows that only one technique, not directly applicable in our case, is free of major radiometric errors. We provide a detailed description of the modified Caltech pyrometer instrument and a procedure for its absolute spectral radiance calibration, accurate to ±5%. We employ a designated central area of a 0.7× demagnified image of a coiled-coil tungsten halogen lamp filament, cross-calibrated against a NIST-traceable tungsten ribbon lamp. We give the results of the cross-calibration along with descriptions of the optical arrangement, data acquisition, and processing. We describe a procedure to characterize the difference between the static and dynamic response of amplified photodetectors, allowing time-dependent photodiode correction factors for spectral radiance histories from shock experiments. We validate correct operation of the modified Caltech pyrometer with actual shock temperature experiments on single-crystal NaCl and MgO and obtain very good agreement with the literature data for these substances. We conclude with a summary of the most essential requirements for error-free calibration of a fiber-optic shock-temperature pyrometer using a high-power coiled tungsten halogen

  17. Contributed Review: Absolute spectral radiance calibration of fiber-optic shock-temperature pyrometers using a coiled-coil irradiance standard lamp.

    PubMed

    Fat'yanov, O V; Asimow, P D

    2015-10-01

    We describe an accurate and precise calibration procedure for multichannel optical pyrometers such as the 6-channel, 3-ns temporal resolution instrument used in the Caltech experimental geophysics laboratory. We begin with a review of calibration sources for shock temperatures in the 3000-30,000 K range. High-power, coiled tungsten halogen standards of spectral irradiance appear to be the only practical alternative to NIST-traceable tungsten ribbon lamps, which are no longer available with large enough calibrated area. However, non-uniform radiance complicates the use of such coiled lamps for reliable and reproducible calibration of pyrometers that employ imaging or relay optics. Careful analysis of documented methods of shock pyrometer calibration to coiled irradiance standard lamps shows that only one technique, not directly applicable in our case, is free of major radiometric errors. We provide a detailed description of the modified Caltech pyrometer instrument and a procedure for its absolute spectral radiance calibration, accurate to ±5%. We employ a designated central area of a 0.7× demagnified image of a coiled-coil tungsten halogen lamp filament, cross-calibrated against a NIST-traceable tungsten ribbon lamp. We give the results of the cross-calibration along with descriptions of the optical arrangement, data acquisition, and processing. We describe a procedure to characterize the difference between the static and dynamic response of amplified photodetectors, allowing time-dependent photodiode correction factors for spectral radiance histories from shock experiments. We validate correct operation of the modified Caltech pyrometer with actual shock temperature experiments on single-crystal NaCl and MgO and obtain very good agreement with the literature data for these substances. We conclude with a summary of the most essential requirements for error-free calibration of a fiber-optic shock-temperature pyrometer using a high-power coiled tungsten halogen

  18. Contributed Review: Absolute spectral radiance calibration of fiber-optic shock-temperature pyrometers using a coiled-coil irradiance standard lamp

    SciTech Connect

    Fat’yanov, O. V. Asimow, P. D.

    2015-10-15

    We describe an accurate and precise calibration procedure for multichannel optical pyrometers such as the 6-channel, 3-ns temporal resolution instrument used in the Caltech experimental geophysics laboratory. We begin with a review of calibration sources for shock temperatures in the 3000-30 000 K range. High-power, coiled tungsten halogen standards of spectral irradiance appear to be the only practical alternative to NIST-traceable tungsten ribbon lamps, which are no longer available with large enough calibrated area. However, non-uniform radiance complicates the use of such coiled lamps for reliable and reproducible calibration of pyrometers that employ imaging or relay optics. Careful analysis of documented methods of shock pyrometer calibration to coiled irradiance standard lamps shows that only one technique, not directly applicable in our case, is free of major radiometric errors. We provide a detailed description of the modified Caltech pyrometer instrument and a procedure for its absolute spectral radiance calibration, accurate to ±5%. We employ a designated central area of a 0.7× demagnified image of a coiled-coil tungsten halogen lamp filament, cross-calibrated against a NIST-traceable tungsten ribbon lamp. We give the results of the cross-calibration along with descriptions of the optical arrangement, data acquisition, and processing. We describe a procedure to characterize the difference between the static and dynamic response of amplified photodetectors, allowing time-dependent photodiode correction factors for spectral radiance histories from shock experiments. We validate correct operation of the modified Caltech pyrometer with actual shock temperature experiments on single-crystal NaCl and MgO and obtain very good agreement with the literature data for these substances. We conclude with a summary of the most essential requirements for error-free calibration of a fiber-optic shock-temperature pyrometer using a high-power coiled tungsten halogen

  19. DECOMMISSIONING OF SHIELDED FACILITIES AT WINFRITH USED FOR POST IRRADIATION EXAMINATION OF NUCLEAR FUELS & OTHER ACTIVE ITEMS

    SciTech Connect

    Miller, K.D.; Parkinson, S.J.; Cornell, R.M.; Staples, A.T.

    2003-02-27

    This paper describes the approaches used in the clearing, cleaning, decontamination and decommissioning of a very large suite of seven concrete shielded caves and other facilities used by UKAEA at Winfrith Technology Centre, England over a period of about 30 years for the postirradiation examination (PIE) of a wide range of nuclear fuels and other very active components. The basic construction of the facilities will first be described, setting the scene for the major challenges that 1970s' thinking posed for decommissioning engineers. The tendency then to use large and heavy items of equipment supported upon massive steel bench structures produced a series of major problems that had to be overcome. The means of solving these problems by utilization of relatively simple and inexpensive equipment will be described. Later, a further set of challenges was experienced to decontaminate the interior surfaces to allow man entries to be undertaken at acceptable dose rates. The paper will describe the types of tooling used and the range of complementary techniques that were employed to steadily reduce the dose rates down to acceptable levels. Some explanations will also be given for the creation of realistic dose budgets and the methods of recording and continuously assessing the progress against these budgets throughout the project. Some final considerations are given to the commercial approaches to be adopted throughout this major project by the decommissioning engineers. Particular emphasis will be given to the selection of equipment and techniques that are effective so that the whole process can be carried out in a cost-effective and timely manner. The paper also provides brief complementary information obtained during the decommissioning of a plutonium-contaminated facility used for a range of semi-experimental purposes in the late 1970s. The main objective here was to remove the alpha contamination in such a manner that the volume of Plutonium Contaminated Materials (P

  20. 30 CFR 910.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or Near...

  1. 30 CFR 922.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities not Located at or near...

  2. 30 CFR 933.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... at or near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or...

  3. 30 CFR 947.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or Near...

  4. 30 CFR 933.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... at or near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or...

  5. 30 CFR 937.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing plants and Support Facilities Not Located at or Near...

  6. 30 CFR 922.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities not Located at or near...

  7. 30 CFR 922.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities not Located at or near...

  8. 30 CFR 921.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... at or near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or...

  9. 30 CFR 910.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or Near...

  10. 30 CFR 939.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... at or near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or...

  11. 30 CFR 910.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or Near...

  12. 30 CFR 933.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... at or near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or...

  13. 30 CFR 939.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... at or near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or...

  14. 30 CFR 947.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or Near...

  15. 30 CFR 921.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... at or near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or...

  16. 30 CFR 937.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing plants and Support Facilities Not Located at or Near...

  17. 30 CFR 947.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or Near...

  18. 30 CFR 937.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing plants and Support Facilities Not Located at or Near...

  19. 30 CFR 921.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... at or near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or...

  20. 30 CFR 939.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a... at or near the minesite or not within the permit area for a mine. Part 827 of this chapter, Special Permanent Program Performance Standards—Coal Processing Plants and Support Facilities Not Located at or...

  1. 10 CFR 170.21 - Schedule of fees for production and utilization facilities, review of standard referenced design...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... facilities or the export only of components for production or utilization facilities issued under 10 CFR part... example, actions under 10 CFR 110.40(b). Application—new license, or amendment; or license exemption... review, for example, those actions under 10 CFR 110.41(a). Application—new license, or amendment;...

  2. X-ray lasing upon two-pulse irradiation of targets on the picosecond SOKOL-P facility

    SciTech Connect

    Andriyash, Aleksandr V; Vikhlyaev, D A; Gavrilov, D S; Dmitrov, D A; Zapysov, A L; Kakshin, A G; Loboda, E A; Lykov, V A; Magda, E P; Politov, V Yu; Potapov, A V; Pronin, V A; Rykovanov, G N; Sukhanov, V N; Tishchenko, A S; Ugodenko, A A; Chefonov, O V

    2006-06-30

    The results of experimental studies of the X-ray lasing on the 3p-3s transitions of neon-like titanium ions are presented. The laser radiation at 1.054 {mu}m was focused to a {approx}30-{mu}m wide line of length from 2 to 8 mm. Plane polished titanium plates were successively irradiated by two pulses: a 400-ps prepulse and a 4-ps main pump pulse delayed by 1.5 ns relative to the prepulse. The total laser energy was 8-10 J. The nanosecond-to-picosecond pulse energy ratio was maintained constant and was equal to 1:3. For a short target length (from 2 to 4 mm), the 326-A line intensity was experimentally observed to grow exponentially with length. The small-signal gain for the X-ray laser radiation is estimated at approximately 30 cm{sup -1}. The X-ray laser beam divergence was equal to about 9 mrad. (lasers)

  3. A Small-Animal Irradiation Facility for Neutron Capture Therapy Research at the RA-3 Research Reactor

    SciTech Connect

    Emiliano Pozzi; David W. Nigg; Marcelo Miller; Silvia I. Thorp; Amanda E. Schwint; Elisa M. Heber; Veronica A. Trivillin; Leandro Zarza; Guillermo Estryk

    2007-11-01

    The National Atomic Energy Commission of Argentina (CNEA) has constructed a thermal neutron source for use in Boron Neutron Capture Therapy (BNCT) applications at the RA-3 research reactor facility located in Buenos Aires. The Idaho National Laboratory (INL) and CNEA have jointly conducted some initial neutronic characterization measurements for one particular configuration of this source. The RA-3 reactor (Figure 1) is an open pool type reactor, with 20% enriched uranium plate-type fuel and light water coolant. A graphite thermal column is situated on one side of the reactor as shown. A tunnel penetrating the graphite structure enables the insertion of samples while the reactor is in normal operation. Samples up to 14 cm height and 15 cm width are accommodated.

  4. High Exposure Facility Technical Description

    SciTech Connect

    Carter, Gregory L.; Stithem, Arthur R.; Murphy, Mark K.; Smith, Alex K.

    2008-02-12

    The High Exposure Facility is a collimated high-level gamma irradiator that is located in the basement of the 318 building. It was custom developed by PNNL back in 1982 to meet the needs for high range radiological instrument calibrations and dosimeter irradiations. At the time no commercially available product existed that could create exposure rates up to 20,000 R/h. This document is intended to pass on the design criteria that was employed to create this unique facility, while maintaining compliance with ANSI N543-1974, "General Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV."

  5. [Food irradiation].

    PubMed

    Migdał, W

    1995-01-01

    A worldwide standard on food irradiation was adopted in 1983 by Codex Alimentarius Commission of the Joint Food Standard Programme of the Food and Agriculture Organization (FAO) of the United Nations and the World Health Organization (WHO). As a result, 41 countries have approved the use of irradiation for treating one or more food items and the number is increasing. Generally, irradiation is used to: food loses, food spoilage, disinfestation, safety and hygiene. The number of countries which use irradiation for processing food for commercial purposes has been increasing steadily from 19 in 1987 to 33 today. In the frames of the national programme on the application of irradiation for food preservation and hygienization an experimental plant for electron beam processing has been established in Institute of Nuclear Chemistry and Technology. The plant is equipped with a small research accelerator Pilot (19MeV, 1 kW) and an industrial unit Elektronika (10MeV, 10 kW). On the basis of the research there were performed at different scientific institutions in Poland, health authorities have issued permission for irradiation for: spices, garlic, onions, mushrooms, potatoes, dry mushrooms and vegetables. PMID:8619113

  6. Synthesis of ZnO nanorod–nanosheet composite via facile hydrothermal method and their photocatalytic activities under visible-light irradiation

    SciTech Connect

    Tan, Wai Kian; Abdul Razak, Khairunisak; Lockman, Zainovia; Kawamura, Go; Muto, Hiroyuki; Matsuda, Atsunori

    2014-03-15

    ZnO composite films consisting of ZnO nanorods and nanosheets were prepared by low-temperature hydrothermal processing at 80 °C on seeded glass substrates. The seed layer was coated on glass substrates by sol–gel dip-coating and pre-heated at 300 °C for 10 min prior to hydrothermal growth. The size of the grain formed after pre-heat treatment was ∼40 nm. A preferred orientation seed layer at the c-axis was obtained, which promoted vertical growth of the ZnO nanorod arrays and formation of the ZnO nanosheets. X-ray diffraction patterns and high-resolution transmission electron microscope (HR-TEM) images confirmed that the ZnO nanorods and nanosheets consist of single crystalline and polycrystalline structures, respectively. Room temperature photoluminescence spectra of the ZnO nanorod–nanosheet composite films exhibited band-edge ultraviolet (UV) and visible emission (blue and green) indicating the formation of ZnO crystals with good crystallinity and are supported by Raman scattering results. The formation of one-dimensional (1D) ZnO nanorod arrays and two-dimensional (2D) ZnO nanosheet films using seeded substrates in a single low-temperature hydrothermal step would be beneficial for realization of device applications that utilize substrates with limited temperature stability. The ZnO nanorods and nanosheets composite structure demonstrated higher photocatalytic activity during degradation of aqueous methylene blue under visible-light irradiation. -- Graphical abstract: Schematic illustration of ZnO nanorod–nanosheet composite structure formation by hydrothermal at low-temperature of 80 °C against time. Highlights: • Novel simultaneous formation of ZnO nanorods and nanosheets composite structure. • Facile single hydrothermal step formation at low-temperature. • Photoluminescence showed ultraviolet and visible emission. • Feasible application on substrates with low temperature stability. • Improved photocatalytic activity under visible

  7. 30 CFR 941.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ..., DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE SOUTH DAKOTA § 941.827 Special performance standards—coal processing plants and support facilities not...

  8. 30 CFR 941.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ..., DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE SOUTH DAKOTA § 941.827 Special performance standards—coal processing plants and support facilities not...

  9. 78 FR 8987 - Standards To Prevent, Detect, and Respond to Sexual Abuse and Assault in Confinement Facilities...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-07

    ...; ] DEPARTMENT OF HOMELAND SECURITY 6 CFR Part 115 RIN 1653-AA65 Standards To Prevent, Detect, and Respond to..., DHS proposed to issue regulations setting standards to prevent, detect, and respond to sexual abuse... SUPPLEMENTARY INFORMATION section in the NPRM (77 FR 75300) for further information on how to comment on...

  10. 77 FR 75299 - Standards To Prevent, Detect, and Respond to Sexual Abuse and Assault in Confinement Facilities

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-19

    ... ] DOJ Department of Justice ERO Enforcement and Removal Operations FR Federal Register HHS Department of... proposed rule proffering national standards as required under PREA. 75 FR 11077 (Mar. 10, 2010). Throughout...) setting forth proposed national PREA standards. 76 FR 6248 (Feb. 3, 2011). The DOJ NPRM solicited...

  11. 20 CFR 1001.121 - Performance standard on facilities and support for Veterans' Employment and Training Service...

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... support for Veterans' Employment and Training Service (VETS) staff. 1001.121 Section 1001.121 Employees... Training Service (VETS) staff. Each State agency shall provide adequate and appropriate facilities and administrative support such as office space, furniture, telephone, equipment, and supplies to VETS staff....

  12. 10 CFR 170.21 - Schedule of fees for production and utilization facilities, review of standard referenced design...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 CFR Part 110. 1. Application for import or export of production and utilization facilities 4... review, for example, actions under 10 CFR 110.40(b). Application—new license, or amendment; or license... Branch review only, for example, those actions under 10 CFR 110.41(a)(1)-(8). Application—new license,...

  13. 10 CFR 170.21 - Schedule of fees for production and utilization facilities, review of standard referenced design...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 CFR Part 110. 1. Application for import or export of production and utilization facilities 4... review, for example, actions under 10 CFR 110.40(b). Application—new license, or amendment; or license... Branch review only, for example, those actions under 10 CFR 110.41(a)(1)-(8). Application—new license,...

  14. 30 CFR 939.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 939.827 Section 939.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  15. 30 CFR 912.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 912.827 Section 912.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  16. 30 CFR 947.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 947.827 Section 947.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  17. 30 CFR 941.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 941.827 Section 941.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  18. 30 CFR 910.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 910.827 Section 910.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  19. 30 CFR 941.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 941.827 Section 941.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  20. 30 CFR 910.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 910.827 Section 910.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  1. 30 CFR 921.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 921.827 Section 921.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH...

  2. 30 CFR 921.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 921.827 Section 921.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH...

  3. 30 CFR 937.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 937.827 Section 937.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  4. 30 CFR 922.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 922.827 Section 922.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  5. 30 CFR 937.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 937.827 Section 937.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  6. 30 CFR 922.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 922.827 Section 922.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  7. 30 CFR 933.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 933.827 Section 933.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  8. 30 CFR 912.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 912.827 Section 912.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  9. 30 CFR 939.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 939.827 Section 939.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  10. 30 CFR 947.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 947.827 Section 947.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  11. 30 CFR 933.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 933.827 Section 933.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE...

  12. 41 CFR 102-76.65 - What standards must facilities subject to the Architectural Barriers Act meet?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... CFR part 1191 (ABA Chapters 1 and 2, and Chapters 3 through 10) as the Architectural Barriers Act... facilities subject to the Architectural Barriers Act meet? 102-76.65 Section 102-76.65 Public Contracts and... REGULATION REAL PROPERTY 76-DESIGN AND CONSTRUCTION Architectural Barriers Act § 102-76.65 What...

  13. 10 CFR 170.21 - Schedule of fees for production and utilization facilities, review of standard referenced design...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 CFR part 110. 1. Application for import or export of production and utilization facilities 4... review, for example, actions under 10 CFR 110.40(b). Application—new license, or amendment; or license... Branch review, for example, those actions under 10 CFR 110.41(a). Application—new license, or...

  14. 10 CFR 170.21 - Schedule of fees for production and utilization facilities, review of standard referenced design...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 CFR part 110. 1. Application for import or export of production or utilization facilities 4... review, for example, actions under 10 CFR 110.40(b). Application—new license, or amendment; or license... Branch review, for example, those actions under 10 CFR 110.41(a). Application—new license, or...

  15. Randomized Trial of Pentoxifylline and Vitamin E vs Standard Follow-up After Breast Irradiation to Prevent Breast Fibrosis, Evaluated by Tissue Compliance Meter

    SciTech Connect

    Jacobson, Geraldine; Bhatia, Sudershan; Smith, Brian J.; Button, Anna M.; Bodeker, Kellie; Buatti, John

    2013-03-01

    Purpose: To conduct a randomized clinical trial to determine whether the combination of pentoxifylline (PTX) and vitamin E given for 6 months after breast/chest wall irradiation effectively prevents radiation-induced fibrosis (RIF). Methods and Materials: Fifty-three breast cancer patients with localized disease were enrolled and randomized to treatment with oral PTX 400 mg 3 times daily and oral vitamin E 400 IU daily for 6 months after radiation (n=26), or standard follow up (n=27). Tissue compliance meter (TCM) measurements were obtained at 18 months to compare tissue compliance in the irradiated and untreated breast/chest wall in treated subjects and controls. Measurements were obtained at 2 mirror image sites on each breast/chest wall, and the average difference in tissue compliance was scored. Differences in TCM measurements were compared using a t test. Subjects were followed a minimum of 2 years for local recurrence, disease-free survival, and overall survival. Results: The mean difference in TCM measurements in the 2 groups was 0.88 mm, median of 1.00 mm (treated) and 2.10 mm, median of 2.4 mm (untreated). The difference between the 2 groups was significant (P=.0478). Overall survival (100% treated, 90.6% controls at 5 years) and disease-free survival (96.2% treated, 86.8% controls at 5 years) were not significantly different in the 2 groups. Conclusions: This study of postirradiation breast cancer patients treated with PTX/vitamin E or standard follow-up indicated a significant difference in radiation-induced fibrosis as measured by TCM. There was no observed impact on local control or survival within the first 2 years of follow-up. The treatment was safe and well tolerated. Pentoxifylline/vitamin E may be clinically useful in preventing fibrosis after radiation in high-risk patients.

  16. Lunar Spectral Irradiance and Radiance (LUSI): New Instrumentation to Characterize the Moon as a Space-Based Radiometric Standard

    PubMed Central

    Smith, Allan W.; Lorentz, Steven R.; Stone, Thomas C.; Datla, Raju V.

    2012-01-01

    The need to understand and monitor climate change has led to proposed radiometric accuracy requirements for space-based remote sensing instruments that are very stringent and currently outside the capabilities of many Earth orbiting instruments. A major problem is quantifying changes in sensor performance that occur from launch and during the mission. To address this problem on-orbit calibrators and monitors have been developed, but they too can suffer changes from launch and the harsh space environment. One solution is to use the Moon as a calibration reference source. Already the Moon has been used to remove post-launch drift and to cross-calibrate different instruments, but further work is needed to develop a new model with low absolute uncertainties capable of climate-quality absolute calibration of Earth observing instruments on orbit. To this end, we are proposing an Earth-based instrument suite to measure the absolute lunar spectral irradiance to an uncertainty1 of 0.5 % (k=1) over the spectral range from 320 nm to 2500 nm with a spectral resolution of approximately 0.3 %. Absolute measurements of lunar radiance will also be acquired to facilitate calibration of high spatial resolution sensors. The instruments will be deployed at high elevation astronomical observatories and flown on high-altitude balloons in order to mitigate the effects of the Earth’s atmosphere on the lunar observations. Periodic calibrations using instrumentation and techniques available from NIST will ensure traceability to the International System of Units (SI) and low absolute radiometric uncertainties. PMID:26900523

  17. Comparison of absolute spectral irradiance responsivity measurement techniques using wavelength-tunable lasers

    SciTech Connect

    Ahtee, Ville; Brown, Steven W.; Larason, Thomas C.; Lykke, Keith R.; Ikonen, Erkki; Noorma, Mart

    2007-07-10

    Independent methods for measuring the absolute spectral irradiance responsivity of detectors have been compared between the calibration facilities at two national metrology institutes, the Helsinki University of Technology (TKK), Finland, and the National Institute of Standards and Technology (NIST). The emphasis is on the comparison of two different techniques for generating a uniform irradiance at a reference plane using wavelength-tunable lasers. At TKK's Laser Scanning Facility (LSF) the irradiance is generated by raster scanning a single collimated laser beam, while at the NIST facility for Spectral Irradiance and Radiance Responsivity Calibrations with Uniform Sources (SIRCUS), lasers are introduced into integrating spheres to generate a uniform irradiance at a reference plane. The laser-based irradiance responsivity results are compared to a traditional lamp-monochromator-based irradiance responsivity calibration obtained at the NIST Spectral Comparator Facility (SCF). A narrowband filter radiometer with a24 nm bandwidth and an effective band-center wavelength of 801 nm was used as the artifact. The results of the comparison between the different facilities, reported for the first time in the near-infrared wavelength range, demonstrate agreement at the uncertainty level of less than 0.1%. This result has significant implications in radiation thermometry and in photometry as well as in radiometry.

  18. A Guide for Developing Standard Operating Job Procedures for the Primary Sedimentation Process Wastewater Treatment Facility. SOJP No. 4.

    ERIC Educational Resources Information Center

    Charles County Community Coll., La Plata, MD.

    This guide describes standard operating job procedures for the primary sedimentation process of wastewater treatment plants. The primary sedimentation process involves removing settleable and suspended solids, in part, from wastewater by gravitational forces, and scum and other floatable solids from wastewater by mechanical means. Step-by-step…

  19. A Guide for Developing Standard Operating Job Procedures for the Grit Removal Process Wastewater Treatment Facility. SOJP No. 2.

    ERIC Educational Resources Information Center

    Deal, Gerald A.; Montgomery, James A.

    This guide describes standard operating job procedures for the grit removal process of wastewater treatment plants. Step-by-step instructions are given for pre-start up inspection, start-up, continuous operation, and shut-down procedures. A description of the equipment used in the process is given. Some theoretical material is presented. (BB)

  20. A Guide for Developing Standard Operating Job Procedures for the Pump Station Process Wastewater Treatment Facility. SOJP No. 3.

    ERIC Educational Resources Information Center

    Perley, Gordon F.

    This is a guide for standard operating job procedures for the pump station process of wastewater treatment plants. Step-by-step instructions are given for pre-start up inspection, start-up procedures, continuous routine operation procedures, and shut-down procedures. A general description of the equipment used in the process is given. Two…

  1. A Guide for Developing Standard Operating Job Procedures for the Tertiary Multimedia Filtration Process Wastewater Treatment Facility. SOJP No. 7.

    ERIC Educational Resources Information Center

    Petrasek, Al, Jr.

    This guide describes the standard operating job procedures for the tertiary multimedia filtration process of wastewater treatment plants. The major objective of the filtration process is the removal of suspended solids from the reclaimed wastewater. The guide gives step-by-step instructions for pre-start up, start-up, continuous operation, and…

  2. Test reactor irradiation coordination

    SciTech Connect

    Heartherly, D.W.; Siman Tov, I.I.; Sparks, D.W.

    1995-10-01

    This task was established to supply and coordinate irradiation services needed by NRC contractors other than ORNL. These services include the design and assembly of irradiation capsules as well as arranging for their exposure, disassembly, and return of specimens. During this period, the final design of the facility and specimen baskets was determined through an iterative process involving the designers and thermal analysts. The resulting design should permit the irradiation of all test specimens to within 5{degrees}C of their desired temperature. Detailing of all parts is ongoing and should be completed during the next reporting period. Procurement of the facility will also be initiated during the next review period.

  3. Guidance for the design and management of a maintenance plan to assure safety and improve the predictability of a DOE nuclear irradiation facility. Final report

    SciTech Connect

    Booth, R.S.; Kryter, R.C.; Shepard, R.L.; Smith, O.L.; Upadhyaya, B.R.; Rowan, W.J.

    1994-10-01

    A program is recommended for planning the maintenance of DOE nuclear facilities that will help safety and enhance availability throughout a facility`s life cycle. While investigating the requirements for maintenance activities, a major difference was identified between the strategy suitable for a conventional power reactor and one for a research reactor facility: the latter should provide a high degree of predicted availability (referred to hereafter as ``predictability``) to its users, whereas the former should maximize total energy production. These differing operating goals necessitate different maintenance strategies. A strategy for scheduling research reactor facility operation and shutdown for maintenance must balance safety, reliability,and predicted availability. The approach developed here is based on three major elements: (1) a probabilistic risk analysis of the balance between assured reliability and predictability (presented in Appendix C), (2) an assessment of the safety and operational impact of maintenance activities applied to various components of the facility, and (3) a data base of historical and operational information on the performance and requirements for maintenance of various components. These factors are integrated into a set of guidelines for designing a new highly maintainable facility, for preparing flexible schedules for improved maintenance of existing facilities, and for anticipating the maintenance required to extend the life of an aging facility. Although tailored to research reactor facilities, the methodology has broader applicability and may therefore be used to improved the maintenance of power reactors, particularly in anticipation of peak load demands.

  4. Comparison of fracture behavior for low-swelling ferritic and austenitic alloys irradiated in the Fast Flux Test Facility (FFTF) to 180 DPA

    SciTech Connect

    Huang, F.H.

    1992-02-01

    Fracture toughness testing was conducted to investigate the radiation embrittlement of high-nickel superalloys, modified austenitic steels and ferritic steels. These materials have been experimentally proven to possess excellent resistance to void swelling after high neutron exposures. In addition to swelling resistance, post-irradiation fracture resistance is another important criterion for reactor material selection. By means of fracture mechanics techniques the fracture behavior of those highly irradiated alloys was characterized in terms of irradiation and test conditions. Precipitation-strengthened alloys failed by channel fracture with very low postirradiation ductility. The fracture toughness of titanium-modified austenitic stainless steel D9 deteriorates with increasing fluence to about 100 displacement per atom (dpa), the fluence level at which brittle fracture appears to occur. Ferritic steels such as HT9 are the most promising candidate materials for fast and fusion reactor applications. The upper-shelf fracture toughness of alloy HT9 remained adequate after irradiation to 180 dpa although its ductile- brittle transition temperature (DBTT) shift by low temperature irradiation rendered the material susceptible to brittle fracture at room temperature. Understanding the fracture characteristics under various irradiation and test conditions helps reduce the potential for brittle fracture by permitting appropriate measure to be taken.

  5. Standard Review Plan for the review of a license application for a low-level radioactive waste disposal facility. Revision 3

    SciTech Connect

    Not Available

    1994-04-01

    The Standard Review Plan (SRP) (NUREG-1200) provides guidance to staff reviewers in the Office of Nuclear Material Safety and Safeguards who perform safety reviews of applications to construct and operate low-level radioactive waste disposal facilities. The SRP ensures the quality and uniformity of the staff reviews and presents a well-defined base from which to evaluate proposed changes in the scope and requirements of the staff reviews. The SRP makes information about the regulatory licensing process widely available and serves to improve the understanding of the staff`s review process by interested members of the public and the industry. Each individual SRP addresses the responsibilities of persons performing the review, the matters that are reviewed, the Commission`s regulations and acceptance criteria necessary for the review, how the review is accomplished, the conclusions that are appropriate, and the implementation requirements.

  6. The spectral irradiance traceability chain at PTB

    SciTech Connect

    Sperfeld, P.; Pape, S.; Nevas, S.

    2013-05-10

    international intercomparisons among NMIs. Ultimately, the spectral irradiance can be realized with expanded measurement uncertainties of far less than 1 % over a wide spectral range. Thus, for customers with high demands on low measurement uncertainties, it is possible to calibrate their working standards directly against the blackbody-radiator, taking into account the higher necessary effort. In special cases it is possible to calibrate the customer's spectroradiometric facilities directly in front of the blackbody-radiator. In the context of the European Metrology Research Project Traceability for surface spectral solar ultraviolet radiation, the traceability chain will be improved and adapted.

  7. The spectral irradiance traceability chain at PTB

    NASA Astrophysics Data System (ADS)

    Sperfeld, P.; Pape, S.; Nevas, S.

    2013-05-01

    international intercomparisons among NMIs. Ultimately, the spectral irradiance can be realized with expanded measurement uncertainties of far less than 1 % over a wide spectral range. Thus, for customers with high demands on low measurement uncertainties, it is possible to calibrate their working standards directly against the blackbody-radiator, taking into account the higher necessary effort. In special cases it is possible to calibrate the customer's spectroradiometric facilities directly in front of the blackbody-radiator. In the context of the European Metrology Research Project Traceability for surface spectral solar ultraviolet radiation, the traceability chain will be improved and adapted.

  8. Experimental study of surface insulated-standard hybrid tungsten planar wire array Z-pinches at "QiangGuang-I" facility

    NASA Astrophysics Data System (ADS)

    Sheng, Liang; Peng, Bodong; Li, Yang; Yuan, Yuan; Li, Mo; Zhang, Mei; Zhao, Chen; Zhao, Jizhen; Wang, Liangping

    2016-01-01

    The experimental results of the insulated-standard hybrid wire array Z pinches carried out on "QiangGuang-I" facility at Northwest Institute of Nuclear Technology were presented and discussed. The surface insulating can impose a significant influence on the dynamics and radiation characteristics of the hybrid wire array Z pinches, especially on the early stage (t/timp < 0.6). The expansion of insulated wires at the ablation stage is suppressed, while the streams stripped from the insulated wires move faster than that from the standard wires. The foot radiation of X-ray is enhanced by increment of the number of insulated wires, 19.6 GW, 33.6 GW, and 68.6 GW for shots 14037S, 14028H, and 14039I, respectively. The surface insulation also introduces nonhomogeneity along the single wire—the streams move much faster near the electrodes. The colliding boundary of the hybrid wire array Z pinches is bias to the insulated side approximately 0.6 mm.

  9. Facile fabrication of high-performance InGaZnO thin film transistor using hydrogen ion irradiation at room temperature

    SciTech Connect

    Ahn, Byung Du; Park, Jin-Seong; Chung, K. B.

    2014-10-20

    Device performance of InGaZnO (IGZO) thin film transistors (TFTs) are investigated as a function of hydrogen ion irradiation dose at room temperature. Field effect mobility is enhanced, and subthreshold gate swing is improved with the increase of hydrogen ion irradiation dose, and there is no thermal annealing. The electrical device performance is correlated with the electronic structure of IGZO films, such as chemical bonding states, features of the conduction band, and band edge states below the conduction band. The decrease of oxygen deficient bonding and the changes in electronic structure of the conduction band leads to the improvement of device performance in IGZO TFT with an increase of the hydrogen ion irradiation dose.

  10. Facility safety study

    NASA Technical Reports Server (NTRS)

    1979-01-01

    The safety of NASA's in house microelectronics facility is addressed. Industrial health standards, facility emission control requirements, operation and safety checklists, and the disposal of epitaxial vent gas are considered.

  11. Economics of food irradiation.

    PubMed

    Deitch, J

    1982-01-01

    This article examines the cost competitiveness of the food irradiation process. An analysis of the principal factors--the product, physical plant, irradiation source, and financing--that impact on cost is made. Equations are developed and used to calculate the size of the source for planned product throughput, efficiency factors, power requirements, and operating costs of sources, radionuclides, and accelerators. Methods of financing and capital investment are discussed. A series of tables show cost breakdowns of sources, buildings, equipment, and essential support facilities for both a cobalt-60 and a 10-MeV electron accelerator facility. Additional tables present irradiation costs as functions of a number of parameters--power input, source size, dose, and hours of annual operation. The use of the numbers in the tables are explained by examples of calculations of the irradiation costs for disinfestation of grains and radicidation of feed. PMID:6759046

  12. EFFECT OF POLY (ETHYLENE GLYCOL) ON THE FORMATION OF NANOSTRUCTURES: A FACILE SUSTAINABLE APPROACH FOR THE SYNTHESIS OF SILVER NANORODS USING MICROWAVE IRRADIATION

    EPA Science Inventory

    Bulk synthesis of silver nanorods employing poly (ethylene glycol) (PEG) under microwave irradiation is reported. The formation of nanorods or particulate morphology is dependent on the PEG concentration. This greener method uses no surfactants or reducing agents and employs a b...

  13. Site-specific standard request for Underground Storage Tanks 1219-U, 1222-U, 2082-U, and 2068-U at the Rust Garage Facility Buildings 9754-1 and 9720-15

    SciTech Connect

    Not Available

    1994-08-01

    This document is a site-specific standard request for underground storage tanks located at the Rust Garage Facility. These standards are justified based on conclusion derived from the exposure assessment that indicates there is no current or forseeable future human health risk associated with petroleum contaminants on the site, that current and future ecological risks would be generally limited to subsurface species and plant life with roots extending into the area, and that most of the impacted area at the site is covered by asphalt or concrete. The vertical and horizontal extent of soil and ground water contamination are limited to immediate area of the Rust Garage Facility.

  14. Direct drive targets for the megajoule facility UFL-2M

    NASA Astrophysics Data System (ADS)

    Rozanov, V. B.; Gus'kov, S. Yu; Vergunova, G. A.; Demchenko, N. N.; Stepanov, R. V.; Doskoch, I. Ya; Yakhin, R. A.; Zmitrenko, N. V.

    2016-03-01

    Development of direct drive target schemes for the megajoule facility is a topical problem of up-to-date inertial fusion physics. The choice of possible schemes and solutions depends essentially on the irradiation conditions. The installations both running (NIF) and under construction (LMJ) are destined to the 3ω irradiation in PDD (polar direct drive) configuration. The UFL-2M installation that is under construction is based on 2ω irradiation and a symmetrical scheme of direct drive target irradiation. Under these conditions possible schemes for direct drive targets demonstrating the ignition and the achievement of gain G=10÷20 are considered in this report. At the same time, the possibilities are analyzed for the target compression and ignition with a reliability reserve at the conditions that can deviate from the standard ones, and if our understanding of the physics of the processes is not completely adequate to the physics of the real processes.

  15. Irradiation Creep in Graphite

    SciTech Connect

    Ubic, Rick; Butt, Darryl; Windes, William

    2014-03-13

    An understanding of the underlying mechanisms of irradiation creep in graphite material is required to correctly interpret experimental data, explain micromechanical modeling results, and predict whole-core behavior. This project will focus on experimental microscopic data to demonstrate the mechanism of irradiation creep. High-resolution transmission electron microscopy should be able to image both the dislocations in graphite and the irradiation-induced interstitial clusters that pin those dislocations. The team will first prepare and characterize nanoscale samples of virgin nuclear graphite in a transmission electron microscope. Additional samples will be irradiated to varying degrees at the Advanced Test Reactor (ATR) facility and similarly characterized. Researchers will record microstructures and crystal defects and suggest a mechanism for irradiation creep based on the results. In addition, the purchase of a tensile holder for a transmission electron microscope will allow, for the first time, in situ observation of creep behavior on the microstructure and crystallographic defects.

  16. NHEXAS PHASE I REGION 5 STUDY--STANDARD OPERATING PROCEDURES FOR PERSONNEL SAFETY IN THE ACS INORGANIC CLEAN LAB FACILITY (NHX/SOP-300-002)

    EPA Science Inventory

    This procedure provides guidelines to ensure the safety of the laboratory working staff and the clean room facility. The clean room facility was designed to provide a particle-free clean room environment for trace and ultra-trace level metal analyses. As a result, the facility wa...

  17. Status of food irradiation in the United States

    NASA Astrophysics Data System (ADS)

    Derr, Donald D.; Engel, Ronald E.

    1993-07-01

    The time immediately preceding the 8th International Meeting on Radiation Processing in September 1992 has been a landmark period for food irradiation in the United States. U.S. regulatory officials, industry and media representatives, and some consumer organizations share the opinion that radiation processing may be part of the solution to microbiological contamination of products of animal origin. Several new regulations being developed by U.S. regulatory agencies and being petitioned by industry groups are outlined. Renewed interest on the part of the U.S. Army in using irradiated foods in many of their nations is reviewed. The first commercial facility designed for food irradiation and two demonstration food irradiation facilities began operations early in 1992. The progress of these facilities is discussed. The North American Free Trade Agreement (NAFTA) and the Uruguay round of GATT negotiations may significantly lower barriers that impede international agricultural trade. International agreement on appropriate control and inspection procedures would eliminate unnecessary differences and improve mutual trust thus facilitating international trade in irradiated foods. The harmonization of radiation process practices, dosimetry standards, and other issues plays a very important role in meeting the provisions of trade agreeements. It is vitally important to address these issues early in the commercialization of food irradiation throughout the trading world. Some comments in that area are provided. Much has been done already to harmonize regulations and facilitate trade; but there is still much to be done. Regardless of how these issues are resolved, they will have a significant impact on the use of radiation processing for foods and the trade of irradiated foods all over the world.

  18. TECHNICAL BASIS FOR DOE STANDARD 3013 EQUIVALENCY SUPPORTING REDUCED TEMPERATURE STABILIZATION OF OXALATE-DERIVED PLUTONIUM OXIDE PRODUCED BY THE HB-LINE FACILITY AT SAVANNAH RIVER SITE

    SciTech Connect

    Duffey, J.; Livingston, R.; Berg, J.; Veirs, D.

    2012-07-02

    The HB-Line (HBL) facility at the Savannah River Site (SRS) is designed to produce high-purity plutonium dioxide (PuO{sub 2}) which is suitable for future use in production of Mixed Oxide (MOX) fuel. The MOX Fuel Fabrication Facility (MFFF) requires PuO{sub 2} feed to be packaged per the U.S. Department of Energy (DOE) Standard 3013 (DOE-STD-3013) to comply with the facility's safety basis. The stabilization conditions imposed by DOE-STD-3013 for PuO{sub 2} (i.e., 950 C for 2 hours) preclude use of the HBL PuO{sub 2} in direct fuel fabrication and reduce the value of the HBL product as MFFF feedstock. Consequently, HBL initiated a technical evaluation to define acceptable operating conditions for production of high-purity PuO{sub 2} that fulfills the DOE-STD-3013 criteria for safe storage. The purpose of this document is to demonstrate that within the defined operating conditions, the HBL process will be equivalent for meeting the requirements of the DOE-STD-3013 stabilization process for plutonium-bearing materials from the DOE complex. The proposed 3013 equivalency reduces the prescribed stabilization temperature for high-purity PuO{sub 2} from oxalate precipitation processes from 950 C to 640 C and places a limit of 60% on the relative humidity (RH) at the lowest material temperature. The equivalency is limited to material produced using the HBL established flow sheet, for example, nitric acid anion exchange and Pu(IV) direct strike oxalate precipitation with stabilization at a minimum temperature of 640 C for four hours (h). The product purity must meet the MFFF acceptance criteria of 23,600 {micro}g/g Pu (i.e., 2.1 wt %) total impurities and chloride content less than 250 {micro}g/g of Pu. All other stabilization and packaging criteria identified by DOE-STD-3013-2012 or earlier revisions of the standard apply. Based on the evaluation of test data discussed in this document, the expert judgment of the authors supports packaging the HBL product under a 3013

  19. Evaluation of standard and alternative methods for the decontamination of VX and HD in chemical agent disposal facilities. Final report, February 1992-February 1993

    SciTech Connect

    Hovanec, J.W.; Szafraniec, L.L.; Albizo, J.M.; Beaudry, W.T.; Henderson, V.D.

    1993-04-01

    Standard decontaminant formulations, aqueous sodium hydroxide and aqueous sodium hypochlorite, were providing slow and incomplete results when used to decontaminate certain operating facilities at the Johnston Atoll Chemical Agent Disposal System and the Chemical Agent Disposal System (Utah). A study was undertaken to define the capabilities and limitations of using concentrated sodium hydroxide to decontaminate VX, the effect of adding hydrogen peroxide to the sodium hydroxide for the decontamination of VX, the efficacy of aqueous oxone for the decontamination of VX, and the efficacy of oxone in a water/1-methyl-2-pyrrolidinone (MP) mixture for the decontamination of HD. Using aqueous sodium hydroxide alone was not desirable since the formation of toxic EA2192 could not be averted. However, the addition of hydrogen peroxide resulted in effective VX decontamination without EA2192 formation. Aqueous oxone was also found to be effective for both VX and HD. The incorporation of MP did little to improve HD dissolution and reacted with the oxone to reduce the effective usable life of the decontamination solution. Thus, the use of MP in HD decontamination was not recommended.

  20. Positron Annihilation Lifetime Spectroscopy Study of Neutron Irradiated High Temperature Superconductors YBa2Cu3O7-δ for Application in Fusion Facilities

    NASA Astrophysics Data System (ADS)

    Veterníková, J.; Chudý, M.; Slugeň, V.; Eisterer, M.; Weber, H. W.; Sojak, S.; Petriska, M.; Hinca, R.; Degmová, J.; Sabelová, V.

    2012-02-01

    This study focuses on the crystallographic defects introduced by neutron irradiation and the resulting changes of the superconducting properties in the high temperature superconductor YBa2Cu3O7-δ. This material is considered to be most promising for magnet systems in future fusion reactors. Two different bulk samples, pure non-doped YBa2Cu3O7-δ (YBCO) and multi-seed YBa2Cu3O7-δ doped by platinum (MS2F) were studied prior to and after irradiation in the TRIGA MARK II reactor in Vienna. Neutron irradiation is responsible for a significant enhancement of the critical current densities as well as for a reduction in critical temperature. The accumulation of small open volume defects (<0.5 nm) partially causes those changes. These defects were studied by positron annihilation lifetime spectroscopy at room temperature. A high concentration of Cu-O di-vacancies was found in both samples, which increased with neutron fluence. The defect concentration was significantly reduced after a heat treatment.

  1. Uniform Federal Accessibility Standards.

    ERIC Educational Resources Information Center

    Department of Housing and Urban Development, Washington, DC.

    The document presents uniform standards for facility accessibility by physically handicapped persons for Federal and federally funded facilities. The standards are to be applied during the design, construction, and alteration of buildings and facilities to the extent required by the Architectural Barriers Act of 1968, as amended. Technical…

  2. Bandwidth and spectral stray light effects in the NASA GSFC Radiometric Calibration Facility primary transfer radiometer

    NASA Astrophysics Data System (ADS)

    Barnes, Robert A.; Cooper, John W.; Marketon, John E.; Brown, Steven W.; Johnson, B. Carol; Butler, James J.

    2006-08-01

    As part of an effort to reduce uncertainties in the radiometric calibrations of integrating sphere sources and standard lamp irradiance sources, the Goddard Space Flight Center (GSFC) Radiometric Calibration Facility's (RCF) primary radiometer was characterized at the NIST facility for Spectral Irradiance and Radiance Calibrations with Uniform Sources (SIRCUS). Based on those measurements, a nominal slit scattering function was developed for the radiometer. This allowed calculations of band averaged spectral radiances and irradiances for the radiometer's measurements of sphere and standard lamp sources, respectively. From these calculations the effects of bandwidth and spectral stray light were isolated for measurements in the blue spectral region. These effects, which depend on the spectral distribution of the source being measured, can be as large as 8% for measurements at 400 nm. The characterization results and a correction algorithm for these effects are presented here.

  3. 9 CFR 3.27 - Facilities, outdoor.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Pigs and Hamsters Facilities and Operating Standards § 3.27 Facilities, outdoor. (a) Hamsters shall not be housed in outdoor facilities. (b) Guinea pigs shall not be housed in outdoor facilities...

  4. 9 CFR 3.27 - Facilities, outdoor.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Pigs and Hamsters Facilities and Operating Standards § 3.27 Facilities, outdoor. (a) Hamsters shall not be housed in outdoor facilities. (b) Guinea pigs shall not be housed in outdoor facilities...

  5. Radiation Safety Training for Industrial Irradiators: What Are We Trying To Accomplish?

    NASA Astrophysics Data System (ADS)

    Smith, M. A.

    1998-06-01

    Radiation safety training at an industrial irradiator facility takes a different approach than the traditional methods and topics used at other facilities. Where the more routine industrial radiation users focus on standard training topics of contamination control, area surveys, and the traditional dogma of time, distance, and shielding, radiation safety in an industrial irradiation facility must be centered on preventing accidents. Because the primary methods for accomplishing that goal are engineering approaches such as safety system interlocks, training provided to facility personnel should address system operation and emergency actions. This presents challenges in delivering radiation safety to an audience of varied educational and technical background where little to no commercially available training material specific to this type of operation exists.

  6. NSUF Irradiated Materials Library

    SciTech Connect

    Cole, James Irvin

    2015-09-01

    The Nuclear Science User Facilities has been in the process of establishing an innovative Irradiated Materials Library concept for maximizing the value of previous and on-going materials and nuclear fuels irradiation test campaigns, including utilization of real-world components retrieved from current and decommissioned reactors. When the ATR national scientific user facility was established in 2007 one of the goals of the program was to establish a library of irradiated samples for users to access and conduct research through competitively reviewed proposal process. As part of the initial effort, staff at the user facility identified legacy materials from previous programs that are still being stored in laboratories and hot-cell facilities at the INL. In addition other materials of interest were identified that are being stored outside the INL that the current owners have volunteered to enter into the library. Finally, over the course of the last several years, the ATR NSUF has irradiated more than 3500 specimens as part of NSUF competitively awarded research projects. The Logistics of managing this large inventory of highly radioactive poses unique challenges. This document will describe materials in the library, outline the policy for accessing these materials and put forth a strategy for making new additions to the library as well as establishing guidelines for minimum pedigree needed to be included in the library to limit the amount of material stored indefinitely without identified value.

  7. Temperature dependence of fracture toughness in HT9 steel neutron-irradiated up to 145 dpa

    SciTech Connect

    Baek, Jong-Hyuk; Byun, Thak Sang; Maloy, S; Toloczko, M

    2014-01-01

    The temperature dependence of fracture toughness in HT9 steel irradiated to high doses was investigated using miniature three-point bend (TPB) fracture specimens. These specimens were from the ACO-3 fuel duct wall of the Fast Flux Test Facility (FFTF), in which irradiation doses were in the range of 3.2 144.8 dpa and irradiation temperatures in the range of 380.4 502.6 oC. A miniature specimen reuse technique has been established for this investigation: the specimens used were the tested halves of miniature Charpy impact specimens (~13 3 4 mm) with diamond-saw cut in the middle. The fatigue precracking for specimens and fracture resistance (J-R) tests were carried out in a MTS servo-hydraulic testing machine with a vacuum furnace following the standard procedure described in the ASTM Standard E 1820-09. For each of five irradiated and one archive conditions, 7 to 9 J-R tests were performed at selected temperatures ranging from 22 C to 600 C. The fracture toughness of the irradiated HT9 steel was strongly dependent on irradiation temperatures rather than irradiation dose. When the irradiation temperature was below about 430 C, the fracture toughness of irradiated HT9 increased with test temperature, reached an upper shelf of 180 200 MPa m at 350 450 C and then decreased with test temperature. When the irradiation temperature 430 C, the fracture toughness was nearly unchanged until about 450 C and decreased with test temperature in higher temperature range. Similar test temperature dependence was observed for the archive material although the highest toughness values are lower after irradiation. Ductile stable crack growth occurred except for a few cases where both the irradiation temperature and test temperature are relatively low.

  8. Using the LANSCE irradiation facility to predict the number of fatal soft errors in one of the world’s fastest supercomputers

    NASA Astrophysics Data System (ADS)

    Michalak, S. E.; Harris, K. W.; Hengartner, N. W.; Takala, B. E.; Wender, S. A.

    2005-12-01

    Los Alamos National Laboratory (LANL) is home to the Los Alamos Neutron Science Center (LANSCE). LANSCE is a unique facility because its neutron spectrum closely mimics the neutron spectrum at terrestrial and aircraft altitudes, but is many times more intense. Thus, LANSCE provides an ideal setting for accelerated testing of semiconductor and other devices that are susceptible to cosmic ray induced neutrons. Many industrial companies use LANSCE to estimate device susceptibility to cosmic ray induced neutrons, and it has also been used to test parts from one of LANL's supercomputers, the ASC (Advanced Simulation and Computing Program) Q. This paper discusses our use of the LANSCE facility to study components in Q including a comparison with failure data from Q.

  9. Facility effluent monitoring plan for the 327 Facility

    SciTech Connect

    1994-11-01

    The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements.

  10. 40 CFR 60.5410 - How do I demonstrate initial compliance with the standards for my gas well affected facility, my...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... affected facility, and my equipment leaks and sweetening unit affected facilities at onshore natural gas... Performance for Crude Oil and Natural Gas Production, Transmission and Distribution § 60.5410 How do I... at onshore natural gas processing plants? You must determine initial compliance with the...

  11. 40 CFR 60.5410 - How do I demonstrate initial compliance with the standards for my gas well affected facility, my...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... affected facility, and my equipment leaks and sweetening unit affected facilities at onshore natural gas... Performance for Crude Oil and Natural Gas Production, Transmission and Distribution § 60.5410 How do I... at onshore natural gas processing plants? You must determine initial compliance with the...

  12. Elimination of coliforms and Salmonella spp. in sheep meat by gamma irradiation treatment

    PubMed Central

    Henriques, Luciana Salles Vasconcelos; da Costa Henry, Fábio; Barbosa, João Batista; Ladeira, Silvania Alves; de Faria Pereira, Silvia Menezes; da Silva Antonio, Isabela Maria; Teixeira, Gina Nunes; Martins, Meire Lelis Leal; de Carvalho Vital, Helio; dos Prazeres Rodrigues, Dália; dos Reis, Eliane Moura Falavina

    2013-01-01

    This study aimed at evaluating the bacteriological effects of the treatment of sheep meat contaminated with total coliforms, coliforms at 45 °C and Salmonella spp. by using irradiation at doses of 3 kGy and 5 kGy. Thirty sheep meat samples were collected from animals located in Rio de Janeiro State, Brazil, and then grouped in three lots including 10 samples: non-irradiated (control); irradiated with 3 kGy; and irradiated with 5 kGy. Exposure to gamma radiation in a 137Cs source-driven irradiating facility was perfomed at the Nuclear Defense Section of the Brazilian Army Technological Center (CTEx) in Rio de Janeiro. The samples were kept under freezing temperature (−18 °C) until the analyses, which occurred in two and four months after irradiation. The results were interpreted by comparison with the standards of the current legislation and demonstrated that non-irradiated samples were outside the parameters established by law for all groups of bacteria studied. Gamma irradiation was effective in inactivating those microorganisms at both doses tested and the optimal dose was achieved at 3 kGy. The results have shown not only the need for sanitary conditions improvements in slaughter and processing of sheep meat but also the irradiation effectiveness to eliminate coliform bacteria and Salmonella spp. PMID:24688504

  13. Microstructural characterization of Eurofer-97 and Eurofer-ODS steels before and after multi-beam ion irradiations at JANNUS Saclay facility

    NASA Astrophysics Data System (ADS)

    Brimbal, Daniel; Beck, Lucile; Troeber, Oliver; Gaganidze, Ermile; Trocellier, Patrick; Aktaa, Jarir; Lindau, Rainer

    2015-10-01

    RAFM steels such as Eurofer-97 and Eurofer-ODS are potential structural materials for future fusion reactors. In order to study their resistance to the high energy neutrons they will be subjected to in this context, we have irradiated these materials in single-, dual- and triple-beam mode to 26 dpa at 400 °C. In single-beam mode (Fe ions only), both materials resist swelling but dislocation loops form. For dual- (Fe and He ions) and triple-beam (Fe, He and H) modes, the same dislocation loop microstructure is observed as for the single-beam mode, but small cavities form, aided by the presence of gases. Despite the formation of cavities, swelling is very low for the present conditions. The influence of ODS particles on swelling is briefly discussed.

  14. Facile room-temperature synthesis of carboxylated graphene oxide-copper sulfide nanocomposite with high photodegradation and disinfection activities under solar light irradiation

    PubMed Central

    Yu, Shuyan; Liu, Jincheng; Zhu, Wenyu; Hu, Zhong-Ting; Lim, Teik-Thye; Yan, Xiaoli

    2015-01-01

    Carboxylic acid functionalized graphene oxide-copper (II) sulfide nanoparticle composite (GO-COOH-CuS) was prepared from carboxylated graphene oxide and copper precursor in dimethyl sulfoxide (DMSO) by a facile synthesis process at room temperature. The high-effective combination, the interaction between GO-COOH sheets and CuS nanoparticles, and the enhanced visible light absorption were confirmed by transmission electron microscopy (TEM), field emission scanning electron microscopy (FESEM), X-ray powder diffraction (XRD), Fourier transform infrared spectroscopy (FTIR), thermo gravimetric analysis (TGA), X-ray photoelectron spectroscopy (XPS), UV-vis diffuse reflectance spectra (DRS) and Photoluminescence (PL) spectra. The as-synthesized GO-COOH-CuS nanocomposite exhibited excellent photocatalytic degradation performance of phenol and rhodamine B, high antibacterial activity toward E. coli and B. subtilis, and good recovery and reusability. The influence of CuS content, the synergistic reaction between CuS and GO-COOH, and the charge-transfer mechanism were systematically investigated. The facile and low-energy synthesis process combined with the excellent degradation and antibacterial performance signify that the GO-COOH-CuS has a great potential for water treatment application. PMID:26553709

  15. Facile room-temperature synthesis of carboxylated graphene oxide-copper sulfide nanocomposite with high photodegradation and disinfection activities under solar light irradiation.

    PubMed

    Yu, Shuyan; Liu, Jincheng; Zhu, Wenyu; Hu, Zhong-Ting; Lim, Teik-Thye; Yan, Xiaoli

    2015-01-01

    Carboxylic acid functionalized graphene oxide-copper (II) sulfide nanoparticle composite (GO-COOH-CuS) was prepared from carboxylated graphene oxide and copper precursor in dimethyl sulfoxide (DMSO) by a facile synthesis process at room temperature. The high-effective combination, the interaction between GO-COOH sheets and CuS nanoparticles, and the enhanced visible light absorption were confirmed by transmission electron microscopy (TEM), field emission scanning electron microscopy (FESEM), X-ray powder diffraction (XRD), Fourier transform infrared spectroscopy (FTIR), thermo gravimetric analysis (TGA), X-ray photoelectron spectroscopy (XPS), UV-vis diffuse reflectance spectra (DRS) and Photoluminescence (PL) spectra. The as-synthesized GO-COOH-CuS nanocomposite exhibited excellent photocatalytic degradation performance of phenol and rhodamine B, high antibacterial activity toward E. coli and B. subtilis, and good recovery and reusability. The influence of CuS content, the synergistic reaction between CuS and GO-COOH, and the charge-transfer mechanism were systematically investigated. The facile and low-energy synthesis process combined with the excellent degradation and antibacterial performance signify that the GO-COOH-CuS has a great potential for water treatment application. PMID:26553709

  16. Facile room-temperature synthesis of carboxylated graphene oxide-copper sulfide nanocomposite with high photodegradation and disinfection activities under solar light irradiation

    NASA Astrophysics Data System (ADS)

    Yu, Shuyan; Liu, Jincheng; Zhu, Wenyu; Hu, Zhong-Ting; Lim, Teik-Thye; Yan, Xiaoli

    2015-11-01

    Carboxylic acid functionalized graphene oxide-copper (II) sulfide nanoparticle composite (GO-COOH-CuS) was prepared from carboxylated graphene oxide and copper precursor in dimethyl sulfoxide (DMSO) by a facile synthesis process at room temperature. The high-effective combination, the interaction between GO-COOH sheets and CuS nanoparticles, and the enhanced visible light absorption were confirmed by transmission electron microscopy (TEM), field emission scanning electron microscopy (FESEM), X-ray powder diffraction (XRD), Fourier transform infrared spectroscopy (FTIR), thermo gravimetric analysis (TGA), X-ray photoelectron spectroscopy (XPS), UV-vis diffuse reflectance spectra (DRS) and Photoluminescence (PL) spectra. The as-synthesized GO-COOH-CuS nanocomposite exhibited excellent photocatalytic degradation performance of phenol and rhodamine B, high antibacterial activity toward E. coli and B. subtilis, and good recovery and reusability. The influence of CuS content, the synergistic reaction between CuS and GO-COOH, and the charge-transfer mechanism were systematically investigated. The facile and low-energy synthesis process combined with the excellent degradation and antibacterial performance signify that the GO-COOH-CuS has a great potential for water treatment application.

  17. Facile one-step synthesis of N-doped ZnO micropolyhedrons for efficient photocatalytic degradation of formaldehyde under visible-light irradiation

    NASA Astrophysics Data System (ADS)

    Wu, Changle

    2014-11-01

    N-doped ZnO micropolyhedrons were fabricated by calcining the mixture of commercial ZnO (analytical grade) and NH4NO3 at 600 °C for 1.5 h, in which NH4NO3 was utilized as the nitrogen source. The structure, composition, BET specific surface area and optical properties of N-doped ZnO sample were characterized by X-ray diffraction, X-ray photoelectron spectroscopy, wavelength dispersive X-ray fluorescence spectroscopy, field emission scanning electron microscopy, high resolution transmission electron microscopy, N2 adsorption-desorption isotherms, and UV-vis diffuse reflectance spectroscopy. The photocatalytic results demonstrated that the as-synthesized N-doped ZnO microcrystals possessed much higher photocatalytic activity than N-doped TiO2 (which was synthesized by calcining the mixture of P25 TiO2 and NH4NO3 at 600 °C for 1.5 h) and commercial pure ZnO in the decomposition of formaldehyde under visible-light (λ > 420 nm) irradiation. The present work suggests that NH4NO3 is a promising nitrogen source for one-step calcination synthesis of microcrystalline N-doped ZnO, which can be applied as a visible-light-activated photocatalyst in efficient utilization of solar energy for treating formaldehyde wastewater.

  18. Facile synthesis of novel CaFe2O4/g-C3N4 nanocomposites for degradation of methylene blue under visible-light irradiation.

    PubMed

    Vadivel, S; Maruthamani, D; Habibi-Yangjeh, A; Paul, Bappi; Dhar, Siddhartha Sankar; Selvam, Kaliyamoorthy

    2016-10-15

    Hybrid organic/inorganic nanocomposites comprised of calcium ferrite (CaFe2O4) and graphitic carbon nitride (g-C3N4) were prepared via a simple two-step process. The hybridized CaFe2O4/g-C3N4 heterostructure was characterized by a variety of techniques, including X-ray diffraction (XRD), Fourier transform-infrared spectroscopy (FT-IR), UV-vis diffuse reflectance spectroscopy (UV-vis DRS), scanning electron microscopy (SEM), transmission electron microscopy (TEM), energy dispersive analysis of X-rays (EDS), X-ray photoelectron spectroscopy (XPS), photoluminescence spectroscopy, electrochemical impedance spectroscopy (EIS), and photoelectrochemical studies. Photocatalytic activity of the prepared samples was evaluated against degradation of methylene blue (MB) under visible-light irradiation. The photocatalytic activity of CaFe2O4 30%/g-C3N4 nanocomposite, as optimum photocatalyst, for degradation of MB was superior to the pure CaFe2O4 and g-C3N4 samples. It was demonstrated that the photogenerated holes and superoxide ion radicals were the two main reactive species towards the photocatalytic degradation of MB over the nanocomposite. Based on the experimental results, a possible photocatalytic mechanism for the MB degradation over the nanocomposite was proposed. This work may provide some inspiration for the fabrication of spinel ferrites with efficient photocatalytic performance. PMID:27421115

  19. 48 CFR 9904.414 - Cost accounting standard-cost of money as an element of the cost of facilities capital.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 48 Federal Acquisition Regulations System 7 2012-10-01 2012-10-01 false Cost accounting standard... Acquisition Regulations System COST ACCOUNTING STANDARDS BOARD, OFFICE OF FEDERAL PROCUREMENT POLICY, OFFICE OF MANAGEMENT AND BUDGET PROCUREMENT PRACTICES AND COST ACCOUNTING STANDARDS COST...

  20. 48 CFR 9904.414 - Cost accounting standard-cost of money as an element of the cost of facilities capital.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 48 Federal Acquisition Regulations System 7 2014-10-01 2014-10-01 false Cost accounting standard... Acquisition Regulations System COST ACCOUNTING STANDARDS BOARD, OFFICE OF FEDERAL PROCUREMENT POLICY, OFFICE OF MANAGEMENT AND BUDGET PROCUREMENT PRACTICES AND COST ACCOUNTING STANDARDS COST...

  1. Facile one-pot synthesis of nickel-incorporated titanium dioxide/graphene oxide composites: Enhancement of photodegradation under visible-irradiation

    NASA Astrophysics Data System (ADS)

    Pham, Thanh-Truc; Nguyen-Huy, Chinh; Shin, Eun Woo

    2016-07-01

    Nickel (Ni)-incorporated titanium dioxide (TiO2)/graphene oxide composite photocatalysts were prepared by anchoring the TiO2 and Ni onto the surface of graphene oxide (GO) sheets by a straightforward microwave-assisted, one-pot method for the first time. The as-prepared composite photocatalysts with high Ni content (40-50 wt%) showed good adsorption capacity in the dark and high reaction rate constants under visible illumination while the composite photocatalysts with low Ni content (5-10 wt%) exhibited weak activity. An anatase phase, a small amount of rutile phase and Ni metal were detected using X-ray diffraction (XRD) and transmission electron microscopy (TEM). Raman measurements identified a small fraction of NiTiO3 only at high Ni content. The formation of NiTiO3 and the increase in the specific surface area (SSA) for 40 and 50 wt% Ni-loaded catalysts improved the adsorption capacity and photocatalytic activity upon exposure to visible light, resulting in very effective removal of dye contaminants under visible light irradiation. Increasing the Ni content up to 40 and 50 wt% induced not only a structural change affording high porosity but also a narrowing of the band gap to 2.51 eV. Meanwhile, the presence of GO in the composite photocatalysts inhibited the agglomeration of Ni particles even at high Ni content, resulting in similar Ni particle sizes regardless of the Ni content. At the same time, Ni metal accelerated the reduction of the GO sheets, as evidenced by the Raman data.

  2. Review of Research on Post Irradiation Fruit Quality of Blueberries and Peaches

    Technology Transfer Automated Retrieval System (TEKTRAN)

    The commercial use of irradiation is accelerating with the approval of low dose generic treatments for insect disinfestations and the availability of irradiation facilities. Commercial adoption of irradiation treatment requires an understanding of the radiotolerance limits for individual commodities...

  3. Facile preparation of magnetic C/TiO2/Ni composites and their photocatalytic performance for removal of a dye from water under UV light irradiation.

    PubMed

    Gondal, Mohammed A; Li, Chunli; Chang, Xiaofeng; Sikong, Lek; Yamani, Zain H; Zhou, Qin; Yang, Fan; Lin, Qin

    2012-01-01

    Development of a photocatalyst with high efficiency and separability is still a challenging task in the field of wastewater treatment. In this study, new magnetic separable C/TiO(2)/Ni composite as a photocatalyst was prepared by a facile pyrolysis reaction, using powdered activated carbon (PAC), TiO(2) and Ni(Ac)(2) as precursors. The results proved that the photocatalyst (C/TiO(2)/Ni) synthesized in this work exhibited greater removal activity for Methyl Orange (MO) dye from water as compared with the commercially available well reported TiO(2) nanoparticles (P25). This significant enhancement in the photocatalytic activity for wastewater treatment due to the combination of PAC and TiO(2) could be presumed as the synergetic effect on the contacting interface of TiO(2) and PAC, and such effect was initially demonstrated by electrochemical impedance measurements. Furthermore, the trait that it consists of magnetic properties and therefore is easy to be recycled, which could be harnessed by an external magnet and may have many advantages over pure metal oxides (like TiO(2)) especially in the industrial procedures. PMID:22375540

  4. Commercial implementation of food irradiation

    NASA Astrophysics Data System (ADS)

    Welt, M. A.

    In July 1981, the first specifically designed multi-purpose irradiation facility for food irradiation was put into service by the Radiation Technology, Inc. subsidiary Process Technology, Inc. in West Memphis, Arkansas. The operational experience gained, resulted in an enhanced design which was put into commercial service in Haw River, North Carolina, by another subsidiary, Process Technology (N.C.), Inc. in October 1983. These facilities have enabled the food industry to assess the commercial viability of food irradiation. Further impetus towards commercialization of food irradiation was gained in March 1981 with the filing in the Federal Register, by the FDA, of an Advanced Proposed Notice of Rulemaking for Food Irradiation. Two years later in July 1983, the FDA approved the first food additive regulation involving food irradiation in nineteen years, when they approved the Radiation Technology, Inc. petition calling for the sanitization of spices, onion powder and garlic powder at a maximum dosage of 10 kGy. Since obtaining the spice irradiation approval, the FDA has accepted four additional petitions for filing in the Federal Register. One of the petitions which extended spice irradiation to include insect disinfestation has issued into a regulation while the remaining petitions covering the sanitization of herbs, spice blends, vegetable seasonings and dry powdery enzymes as well as the petition to irradiate hog carcasses and pork products for trichinae control at 1 kGy, are expected to issue either before the end of 1984 or early in 1985. More recently, food irradiation advocates in the United States received another vote of confidence by the announcement that a joint venture food irradiation facility to be constructed in Hawaii by Radiation Technology, is backed by a contractual committment for the processing of 40 million pounds of produce per year. Another step was taken when the Port of Salem, New Jersey announced that the Radiation Technology Model RT-4104

  5. Impact Properties of Irradiated HT9 from the Fuel Duct of FFTF

    SciTech Connect

    Byun, Thak Sang; Maloy, S; Toloczko, M; Lewis, William Daniel

    2012-01-01

    This paper reports Charpy impact test data for the ACO-3 duct material (HT9) from the Fast Flux Test Facility (FFTF) and its archive material. Irradiation doses for the specimens were in the range of 3 148 dpa and irradiation temperatures in the range of 378 504 oC. The impact tests were performed for the small V-notched Charpy specimens with dimensions of 3 4 27 mm at an impact speed of 3.2 m/s in a 25J capacity machine. Irradiation lowered the upper-shelf energy (USE) and increased the transition temperatures significantly. The shift of transition temperatures was greater after relatively low temperature irradiation. The USE values were in the range of 5.5 6.7 J before irradiation and decreased to the range of 2 5 J after irradiation. Lower USEs were measured for lower irradiation temperatures and specimens with T-L orientation. For the irradiated specimens, the dose dependences of transition temperature and USE were not significant because of the radiation effect on impact behavior nearly saturated at the lowest dose of about 3 dpa. A comparison showed that the lateral expansion of specimens showed a linear correlation with absorbed impact energy, but with large scatter in the results. The size effect was also discussed to clarify the differences in the impact data of subsize and standard specimens.

  6. Distilling Complex Model Results into Simple Models for use in Assessing Compliance with Performance Standards for Low Level Waste Disposal Facilities

    SciTech Connect

    Arthur S. Rood

    2007-02-01

    Assessing the long term performance of waste disposal facility requires numerical simulation of saturated and unsaturated groundwater flow and contaminant transport. Complex numerical models have been developed to try to realistically simulate subsurface flow and transport processes. These models provide important information about system behavior and identify important processes, but may not be practical for demonstrating compliance with performance standards because of excessively long computer simulation times and input requirements. Two approaches to distilling the behavior of a complex model into simpler formulations that are practical for demonstrating compliance with performance objectives are examined in this paper. The first approach uses the information obtained from the complex model to develop a simple model that mimics the complex model behavior for stated performance objectives. The simple model may need to include essential processes that are important to assessing performance, such as time-variable infiltration and waste emplacement rates, subsurface heterogeneity, sorption, decay, and radioactive ingrowth. The approach was applied to a Low-Level Waste disposal site at the Idaho National Laboratory where a complex three dimensional vadose zone model was developed first to understand system behavior and important processes. The complex model was distilled down to a relatively simple one-dimensional vadose zone model and three-dimensional aquifer transport model. Comparisons between the simple model and complex model of vadose zone fluxes and groundwater concentrations showed relatively good agreement between the models for both fission and activation products (129I, 36Cl, 99Tc) and actinides (238U, 239Pu, 237Np). Application of the simple model allowed for Monte Carlo uncertainty analysis and simulations of numerous disposal and release scenarios. The second approach investigated was the response surface model. In the response surface model approach

  7. Facilities maintenance handbook

    NASA Technical Reports Server (NTRS)

    1991-01-01

    This handbook is a guide for facilities maintenance managers. Its objective is to set minimum facilities maintenance standards. It also provides recommendations on how to meet the standards to ensure that NASA maintains its facilities in a manner that protects and preserves its investment in the facilities in a cost-effective manner while safely and efficiently performing its mission. This handbook implements NMI 8831.1, which states NASA facilities maintenance policy and assigns organizational responsibilities for the management of facilities maintenance activities on all properties under NASA jurisdiction. It is a reference for facilities maintenance managers, not a step-by-step procedural manual. Because of the differences in NASA Field Installation organizations, this handbook does not assume or recommend a typical facilities maintenance organization. Instead, it uses a systems approach to describe the functions that should be included in any facilities maintenance management system, regardless of its organizational structure. For documents referenced in the handbook, the most recent version of the documents is applicable. This handbook is divided into three parts: Part 1 specifies common definitions and facilities maintenance requirements and amplifies the policy requirements contained in NMI 8831. 1; Part 2 provides guidance on how to meet the requirements of Part 1, containing recommendations only; Part 3 contains general facilities maintenance information. One objective of this handbook is to fix commonality of facilities maintenance definitions among the Centers. This will permit the application of uniform measures of facilities conditions, of the relationship between current replacement value and maintenance resources required, and of the backlog of deferred facilities maintenance. The utilization of facilities maintenance system functions will allow the Centers to quantitatively define maintenance objectives in common terms, prepare work plans, and

  8. A methodology for existing system upgrade to current ASME standards and system lifetime extension

    SciTech Connect

    Burr, T.K.; Dwight, J.E. Jr.; Hawkes, G.L.; Pace, N.E.

    1990-01-01

    In the wake of the Chernobyl events, there has been an increase in the awareness and review of government operated reactors both internationally, and within the United States. Government reactors have recently come under increased and indepth scrutiny. Department of Energy Secretary Hodel committed to a review of the safety of non-commercial reactors and irradiation facilities within the department. The increased attention has been in the areas of accident response, PRA of the facilities, environmental impacts, and the construction and associated standards for the facilities. This paper focuses on the system qualifications to current standards. Specifically, this paper discusses a method used for upgrading an existing high pressure nuclear system to current ASME Code standards and to extend the system's lifetime. This paper reports the methods used in an attempt to qualify components of the Advanced Test Reactor (ATR) located at the Idaho National Engineering Laboratory (INEL) to current ASME Code Section III standards.

  9. 48 CFR 9904.414 - Cost accounting standard-cost of money as an element of the cost of facilities capital.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... Acquisition Regulations System COST ACCOUNTING STANDARDS BOARD, OFFICE OF FEDERAL PROCUREMENT POLICY, OFFICE OF MANAGEMENT AND BUDGET PROCUREMENT PRACTICES AND COST ACCOUNTING STANDARDS COST ACCOUNTING... 48 Federal Acquisition Regulations System 7 2013-10-01 2012-10-01 true Cost accounting...

  10. Twenty new ISO standards on dosimetry for radiation processing

    NASA Astrophysics Data System (ADS)

    Farrar, H., IV

    2000-03-01

    Twenty standards on essentially all aspects of dosimetry for radiation processing were published as new ISO standards in December 1998. The standards are based on 20 standard practices and guides developed over the past 14 years by Subcommittee E10.01 of the American Society for Testing and Materials (ASTM). The transformation to ISO standards using the 'fast track' process under ISO Technical Committee 85 (ISO/TC85) commenced in 1995 and resulted in some overlap of technical information between three of the new standards and the existing ISO Standard 11137 Sterilization of health care products — Requirements for validation and routine control — Radiation sterilization. Although the technical information in these four standards was consistent, compromise wording in the scopes of the three new ISO standards to establish precedence for use were adopted. Two of the new ISO standards are specifically for food irradiation applications, but the majority apply to all forms of gamma, X-ray, and electron beam radiation processing, including dosimetry for sterilization of health care products and the radiation processing of fruit, vegetables, meats, spices, processed foods, plastics, inks, medical wastes, and paper. Most of the standards provide exact procedures for using individual dosimetry systems or for characterizing various types of irradiation facilities, but one covers the selection and calibration of dosimetry systems, and another covers the treatment of uncertainties using the new ISO Type A and Type B evaluations. Unfortunately, nine of the 20 standards just adopted by the ISO are not the most recent versions of these standards and are therefore already out of date. To help solve this problem, efforts are being made to develop procedures to coordinate the ASTM and ISO development and revision processes for these and future ASTM-originating dosimetry standards. In the meantime, an additional four dosimetry standards have recently been published by the ASTM but

  11. APPLICATION OF STANDARDIZED QUALITY CONTROL PROCEDURES TO OPEN-PATH FOURIER TRANSFORM INFRARED DATA COLLECTED AT A CONCENTRATED SWINE PRODUCTION FACILITY

    EPA Science Inventory

    Open-path Fourier transform infrared (OP/FT-IR) spectrometry was used to measure the concentrations of ammonia, methane, and other atmospheric eases at a concentrated swine production facility. A total of 2200 OP/FT-IR spectra were acquired along nine different monitoring paths d...

  12. FDA Certified Mammography Facilities

    MedlinePlus

    ... Products Radiation-Emitting Products Home Radiation-Emitting Products Mammography Quality Standards Act and Program Consumer Information (MQSA) ... it Email Print This list of FDA Certified Mammography Facilities is updated weekly. If you click on ...

  13. 9 CFR 3.25 - Facilities, general.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... Pigs and Hamsters Facilities and Operating Standards § 3.25 Facilities, general. (a) Structural strength. Indoor and outdoor housing facilities for guinea pigs or hamsters shall be structurally sound...

  14. Comparison of irradiation creep and swelling of an austenitic alloy irradiated in FFTF and PFR

    SciTech Connect

    Garner, F.A.; Toloczko, M.B.; Munro, B.; Adaway, S.; Standring, J.

    1999-10-01

    comparative irradiation of identically constructed creep tubes in the Fast Flux Test Facility (FFTF) and the Prototypic Fast Reactor (PFR) shows that differences in irradiation conditions arising from both reactor operation and the design of the irradiation vehicle can have a significant impact on the void swelling and irradiation creep of austenitic stainless steels. In spite of these differences, the derived creep coefficients fall within the range of previously observed values for 316 SS.

  15. Establishing and maintaining a facility representative program at DOE facilities

    SciTech Connect

    1997-10-01

    The purpose of this standard is to help ensure that DOE Facility Representatives are selected based on consistently high standards and from the best qualified candidates, that they receive the necessary training, and that their duties are well understood and documented. The standard defines the duties, responsibilities, and qualifications for Facility Representatives, based on facility hazard classification; risks to workers, the public, and the environment; and the operational activity level. Guidance provided includes: (1) an approach for determining the required facility coverage; (2) the duties, responsibilities, and authorities of a Facility Representative; (3) training and qualifications expected of a Facility Representative; and (4) elements necessary for successful Facility Representative Programs at DOE Field Offices. This guidance was written primarily to address nuclear facilities. 12 refs., 2 tabs.

  16. 9 CFR 3.27 - Facilities, outdoor.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... WELFARE STANDARDS Specifications for the Humane Handling, Care, Treatment, and Transportation of Guinea Pigs and Hamsters Facilities and Operating Standards § 3.27 Facilities, outdoor. (a) Hamsters shall not be housed in outdoor facilities. (b) Guinea pigs shall not be housed in outdoor facilities...

  17. 9 CFR 3.27 - Facilities, outdoor.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... WELFARE STANDARDS Specifications for the Humane Handling, Care, Treatment, and Transportation of Guinea Pigs and Hamsters Facilities and Operating Standards § 3.27 Facilities, outdoor. (a) Hamsters shall not be housed in outdoor facilities. (b) Guinea pigs shall not be housed in outdoor facilities...

  18. Hazardous waste management system: standards applicable to generators of hazardous waste and standards applicable to owners and operators of hazardous waste treatment, storage, and disposal facilities--Environmental Protection Agency. Proposed rule.

    PubMed

    1982-10-12

    The Environmental Protection Agency (EPA) is today proposing amendments to its hazardous waste regulations under Subtitle C of the Resource Conservation and Recovery Act (RCRA). These amendments would replace the annual reporting requirements for hazardous waste generators and owners and operators of hazardous waste treatment, storage, ad disposal (TSD) facilities with a biennial survey of representative samples of those populations. This approach will provide verifiable data on a wider range of topics, better serve EPA's long term regulatory needs under RCRA, and reduce significantly the information burden on the regulated community. PMID:10258157

  19. TECHNICAL BASIS FOR DOE STANDARD 3013 EQUIVALENCY SUPPORTING REDUCED TEMPERATURE STABILIZATION OF OXALATE-DERIVED PLUTONIUM DIOXIDE PRODUCED BY THE HB-LINE FACILITY AT SAVANNAH RIVER SITE

    SciTech Connect

    Duffey, J. M.; Livingston, R. R.; Berg, J. M.; Veirs, D. K.

    2013-02-06

    This report documents the technical basis for determining that stabilizing highpurity PuO{sub 2} derived from oxalate precipitation at the SRS HB-Line facility at a minimum of 625 {degree}C for at least four hours in an oxidizing atmosphere is equivalent to stabilizing at a minimum of 950 {degree}C for at least two hours as regards meeting the objectives of stabilization defined by DOE-STD-3013 if the material is handled in a way to prevent excessive absorption of water.

  20. Interim status standards for owners and operators of hazardous waste treatment, storage, and disposal facilities--Environmental Protection Agency. Interim final rule and interim final amendments to rules and request for comments.

    PubMed

    1981-11-17

    The Environmental Protection Agency [EPA] has issued standards applicable to owners and operators of hazardous waste management facilities as required by the Resource Conservation and Recovery Act [RCRA]. One of these standards bans the disposal of most containerized liquid hazardous waste in landfills, effective November 19, 1981. As a result of reconsideration of this restriction, EPA is today promulgating an interim final rule to allow the disposal of small containers of liquid and solid hazardous waste in landfills provided that the wastes are placed in overpacked drums [lab packs] in the manner specified in today's rule. The purpose of today's rule is to provide an environmental sound disposal option for generators of small containers of hazardous wastes, such as laboratories. PMID:10253364

  1. A Guide for Developing Standard Operating Job Procedures for the Tertiary Chemical Treatment - Lime Precipitation Process Wastewater Treatment Facility. SOJP No. 6.

    ERIC Educational Resources Information Center

    Petrasek, Al, Jr.

    This guide describes the standard operating job procedures for the tertiary chemical treatment - lime precipitation process of wastewater treatment plants. Step-by-step instructions are given for pre-start up, start-up, continuous operation, and shut-down procedures. In addition, some theoretical material is presented along with some relevant…

  2. Standards applicable to owners and operators of hazardous waste treatment, storage, and disposal facilities: liability requirements. Environmental Protection Agency. Revised interim final rule.

    PubMed

    1982-04-16

    The Environmental Protection Agency is today revising regulations of January 12, 1981, on liability coverage requirements for hazardous waste facility owners or operators. Under these requirements, owners or operators must demonstrate liability coverage for bodily injury and property damage to third parties resulting from facility operations. The major revisions are: addition of the option of a financial test as a means of demonstrating liability coverage to satisfy the requirements; addition of the option of submitting a certificate of insurance as evidence of insurance; and changes in the requirements for the endorsement and certificate. In a future document, EPA will propose to delete two provisions of the January 12, 1981 regulations. These provisions are: the procedure to obtain a variance for liability coverage requirements; and the provision allowing an owner or operator to use State assumption of legal responsibility for liability coverage to satisfy the liability requirements. The January 12, 1981, regulations were issued under an accelerated schedule imposed by a court order. The revisions that are being made today are necessary to eliminate unworkable aspects of the previous regulations, improve their effectiveness, and allow reasonable flexibility in satisfying the requirements. PMID:10255071

  3. Site-specific standard request for underground storage tanks 1219-U, 1222-U, 2082-U, and 2068-U at the rust garage facility buildings 9754-1 and 9720-15: Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, Facility ID No. 0-010117

    SciTech Connect

    1994-12-01

    This document represents a Site-specific Standard Request for underground storage tanks (USTs) 1219-U,1222-U and 2082-U previously located at former Building 9754-1, and tank 2086-U previously located at Building 9720-15, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. The tanks previously contained petroleum products. For the purposes of this report, the two building sites will be regarded as a single UST site and will be referred to as the Rust Garage Facility. The current land use associated with the Y-12 Plant is light industrial and the operational period of the plant is projected to be at least 30 years. Thus, potential future residential exposures are not expected to occur for at least 30 years. Based on the degradation coefficient for benzene (the only carcinogenic petroleum constituent detected in soils or groundwater at the Rust Garage Facility), it is expected that the benzene and other contaminants at the site will likely be reduced prior to expiration of the 30-year plant operational period. As the original sources of petroleum contamination have been removed, and the area of petroleum contamination is limited, a site-specific standard is therefore being requested for the Rust Garage Facility.

  4. Design and verification of the shielding around the new Neutron Standards Laboratory (LPN) at CIEMAT.

    PubMed

    Méndez-Villafañe, R; Guerrero, J E; Embid, M; Fernández, R; Grandio, R; Pérez-Cejuela, P; Márquez, J L; Alvarez, F; Ortego, P

    2014-10-01

    The construction of the new Neutron Standards Laboratory at CIEMAT (Laboratorio de Patrones Neutrónicos) has been finalised and is ready to provide service. The facility is an ∼8 m×8 m×8 m irradiation vault, following the International Organization for Standardization 8529 recommendations. It relies on several neutron sources: a 5-GBq (5.8× 10(8) s(-1)) (252)Cf source and two (241)Am-Be neutron sources (185 and 11.1 GBq). The irradiation point is located 4 m over the ground level and in the geometrical centre of the room. Each neutron source can be moved remotely from its storage position inside a water pool to the irradiation point. Prior to this, an important task to design the neutron shielding and to choose the most appropriate materials has been developed by the Radiological Security Unit and the Ionizing Radiations Metrology Laboratory. MCNPX was chosen to simulate the irradiation facility. With this information the walls were built with a thickness of 125 cm. Special attention was put on the weak points (main door, air conditioning system, etc.) so that the ambient dose outside the facility was below the regulatory limits. Finally, the Radiation Protection Unit carried out a set of measurements in specific points around the installation with an LB6411 neutron monitor and a Reuter-Stokes high-pressure ion chamber to verify experimentally the results of the simulation. PMID:24478306

  5. Predictors of survival and effect of short (40 Gy) or standard-course (60 Gy) irradiation plus concomitant temozolomide in elderly patients with glioblastoma: a multicenter retrospective study of AINO (Italian Association of Neuro-Oncology).

    PubMed

    Lombardi, Giuseppe; Pace, Andrea; Pasqualetti, Francesco; Rizzato, Simona; Faedi, Marina; Anghileri, Elena; Nicolotto, Elisa; Bazzoli, Elena; Bellu, Luisa; Villani, Veronica; Fabi, Alessandra; Ferrazza, Patrizia; Gurrieri, Lorena; Dall'Agata, Monia; Eoli, Marica; Della Puppa, Alessandro; Pambuku, Ardi; D'Avella, Domenico; Berti, Franco; Rudà, Roberta; Zagonel, Vittorina

    2015-11-01

    The efficacy of temozolomide (TMZ) plus radiation therapy (RT) in elderly patients with glioblastoma is unclear. We performed a large multicenter retrospective study to analyze prognostic factors and clinical outcome in these patients. Inclusion criteria were age ≥65 years, newly histologically confirmed glioblastoma, ECOG PS 0-2, adjuvant treatment with RT plus TMZ. We enrolled 237 patients; the average age was 71 and ECOG PS was 0-1 in 196 patients; gross total resection was performed in 174 cases. MGMT was analyzed in 151 persons and was methylated in 56 %. IDH1 was assessed in 100 patients and was mutated in 6 %. Seventy-one patients were treated with RT 40 Gy and 166 with RT 60 Gy. Progression-free survival and overall survival (OS) were 11.3 and 17.3 months, respectively. Overall survival was 19.4 vs 13.8 months for patients treated with RT 60 Gy and 40 Gy (p = 0.02); OS was 17.7 versus 16.1 months for patients treated with gross total resection vs partial surgery (p = 0.02); OS was 21.2 versus 13.6 months for methylated and unmethylated MGMT (p < 0.001). On multivariate analysis, gross total resection, RT 60 Gy, methylated MGMT and ECOG PS 0-1 were independent predictors of longer survival. Twenty-five patients (10 %) had grade 3-4 haematological toxicity during the concomitant treatment. We showed that, in elderly patients in good clinical condition treated with concomitant treatment, standard-course irradiation might be more effective than short-course irradiation. Methylated MGMT remains the most important prognostic factor. PMID:26423801

  6. Interim status standards for owners and operators of hazardous waste treatment, storage, and disposal facilities: Environmental Protection Agency. Proposed amendments to rule.

    PubMed

    1982-02-25

    On May 19, 1980, EPA promulgated regulations, applicable to owners and operators of hazardous waste treatment, storage, and disposal facilities during interim status, which prohibited the landfill disposal of most containerized liquid waste or waste containing free liquid on and after November 19, 1981. As a result of issues raised by the regulated community with respect to this prohibition, the Agency is today proposing an amendment to this regulation to allow some containers holding free liquids to be disposed of in a landfill, in some circumstances. In a separate action in today's federal Register, EPA is providing a 90-day extension (from today's date) of the compliance date for the prohibition of landfill disposal of containerized liquid waste and the restrictions on the landfill disposal of liquid ignitable waste to allow time to complete this rulemaking action and to avoid immediately imposing requirements that might be changed as a result of this rulemaking action. PMID:10254380

  7. Container and waste pile standards for owners and operators of hazardous waste facilities: consolidated permit regulations--Environmental Protection Agency. Amendments to interim final rule.

    PubMed

    1981-11-01

    The Environmental Protection Agency (EPA) is today promulgating amendments to the hazardous waste management regulations regarding the management of hazardous waste in containers and piles and associated permit regulations (40 CFR Part 264, Subparts I and L, and Part 122, Subpart B). These amendments better tailor the standards to the particular type of hazard posed by specific situations. The standards for containers are amended to waive the containment system requirements for wastes that do not contain free liquids, provided that the wastes are protected from contact with accumulated liquid. The standards for waste piles are amended to waive the containment system requirements for wastes that do not contain free liquids, provided that the pile is protected from precipitation by a structure and from surface water run-on and wind dispersal of the waste by the structure or some other means. The Agency believes these amendments believes these amendments will not reduce the level of protection of human health and the environment. PMID:10253362

  8. Investigation of the effect of some irradiation parameters on the response of various types of dosimeters to electron irradiation

    NASA Astrophysics Data System (ADS)

    Farah, K.; Kuntz, F.; Kadri, O.; Ghedira, L.

    2004-09-01

    Several undyed and dyed polymer films are commercially available for dosimetry in intense radiation fields, especially for radiation processing of food and sterilisation of medical devices. The effects of temperature during irradiation and post-irradiation stability, on the response of these dosimeters are of importance to operators of irradiation facilities. The present study investigates the effects of temperature during irradiation by 2.2 MeV electrons beam accelerator and post irradiation storage on the response of several types of dosimeter films. All dosimeters showed a significant effect of temperature during irradiation and post-irradiation storage.

  9. Centurion — a revolutionary irradiator

    NASA Astrophysics Data System (ADS)

    McKinney, Dan; Perrins, Robert

    2000-03-01

    The facility characteristics for irradiation of red meat and poultry differ significantly from those of medical disposables. This paper presents the results of the market requirement definition which resulted in an innovative conceptual design. The process and the "state of the art tools" used to bring this abstract idea into a proof of concept are presented.

  10. A demonstration of CMOS VLSI circuit prototyping in support of the site facility using the 1.2 micron standard cell library developed by National Security Agency

    NASA Technical Reports Server (NTRS)

    Smith, Edwyn D.

    1991-01-01

    Two silicon CMOS application specific integrated circuits (ASICs), a data generation chip, and a data checker chip were designed. The conversion of the data generator circuitry into a pair of CMOS ASIC chips using the 1.2 micron standard cell library is documented. The logic design of the data checker is discussed. The functions of the control circuitry is described. An accurate estimate of timing relationships is essential to make sure that the logic design performs correctly under practical conditions. Timing and delay information are examined.

  11. Acceptable standard format and content for the fundamental nuclear material control (FNMC) plan required for low-enriched uranium facilities. Revision 2

    SciTech Connect

    Joy, D.R.

    1995-12-01

    This report documents a standard format suggested by the NRC for use in preparing fundamental nuclear material control (FNMC) plans as required by the Low Enriched Uranium Reform Amendments (10CFR 74.31). This report also describes the necessary contents of a comprehensive plan and provides example acceptance criteria which are intended to communicate acceptable means of achieving the performance capabilities of the Reform Amendments. By using the suggested format, the licensee or applicant will minimize administrative problems associated with the submittal, review and approval of the FNMC plan. Preparation of the plan in accordance with this format Will assist the NRC in evaluating the plan and in standardizing the review and licensing process. However, conformance with this guidance is not required by the NRC. A license applicant who employs a format that provides a equal level of completeness and detail may use their own format. This document is also intended for providing guidance to licensees when making revisions to their FNMC plan.

  12. Tissue irradiator

    DOEpatents

    Hungate, F.P.; Riemath, W.F.; Bunnell, L.R.

    1975-12-16

    A tissue irradiator is provided for the in-vivo irradiation of body tissue. The irradiator comprises a radiation source material contained and completely encapsulated within vitreous carbon. An embodiment for use as an in- vivo blood irradiator comprises a cylindrical body having an axial bore therethrough. A radioisotope is contained within a first portion of vitreous carbon cylindrically surrounding the axial bore, and a containment portion of vitreous carbon surrounds the radioisotope containing portion, the two portions of vitreous carbon being integrally formed as a single unit. Connecting means are provided at each end of the cylindrical body to permit connections to blood- carrying vessels and to provide for passage of blood through the bore. In a preferred embodiment, the radioisotope is thulium-170 which is present in the irradiator in the form of thulium oxide. A method of producing the preferred blood irradiator is also provided, whereby nonradioactive thulium-169 is dispersed within a polyfurfuryl alcohol resin which is carbonized and fired to form the integral vitreous carbon body and the device is activated by neutron bombardment of the thulium-169 to produce the beta-emitting thulium-170.

  13. The solar absolute spectral irradiance 1150-3173 A - May 17, 1982

    NASA Technical Reports Server (NTRS)

    Mount, G. H.; Rottman, G. J.

    1983-01-01

    The full-disk solar spectral irradiance in the spectral range 1150-3173 A was obtained from a rocket observation above White Sands Missile Range, NM, on May 17, 1982, half way in time between solar maximum and solar minimum. Comparison with measurements made during solar maximum in 1980 indicate a large decrease in the absolute solar irradiance at wavelengths below 1900 A to approximately solar minimum values. No change above 1900 A from solar maximum to this flight was observed to within the errors of the measurements. Irradiance values lower than the Broadfoot results in the 2100-2500 A spectral range are found, but excellent agreement with Broadfoot between 2500 and 3173 A is found. The absolute calibration of the instruments for this flight was accomplished at the National Bureau of Standards Synchrotron Radiation Facility which significantly improves calibration of solar measurements made in this spectral region.

  14. Metal fuel test program in the Fast Flux Test Facility

    SciTech Connect

    Pitner, A.L.; Baker, R.B.

    1992-10-01

    This report discusses irradiation testing of metal fuel assemblies in the Fast Flux Test Facility (FFTF) which has demonstrated the viability of this robust fuel design for liquid metal reactor applications. This fuel design provides high burnup capability with reduced fabrication costs relative to standard mixed-oxide FFTF driver fuel assemblies. Development of this fuel design required the establishment of innovative sodium bonding technology as well as special techniques for sodium bond quality verification. Eight metal fuel test assemblies have been irradiated under demanding conditions to burnups as high as 143 MWd/kgM with no indication of pin breach. The unique FFTF instrumentation system has permitted the in situ observation of axial fuel growth in metal fuel assemblies.

  15. Computational and experimental physics performance characterization of the neutron capture therapy research facility at Washington State Univ

    SciTech Connect

    Nigg, D. W.; Sloan, P. E.; Venhuizen, J. R.; Wemple, C. A.; Tripard, G. E.; Fox, K.; Corwin, E.

    2006-07-01

    This paper summarizes the results of the final beam characterization measurements for a dual mode epithermal-thermal beam facility for neutron capture therapy research that was recently constructed at the Washington State Univ. TRIGA{sup TM} research reactor. The results show that the performance of the beam facility is consistent with the design computations and with international standards for the intended application. A useful epithermal neutron flux of 1.3 x 10{sup 9} n/cm{sup 2}-s is produced at the irradiation point with the beam in epithermal mode and shaped by a 10-cm circular aperture plate. When the beam is thermalized with approximately 34 cm of heavy water, the useful thermal flux at the irradiation point is approximately 3.5 x 10{sup 8} n/cm{sup 2}-s. The new WSU facility is one of only two such installations currently operating in the US. (authors)

  16. Higher Early Monocyte and Total Lymphocyte Counts Are Associated with Better Overall Survival after Standard Total Body Irradiation, Cyclophosphamide, and Fludarabine Reduced-Intensity Conditioning Double Umbilical Cord Blood Allogeneic Stem Cell Transplantation in Adults.

    PubMed

    Le Bourgeois, Amandine; Peterlin, Pierre; Guillaume, Thierry; Delaunay, Jacques; Duquesne, Alix; Le Gouill, Steven; Moreau, Philippe; Mohty, Mohamad; Campion, Loïc; Chevallier, Patrice

    2016-08-01

    This single-center retrospective study aimed to report the impact of early hematopoietic and immune recoveries after a standard total body irradiation, cyclophosphamide, and fludarabine (TCF) reduced-intensity conditioning (RIC) regimen for double umbilical cord blood (dUCB) allogeneic stem cell transplantation (allo-SCT) in adults. We analyzed 47 consecutive patients older than 17 years who engrafted after a dUCB TCF allo-SCT performed between January 2006 and April 2013 in our department. Median times for neutrophil and platelet recoveries were 17 (range, 6 to 59) and 37 days (range, 0 to 164), respectively. The 3-year overall (OS) and disease-free survivals, relapse incidence, and nonrelapse mortality were 65.7%, 57.2%, 27.1%, and 19%, respectively. In multivariate analysis, higher day +30 monocyte (≥615/mm(3); hazard ratio [HR], .04; 95% confidence interval [CI], .004 to .36; P < .01) and day +42 lymphocyte (≥395/mm(3); HR, .16; 95% CI, .03 to .78; P = .02) counts were independently associated with better OS. These results suggest that early higher hematopoietic and immune recovery is predictive of survival after dUCB TCF RIC allo-SCT in adults. Factors other than granulocyte colony-stimulating factor, which was used in all cases, favoring expansion of monocytes or lymphocytes, should be tested in the future as part of the UCB transplantation procedure. PMID:27118570

  17. Nanoindentation on ion irradiated steels

    NASA Astrophysics Data System (ADS)

    Hosemann, P.; Vieh, C.; Greco, R. R.; Kabra, S.; Valdez, J. A.; Cappiello, M. J.; Maloy, S. A.

    2009-06-01

    Radiation induced mechanical property changes can cause major difficulties in designing systems operating in a radiation environment. Investigating these mechanical property changes in an irradiation environment is a costly and time consuming activity. Ion beam accelerator experiments have the advantage of allowing relatively fast and inexpensive materials irradiations without activating the sample but do in general not allow large beam penetration depth into the sample. In this study, the ferritic/martensitic steel HT-9 was processed and heat treated to produce one specimen with a large grained ferritic microstructure and further heat treated to form a second specimen with a fine tempered martensitic lath structure and exposed to an ion beam and tested after irradiation using nanoindentation to investigate the irradiation induced changes in mechanical properties. It is shown that the HT-9 in the ferritic heat treatment is more susceptible to irradiation hardening than HT-9 after the tempered martensitic heat treatment. Also at an irradiation temperature above 550 °C no detectable hardness increase due to irradiation was detected. The results are also compared to data from the literature gained from the fast flux test facility.

  18. Survival of spacecraft-associated microorganisms under simulated martian UV irradiation.

    PubMed

    Newcombe, David A; Schuerger, Andrew C; Benardini, James N; Dickinson, Danielle; Tanner, Roger; Venkateswaran, Kasthuri

    2005-12-01

    Spore-forming microbes recovered from spacecraft surfaces and assembly facilities were exposed to simulated Martian UV irradiation. The effects of UVA (315 to 400 nm), UVA+B (280 to 400 nm), and the full UV spectrum (200 to 400 nm) on the survival of microorganisms were studied at UV intensities expected to strike the surfaces of Mars. Microbial species isolated from the surfaces of several spacecraft, including Mars Odyssey, X-2000 (avionics), and the International Space Station, and their assembly facilities were identified using 16S rRNA gene sequencing. Forty-three Bacillus spore lines were screened, and 19 isolates showed resistance to UVC irradiation (200 to 280 nm) after exposure to 1,000 J m(-2) of UVC irradiation at 254 nm using a low-pressure mercury lamp. Spores of Bacillus species isolated from spacecraft-associated surfaces were more resistant than a standard dosimetric strain, Bacillus subtilis 168. In addition, the exposure time required for UVA+B irradiation to reduce the viable spore numbers by 90% was 35-fold longer than the exposure time required for the full UV spectrum to do this, confirming that UVC is the primary biocidal bandwidth. Among the Bacillus species tested, spores of a Bacillus pumilus strain showed the greatest resistance to all three UV bandwidths, as well as the total spectrum. The resistance to simulated Mars UV irradiation was strain specific; B. pumilus SAFR-032 exhibited greater resistance than all other strains tested. The isolation of organisms like B. pumilus SAFR-032 and the greater survival of this organism (sixfold) than of the standard dosimetric strains should be considered when the sanitation capabilities of UV irradiation are determined. PMID:16332797

  19. Survival of Spacecraft-Associated Microorganisms under Simulated Martian UV Irradiation

    PubMed Central

    Newcombe, David A.; Schuerger, Andrew C.; Benardini, James N.; Dickinson, Danielle; Tanner, Roger; Venkateswaran, Kasthuri

    2005-01-01

    Spore-forming microbes recovered from spacecraft surfaces and assembly facilities were exposed to simulated Martian UV irradiation. The effects of UVA (315 to 400 nm), UVA+B (280 to 400 nm), and the full UV spectrum (200 to 400 nm) on the survival of microorganisms were studied at UV intensities expected to strike the surfaces of Mars. Microbial species isolated from the surfaces of several spacecraft, including Mars Odyssey, X-2000 (avionics), and the International Space Station, and their assembly facilities were identified using 16S rRNA gene sequencing. Forty-three Bacillus spore lines were screened, and 19 isolates showed resistance to UVC irradiation (200 to 280 nm) after exposure to 1,000 J m−2 of UVC irradiation at 254 nm using a low-pressure mercury lamp. Spores of Bacillus species isolated from spacecraft-associated surfaces were more resistant than a standard dosimetric strain, Bacillus subtilis 168. In addition, the exposure time required for UVA+B irradiation to reduce the viable spore numbers by 90% was 35-fold longer than the exposure time required for the full UV spectrum to do this, confirming that UVC is the primary biocidal bandwidth. Among the Bacillus species tested, spores of a Bacillus pumilus strain showed the greatest resistance to all three UV bandwidths, as well as the total spectrum. The resistance to simulated Mars UV irradiation was strain specific; B. pumilus SAFR-032 exhibited greater resistance than all other strains tested. The isolation of organisms like B. pumilus SAFR-032 and the greater survival of this organism (sixfold) than of the standard dosimetric strains should be considered when the sanitation capabilities of UV irradiation are determined. PMID:16332797

  20. The DAΦNE-Light Facility

    NASA Astrophysics Data System (ADS)

    Burattini, Emilio; Cinque, Gianfelice; Dabagov, Sultan; Grilli, Antonio; Marcelli, Augusto; Monti, Francesca; Pace, Elisabetta; Piccinini, Massimo; Raco, Agostino

    2004-05-01

    The new Synchrotron Radiation facility at Frascati exploits the intense photon emission from DAΦNE, the 0,51 GeV storage ring circulating over 1 A of electrons. Among the three beamlines commissioned, the Synchrotron INfrared Beamline At Daφne (SINBAD) is fully operational by a brilliant SR beam spanning the entire IR. Recently, the soft X-ray beamline has been characterized and, once implemented the double-crystal monocromator, X-ray Absorption Spectroscopy is applied on material standards in the distinguishing energy region below 4 keV. An UltraViolet line, presently dedicated to photobiology dosimetry, has also given first results on cell irradiation in the UVB band.

  1. The DA{phi}NE-Light Facility

    SciTech Connect

    Burattini, Emilio; Cinque, Gianfelice; Dabagov, Sultan; Grilli, Antonio; Marcelli, Augusto; Pace, Elisabetta; Piccinini, Massimo; Raco, Agostino; Monti, Francesca

    2004-05-12

    The new Synchrotron Radiation facility at Frascati exploits the intense photon emission from DA{phi}NE, the 0,51 GeV storage ring circulating over 1 A of electrons. Among the three beamlines commissioned, the Synchrotron INfrared Beamline At Da{phi}ne (SINBAD) is fully operational by a brilliant SR beam spanning the entire IR. Recently, the soft X-ray beamline has been characterized and, once implemented the double-crystal monocromator, X-ray Absorption Spectroscopy is applied on material standards in the distinguishing energy region below 4 keV. An UltraViolet line, presently dedicated to photobiology dosimetry, has also given first results on cell irradiation in the UVB band.

  2. Overview of the IFMIF test facility

    NASA Astrophysics Data System (ADS)

    Möslang, A.; Antonnucci, C.; Daum, E.; Haines, J. R.; Jitsukawa, I.; Noda, K.; Zinkle, S.

    1998-10-01

    During the past few years, a reference design has been developed for the International Fusion Materials Irradiation Facility (IFMIF). According to the mission and specification of the general requirements, this reference design includes relevant machine parameters and conceptual designs for the major device subsystems - Test Facilities, Lithium Target Facilities and Accelerator Facilities. Major engineering efforts have been undertaken to establish a test cell design that follows closely the users requirements of the fusion materials community and allows safe and completely remote controlled handling. After a short description of the facility requirements, concepts for the two independent test cells, various test assemblies, remote handling equipment and hot cell facilities are presented.

  3. Auditing radiation sterilization facilities

    NASA Astrophysics Data System (ADS)

    Beck, Jeffrey A.

    The diversity of radiation sterilization systems available today places renewed emphasis on the need for thorough Quality Assurance audits of these facilities. Evaluating compliance with Good Manufacturing Practices is an obvious requirement, but an effective audit must also evaluate installation and performance qualification programs (validation_, and process control and monitoring procedures in detail. The present paper describes general standards that radiation sterilization operations should meet in each of these key areas, and provides basic guidance for conducting QA audits of these facilities.

  4. Irradiation subassembly

    DOEpatents

    Seim, O.S.; Filewicz, E.C.; Hutter, E.

    1973-10-23

    An irradiation subassembly for use in a nuclear reactor is described which includes a bundle of slender elongated irradiation -capsules or fuel elements enclosed by a coolant tube and having yieldable retaining liner between the irradiation capsules and the coolant tube. For a hexagonal bundle surrounded by a hexagonal tube the yieldable retaining liner may consist either of six segments corresponding to the six sides of the tube or three angular segments each corresponding in two adjacent sides of the tube. The sides of adjacent segments abut and are so cut that metal-tometal contact is retained when the volume enclosed by the retaining liner is varied and Springs are provided for urging the segments toward the center of the tube to hold the capsules in a closely packed configuration. (Official Gazette)

  5. 9 CFR 3.25 - Facilities, general.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... WELFARE STANDARDS Specifications for the Humane Handling, Care, Treatment, and Transportation of Guinea Pigs and Hamsters Facilities and Operating Standards § 3.25 Facilities, general. (a) Structural strength. Indoor and outdoor housing facilities for guinea pigs or hamsters shall be structurally sound...

  6. 9 CFR 3.25 - Facilities, general.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... WELFARE STANDARDS Specifications for the Humane Handling, Care, Treatment, and Transportation of Guinea Pigs and Hamsters Facilities and Operating Standards § 3.25 Facilities, general. (a) Structural strength. Indoor and outdoor housing facilities for guinea pigs or hamsters shall be structurally sound...

  7. Irradiance gradients

    SciTech Connect

    Ward, G.J. Ecole Polytechnique Federale, Lausanne ); Heckbert, P.S. . School of Computer Science Technische Hogeschool Delft . Dept. of Technical Mathematics and Informatics)

    1992-04-01

    A new method for improving the accuracy of a diffuse interreflection calculation is introduced in a ray tracing context. The information from a hemispherical sampling of the luminous environment is interpreted in a new way to predict the change in irradiance as a function of position and surface orientation. The additional computation involved is modest and the benefit is substantial. An improved interpolation of irradiance resulting from the gradient calculation produces smoother, more accurate renderings. This result is achieved through better utilization of ray samples rather than additional samples or alternate sampling strategies. Thus, the technique is applicable to a variety of global illumination algorithms that use hemicubes or Monte Carlo sampling techniques.

  8. Updates to ISO 21348 (determining solar irradiances)

    NASA Astrophysics Data System (ADS)

    Tobiska, W. Kent

    2012-07-01

    The ISO 21348 (Determining Solar Irradiances) International Standard is going through a document update. A consensus solar spectrum, solar indices/proxies descriptions, solar model descriptions, and solar measurement descriptions are among the Annexes that are proposed to the standard. These topics will be reviewed and described. The International Standards Organization (ISO) published IS 21348 in 2007 after 7 years of development by the international scientific community. In ISO, documents are reviewed on a regular basis and reaffirmed, updated, or deleted according to the votes of national delegations represented in ISO. IS 21348 provides guidelines for specifying the process of determining solar irradiances. Solar irradiances are reported through products such as measurement sets, reference spectra, empirical models, theoretical models and solar irradiance proxies or indices. These products are used in scientific and engineering applications to characterize within the natural space environment solar irradiances that are relevant to space systems and materials. Examples of applications using input solar irradiance energy include the determination of atmospheric densities for spacecraft orbit determination, attitude control and re-entry calculations, as well as for debris mitigation and collision avoidance activity. Direct and indirect pressure from solar irradiance upon spacecraft surfaces also affects attitude control separately from atmospheric density effects. Solar irradiances are used to provide inputs for a) calculations of ionospheric parameters, b) photon-induced radiation effects, and c) radiative transfer modeling of planetary atmospheres. Input solar irradiance energy is used to characterize material properties related to spacecraft thermal control, including surface temperatures, reflectivity, absorption and degradation. Solar energy applications requiring a standard process for determining solar irradiance energy include i) solar cell power

  9. Design study of multi-imaging plate system for BNCT irradiation field at Kyoto university reactor.

    PubMed

    Tanaka, Kenichi; Sakurai, Yoshinori; Kajimoto, Tsuyoshi; Tanaka, Hiroki; Takata, Takushi; Endo, Satoru

    2016-09-01

    The converter configuration for a multi-imaging plate system was investigated for the application of quality assurance in the irradiation field profile for boron neutron capture therapy. This was performed by the simulation calculation using the PHITS code in the fields at the Heavy Water Neutron Irradiation Facility of Kyoto University Reactor. The converter constituents investigated were carbon for gamma rays, and polyethylene with and without LiF at varied (6)Li concentration for thermal, epithermal, and fast neutrons. Consequently, potential combinations of the converters were found for two components, gamma rays and thermal neutrons, for the standard thermal neutron mode and three components of gamma rays, epithermal neutrons, and thermal or fast neutrons, for the standard mixed or epithermal neutron modes, respectively. PMID:27423022

  10. Health Facilities

    MedlinePlus

    Health facilities are places that provide health care. They include hospitals, clinics, outpatient care centers, and specialized care centers, ... psychiatric care centers. When you choose a health facility, you might want to consider How close it ...

  11. 9 CFR 3.51 - Facilities, indoor.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 9 Animals and Animal Products 1 2013-01-01 2013-01-01 false Facilities, indoor. 3.51 Section 3.51 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE ANIMAL... Facilities and Operating Standards § 3.51 Facilities, indoor. (a) Heating. Indoor housing facilities...

  12. 20 CFR 654.416 - Sleeping facilities.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 20 Employees' Benefits 3 2013-04-01 2013-04-01 false Sleeping facilities. 654.416 Section 654.416... THE EMPLOYMENT SERVICE SYSTEM Housing for Agricultural Workers Housing Standards § 654.416 Sleeping facilities. (a) Sleeping facilities shall be provided for each person. Such facilities shall consist...

  13. 20 CFR 654.416 - Sleeping facilities.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 20 Employees' Benefits 3 2012-04-01 2012-04-01 false Sleeping facilities. 654.416 Section 654.416... THE EMPLOYMENT SERVICE SYSTEM Housing for Agricultural Workers Housing Standards § 654.416 Sleeping facilities. (a) Sleeping facilities shall be provided for each person. Such facilities shall consist...

  14. Standards and Administration.

    ERIC Educational Resources Information Center

    Gross, S. P.

    1978-01-01

    Presents a literature review of water quality standards and administration, covering publications of 1976-77. Consideration is given to municipal facilities, National Pollutant Discharge Elimination Systems, regional and international water quality management, and effluent standards. A list of 99 references is also presented. (HM)

  15. Establishment of 6- to 7-MeV high-energy gamma-ray calibration fields produced using the 4-MV Van de Graaff accelerator at the Facility of Radiation Standards, Japan Atomic Energy Agency.

    PubMed

    Kowatari, Munehiko; Tanimura, Yoshihiko

    2016-03-01

    A 6- to 7-MeV high-energy gamma-ray field, produced by the nuclear reaction of (19)F(p, αγ)(16)O, has been established at the Facility of Radiation Standards (FRS) in Japan Atomic Energy Agency for calibration purposes. Basic dosimetric quantities (i.e. averaged gamma-ray energy, air-kerma-to-dose equivalent conversion coefficients and air kerma rates at the point of test) have been precisely determined through a series of measurements using the NaI(Tl) spectrometer and an ionisation chamber coupled with an appropriate build-up material. The measurements obtained comply with values recommended by the International Organization for Standardization for an 'R-F field'. The neutron contamination component for the field has also been measured by means of a conventional neutron dose equivalent meter (the so-called neutron rem-counter) and determined to be ∼ 0.5 % of the total dose equivalent. PMID:26012483

  16. Irradiated foods

    MedlinePlus

    ... it reduces the risk of food poisoning . Food irradiation is used in many countries. It was first approved in the U.S. to prevent sprouts on white potatoes, and to control insects on wheat and in certain spices and seasonings.

  17. Novel neutron sources at the Radiological Research Accelerator Facility.

    PubMed

    Xu, Yanping; Garty, Guy; Marino, Stephen A; Massey, Thomas N; Randers-Pehrson, Gerhard; Johnson, Gary W; Brenner, David J

    2012-03-16

    Since the 1960s, the Radiological Research Accelerator Facility (RARAF) has been providing researchers in biology, chemistry and physics with advanced irradiation techniques, using charged particles, photons and neutrons.We are currently developing a unique facility at RARAF, to simulate neutron spectra from an improvised nuclear device (IND), based on calculations of the neutron spectrum at 1.5 km from the epicenter of the Hiroshima atom bomb. This is significantly different from a standard fission spectrum, because the spectrum changes as the neutrons are transported through air, and is dominated by neutron energies between 0.05 and 8 MeV. This facility will be based on a mixed proton/deuteron beam impinging on a thick beryllium target.A second, novel facility under development is our new neutron microbeam. The neutron microbeam will, for the first time, provide a kinematically collimated neutron beam, 10-20 micron in diameter. This facility is based on a Proton Microbeam, impinging on a thin lithium target near the threshold of the (7)Li(p,n)(7)Be reaction. This novel neutron microbeam will enable studies of neutron damage to small targets, such as single cells, individual organs within small animals or microelectronic components. PMID:22545061

  18. Novel neutron sources at the Radiological Research Accelerator Facility

    DOE PAGESBeta

    Xu, Yanping; Garty, G.; Marino, S. A.; Massey, Thomas Neal; Johnson, G. W.; Randers-Pehrson, Gerhard; Brenner, D. J.

    2012-03-16

    Since the 1960s, the Radiological Research Accelerator Facility (RARAF) has been providing researchers in biology, chemistry and physics with advanced irradiation techniques, using charged particles, photons and neutrons. We are currently developing a unique facility at RARAF, to simulate neutron spectra from an improvised nuclear device (IND), based on calculations of the neutron spectrum at 1.5 km from the epicenter of the Hiroshima atom bomb. This is significantly different from a standard fission spectrum, because the spectrum changes as the neutrons are transported through air, and is dominated by neutron energies between 0.05 and 8 MeV. This facility will bemore » based on a mixed proton/deuteron beam impinging on a thick beryllium target. A second, novel facility under development is our new neutron microbeam. The neutron microbeam will, for the first time, provide a kinematically collimated neutron beam, 10-20 micron in diameter. This facility is based on a proton microbeam, impinging on a thin lithium target near the threshold of the Li-7(p,n)Be-7 reaction. Lastly, this novel neutron microbeam will enable studies of neutron damage to small targets, such as single cells, individual organs within small animals or microelectronic components.« less

  19. Novel neutron sources at the Radiological Research Accelerator Facility

    PubMed Central

    Xu, Yanping; Garty, Guy; Marino, Stephen A.; Massey, Thomas N.; Randers-Pehrson, Gerhard; Johnson, Gary W.; Brenner, David J.

    2012-01-01

    Since the 1960s, the Radiological Research Accelerator Facility (RARAF) has been providing researchers in biology, chemistry and physics with advanced irradiation techniques, using charged particles, photons and neutrons. We are currently developing a unique facility at RARAF, to simulate neutron spectra from an improvised nuclear device (IND), based on calculations of the neutron spectrum at 1.5 km from the epicenter of the Hiroshima atom bomb. This is significantly different from a standard fission spectrum, because the spectrum changes as the neutrons are transported through air, and is dominated by neutron energies between 0.05 and 8 MeV. This facility will be based on a mixed proton/deuteron beam impinging on a thick beryllium target. A second, novel facility under development is our new neutron microbeam. The neutron microbeam will, for the first time, provide a kinematically collimated neutron beam, 10–20 micron in diameter. This facility is based on a Proton Microbeam, impinging on a thin lithium target near the threshold of the 7Li(p,n)7Be reaction. This novel neutron microbeam will enable studies of neutron damage to small targets, such as single cells, individual organs within small animals or microelectronic components. PMID:22545061

  20. Novel neutron sources at the Radiological Research Accelerator Facility

    SciTech Connect

    Xu, Yanping; Garty, G.; Marino, S. A.; Massey, Thomas Neal; Johnson, G. W.; Randers-Pehrson, Gerhard; Brenner, D. J.

    2012-03-16

    Since the 1960s, the Radiological Research Accelerator Facility (RARAF) has been providing researchers in biology, chemistry and physics with advanced irradiation techniques, using charged particles, photons and neutrons. We are currently developing a unique facility at RARAF, to simulate neutron spectra from an improvised nuclear device (IND), based on calculations of the neutron spectrum at 1.5 km from the epicenter of the Hiroshima atom bomb. This is significantly different from a standard fission spectrum, because the spectrum changes as the neutrons are transported through air, and is dominated by neutron energies between 0.05 and 8 MeV. This facility will be based on a mixed proton/deuteron beam impinging on a thick beryllium target. A second, novel facility under development is our new neutron microbeam. The neutron microbeam will, for the first time, provide a kinematically collimated neutron beam, 10-20 micron in diameter. This facility is based on a proton microbeam, impinging on a thin lithium target near the threshold of the Li-7(p,n)Be-7 reaction. Lastly, this novel neutron microbeam will enable studies of neutron damage to small targets, such as single cells, individual organs within small animals or microelectronic components.

  1. Novel neutron sources at the Radiological Research Accelerator Facility

    NASA Astrophysics Data System (ADS)

    Xu, Y.; Garty, G.; Marino, S. A.; Massey, T. N.; Randers-Pehrson, G.; Johnson, G. W.; Brenner, D. J.

    2012-03-01

    Since the 1960s, the Radiological Research Accelerator Facility (RARAF) has been providing researchers in biology, chemistry and physics with advanced irradiation techniques, using charged particles, photons and neutrons. We are currently developing a unique facility at RARAF, to simulate neutron spectra from an improvised nuclear device (IND), based on calculations of the neutron spectrum at 1.5 km from the epicenter of the Hiroshima atom bomb. This is significantly different from a standard fission spectrum, because the spectrum changes as the neutrons are transported through air, and is dominated by neutron energies between 0.05 and 8 MeV. This facility will be based on a mixed proton/deuteron beam impinging on a thick beryllium target. A second, novel facility under development is our new neutron microbeam. The neutron microbeam will, for the first time, provide a kinematically collimated neutron beam, 10-20 micron in diameter. This facility is based on a proton microbeam, impinging on a thin lithium target near the threshold of the 7Li(p,n)7Be reaction. This novel neutron microbeam will enable studies of neutron damage to small targets, such as single cells, individual organs within small animals or microelectronic components.

  2. Phytosanitary of irradiation of fresh tropical commodities in Hawaii: generic treatments, commercial adoption and current issues

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Hawaii Pride is a pioneer in the use of phytosanitary irradiation. The commercial x-ray irradiation facility , Hawaii Pride LLC, has been shipping papaya and other tropical fruits and vegetables to the United States mainland using irradiation for 11 years. Irradiation is an approved treatment to con...

  3. HRB-22 irradiation phase test data report

    SciTech Connect

    Montgomery, F.C.; Acharya, R.T.; Baldwin, C.A.; Rittenhouse, P.L.; Thoms, K.R.; Wallace, R.L.

    1995-03-01

    Irradiation capsule HRB-22 was a test capsule containing advanced Japanese fuel for the High Temperature Test Reactor (HTTR). Its function was to obtain fuel performance data at HTTR operating temperatures in an accelerated irradiation environment. The irradiation was performed in the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL). The capsule was irradiated for 88.8 effective full power days in position RB-3B of the removable beryllium (RB) facility. The maximum fuel compact temperature was maintained at or below the allowable limit of 1300{degrees}C for a majority of the irradiation. This report presents the data collected during the irradiation test. Included are test thermocouple and gas flow data, the calculated maximum and volume average temperatures based on the measured graphite temperatures, measured gaseous fission product activity in the purge gas, and associated release rate-to-birth rate (R/B) results. Also included are quality assurance data obtained during the test.

  4. 40 CFR 265.18 - Location standards.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Location standards. 265.18 Section 265...) INTERIM STATUS STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE TREATMENT, STORAGE, AND DISPOSAL FACILITIES General Facility Standards § 265.18 Location standards. The placement of any hazardous waste in...

  5. Influences of Microwave Irradiation on Environment

    NASA Astrophysics Data System (ADS)

    Murakami, H.; Abe, Y.; Iwata, T.; Kudo, I.; Saito, K.; Okuda, T.

    2004-12-01

    An experimental facility to evaluate the long-duration influence of microwave to environment, a so-called long duration microwave exposure facility (LDMEF), was constructed in Tsukuba in 1994, and so far irradiation tests on plants accumulated over 40,000 hours have been conducted with the aid of 2.45 GHz magnetron. The LDMEF consists of a pair of outdoor electromagnetically isolated areas, one under the influence of microwave irradiation with a 500 W magnetron and one without microwave irradiation. The growth rates of plants in both areas were compared and evaluated with the experimental data for the temperature distribution in the soil and power distribution of microwave. Although any appreciable influence of microwave was not noticed in the power density less than 10 mW/cm2 , the experimental results showed a significant growth rate enhancement when the power density became over 10 mW/cm2 . However, the growth was rather depressed when the power density increased over 15 mW/cm2 . These effects are well explained by the temperature and moisture in the soil which are also under an appreciable influence of microwave irradiation [1,2]. In this context, we newly constructed an indoor irradiation facility, in which the growth conditions of plants under a constant soil temperature can be maintained. In addition, irradiation with a 5.8 GHz magnetron will be conducted in the new facility. In parallel to a series of indoor and outdoor irradiation tests on plants, the influence of microwave irradiation on the growth pattern of albino mouse will be conducted. This experiment will be the first experimental evaluation for the influence of microwave irradiation on animals.

  6. RADIATION FACILITY FOR NUCLEAR REACTORS

    DOEpatents

    Currier, E.L. Jr.; Nicklas, J.H.

    1961-12-12

    A radiation facility is designed for irradiating samples in close proximity to the core of a nuclear reactor. The facility comprises essentially a tubular member extending through the biological shield of the reactor and containing a manipulatable rod having the sample carrier at its inner end, the carrier being longitudinally movable from a position in close proximity to the reactor core to a position between the inner and outer faces of the shield. Shield plugs are provided within the tubular member to prevent direct radiation from the core emanating therethrough. In this device, samples may be inserted or removed during normal operation of the reactor without exposing personnel to direct radiation from the reactor core. A storage chamber is also provided within the radiation facility to contain an irradiated sample during the period of time required to reduce the radioactivity enough to permit removal of the sample for external handling. (AEC)

  7. IRRADIATION FOR POSTHARVEST CONTROL OF QUARANTINE INSECTS

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Interest in the use of irradiation as a phytosanitary treatment for agricultural commodities is growing worldwide, particularly since international IPPC and CODEX standards now endorse and facilitate trade based on this disinfestation method. Irradiation is broadly effective against insects and mite...

  8. Calibration facility safety plan

    NASA Technical Reports Server (NTRS)

    Fastie, W. G.

    1971-01-01

    A set of requirements is presented to insure the highest practical standard of safety for the Apollo 17 Calibration Facility in terms of identifying all critical or catastrophic type hazard areas. Plans for either counteracting or eliminating these areas are presented. All functional operations in calibrating the ultraviolet spectrometer and the testing of its components are described.

  9. Standardization versus Standards.

    ERIC Educational Resources Information Center

    Meier, Deborah

    2002-01-01

    Examines differences between old state-designed norm-referenced tests and new tests aligned with the curriculum. Concludes that new state tests are very similar to old ones. Discusses impact of new high-stakes standardized tests on students and teachers. Argues the new wave of standardized testing is not the answer to improving student…

  10. Disaster Management and Educational Facilities.

    ERIC Educational Resources Information Center

    Kenny, Grace

    2002-01-01

    Summarizes discussions from a seminar focusing on earthquakes and educational facilities, including findings related to educational buildings; partnerships; training; standards, regulations, and procedures; finance and legislation; and research and support. (EV)

  11. Future Long-term Measurements of Solar Spectral Irradiance by JPSS TSIS

    NASA Astrophysics Data System (ADS)

    Richard, E. C.; Harber, D.; Harder, J. W.; Pilewskie, P.; Brown, S.; Smith, A.; Lykke, K.

    2011-12-01

    To advance scientific understanding of how solar variability affects climate processes it is important to maintain accurate, long-term records of solar irradiance. Continuation of solar spectral irradiance (SSI) measurements is needed to characterize poorly understood wavelength-dependent climate processes. Measurement challenges in quantifying the influence of SSI variability on climate are achieving sufficient radiometric absolute accuracy and maintaining the long-term relative accuracy. The Total and Spectral Solar Irradiance Sensor (TSIS) is a dual-instrument package that will acquire solar irradiance as part of the Joint Polar Satellite System (JPSS). The TSIS Spectral Irradiance Monitor (SIM) instrument will continue the SSI measurements that began with the SORCE SIM in 2003. The TSIS SIM incorporates design and calibration improvements to better quantify long-term SSI variability. Specific improvements include the pre-launch SI-traceable calibration, the measurement precision, and the long-term relative stability needed to meet the requirements for establishing a climate record of SSI into the future. To quantify the absolute accuracy over the full spectral range, we have developed a SIM Radiometer Facility (SIMRF) utilizing the NIST Spectral Irradiance and Radiance Responsivity Calibrations using Uniform Sources (SIRCUS). This comprehensive facility includes tuneable laser light sources from the ultraviolet to the near infrared matched in radiant power to the solar spectrum and tied to a cryogenic radiometer traceable to the NIST Primary Optical Watt Radiometer (POWR). The full characterization and calibration follows a measurement equation approach at the unit-level for full validation of the end-to-end performance at the instrument-level to achieve a combined standard uncertainty of 0.25% .

  12. Standards not that standard.

    PubMed

    Vilanova, Cristina; Tanner, Kristie; Dorado-Morales, Pedro; Villaescusa, Paula; Chugani, Divya; Frías, Alba; Segredo, Ernesto; Molero, Xavier; Fritschi, Marco; Morales, Lucas; Ramón, Daniel; Peña, Carlos; Peretó, Juli; Porcar, Manuel

    2015-01-01

    There is a general assent on the key role of standards in Synthetic Biology. In two consecutive letters to this journal, suggestions on the assembly methods for the Registry of standard biological parts have been described. We fully agree with those authors on the need of a more flexible building strategy and we highlight in the present work two major functional challenges standardization efforts have to deal with: the need of both universal and orthogonal behaviors. We provide experimental data that clearly indicate that such engineering requirements should not be taken for granted in Synthetic Biology. PMID:26435739

  13. Facility of Merit Winners, 1997.

    ERIC Educational Resources Information Center

    Schmid, Sue; Sherman, Rachel M.

    1997-01-01

    Presents 10 award-winning college, municipal, and hospital wellness facilities that have been judged to illustrate outstanding standards for quality in planning, design, financing, and operations. Each entry contains photos and information on costs, architectural firms involved, and major facility components. (GR)

  14. PLUMBING FIXTURES FOR EDUCATIONAL FACILITIES.

    ERIC Educational Resources Information Center

    MACCONNELL, JAMES D.; ODELL, WILLIAM R.

    A STUDY OF PLUMBING FIXTURES FOR USE IN EDUCATIONAL FACILITIES WAS MADE TO PROVIDE MANUFACTURERS, ARCHITECTS, AND EDUCATORS WITH A GUIDE TO THE NECESSARY SANITARY FACILITIES REQUIRED FOR--(1) MAINTENANCE OF HEALTH STANDARDS, (2) IMPROVED SUPERVISION, (3) REDUCED MAINTENANCE, AND (4) ENRICHMENT OF THE EDUCATIONAL PROGRAM. THE STUDY IS PRESENTED IN…

  15. Design of YCF-1 mobile γ irradiator

    NASA Astrophysics Data System (ADS)

    Hehu, Zhang; Chuanzhen, Wang

    1993-07-01

    YCF-1 Mobile irradiator is designed by BINE of China. It has been put into running in YanJi city of Jilin province. It is able to be moved to border and distance places and area lumped and spreading out of agricultural products to service. It can play a important role in demonstration and extending irradiation technology in food irradiation, disinfestation, sterilization and quarantine, etc. This paper describes the features and design considerations of mobile irradiator. This irradiator adopted Cesium-137 source. The design capacity of loading source is 9.25PBq (250kCi), A half-time of Cs- 137 is 30.2 years long, exchanging source is not needed utilization rate of energy is higher, and the shielding is thinner, The Weight is lighter, The dose rate on the surface of it is 0.0025mSv/h in accordance with national standard. The internal size of irradiation room is 1800×1800×900mm (L×W×H), The sheilding of irradiation room is a steel shell filled with lead. The thickness of lead is 18cm. The irradiator is installed on a special flat truck. The size of the truck is 7000×3400×4200mm (L×W×H). The weight of irradiator is more than 80 150kw. The main components and parts of irradiator are: source, source racks and hoist, irradiation chamber, storage source chamber, the product's transport system, dose monitoring system, ventilation system and safety interlock system, etc.

  16. 9 CFR 3.50 - Facilities, general.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... WELFARE STANDARDS Specifications for the Humane Handling, Care, Treatment and Transportation of Rabbits... housing facilities for rabbits shall be structurally sound and shall be maintained in good repair,...

  17. Antiradiation Vaccine: Technology Development Of Prophylaxis, Prevention And Treatment Of Biological Consequences And Complications After Neutron Irradiation.

    NASA Astrophysics Data System (ADS)

    Popov, Dmitri; Maliev, Slava; Jones, Jeffrey

    Introduction: Neutrons irradiation produce a unique biological effectiveness compare to different types of radiation because their ability to create a denser trail of ionized atoms in biological living tissues[Straume 1982; Latif et al.2010; Katz 1978; Bogatyrev 1982]. The efficacy of an Anti-Radiation Vaccine for the prophylaxis, prevention and therapy of acute radiation pathology was studied in a neutron exposure facility. The biological effects of fast neutrons include damage of central nervous system and cardiovascular system with development of Acute Cerebrovascular and Cardiovascular forms of acute radiation pathology. After irradiation by high doses of fast neutron, formation of neurotoxins, hematotoxins,cytotoxins forming from cell's or tissue structures. High doses of Neutron Irradiation generate general and specific toxicity, inflammation reactions. Current Acute Medical Management and Methods of Radiation Protection are not effective against moderate and high doses of neutron irradiation. Our experiments demonstrate that Antiradiation Vaccine is the most effective radioprotectant against high doses of neutron-radiation. Radiation Toxins(biological substances with radio-mimetic properties) isolated from central lymph of gamma-irradiated animals could be working substance with specific antigenic properties for vaccination against neutron irradiation. Methods: Antiradiation Vaccine preparation standard - mixture of a toxoid form of Radiation Toxins - include Cerebrovascular RT Neurotoxin, Cardiovascular RT Neurotoxin, Gastrointestinal RT Neurotoxin, Hematopoietic RT Hematotoxin. Radiation Toxins were isolated from the central lymph of gamma-irradiated animals with different forms of Acute Radiation Syndromes - Cerebrovascular, Cardiovascular, Gastrointestinal, Hematopoietic forms. Devices for Y-radiation were "Panorama","Puma". Neutron exposure was accomplished at the Department of Research Institute of Nuclear Physics, Dubna, Russia. The neutrons

  18. Ultraviolet spectral distribution and erythema-weighted irradiance from indoor tanning devices compared with solar radiation exposures.

    PubMed

    Sola, Yolanda; Baeza, David; Gómez, Miguel; Lorente, Jerónimo

    2016-08-01

    Concern regarding the impact of indoor tanning devices on human health has led to different regulations and recommendations, which set limits on erythema-weighted irradiance. Here, we analyze spectral emissions from 52 tanning devices in Spanish facilities and compare them with surface solar irradiance for different solar zenith angles. Whereas most of the devices emitted less UV-B radiation than the midday summer sun, the unweighted UV-A irradiance was 2-6 times higher than solar radiation. Moreover, the spectral distributions of indoor devices were completely different from that of solar radiation, differing in one order of magnitude at some UV-A wavelengths, depending on the lamp characteristics. In 21% of the devices tested, the erythema-weighted irradiance exceeded 0.3Wm(-2): the limit fixed by the European standard and the Spanish regulation. Moreover, 29% of the devices fall within the UV type 4 classification, for which medical advice is required. The high variability in erythema-weighted irradiance results in a wide range of exposure times to reach 1 standard erythemal dose (SED: 100Jm(-2)), with 62% of devices requiring exposures of <10min to reach 1 SED. Nevertheless, the unweighted UV-A dose during this time period would be from 1.4 to 10.3 times more than the solar UV-A dose. PMID:27318601

  19. RCRA FACILITIES

    EPA Science Inventory

    Points represent facilities that are regulated by the EPA under the Resource Conservation and Recovery Act (RCRA). Facilities regulated under RCRA generate, dispose of, treate or transport hazardous waste. RCRA is a law enacted by Congress in 1976 and amended in 1984 to include ...

  20. Total body calcium analysis. [neutron irradiation

    NASA Technical Reports Server (NTRS)

    Lewellen, T. K.; Nelp, W. B.

    1974-01-01

    A technique to quantitate total body calcium in humans is developed. Total body neutron irradiation is utilized to produce argon 37. The radio argon, which diffuses into the blood stream and is excreted through the lungs, is recovered from the exhaled breath and counted inside a proportional detector. Emphasis is placed on: (1) measurement of the rate of excretion of radio argon following total body neutron irradiation; (2) the development of the radio argon collection, purification, and counting systems; and (3) development of a patient irradiation facility using a 14 MeV neutron generator. Results and applications are discussed in detail.