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Sample records for post-irradiation examination facility

  1. 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.

  2. 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

  3. AGC-1 Post Irradiation Examination Status

    SciTech Connect

    David Swank

    2011-09-01

    The Next Generation Nuclear Plant (NGNP) Graphite R&D program is currently measuring irradiated material property changes in several grades of nuclear graphite for predicting their behavior and operating performance within the core of new Very High Temperature Reactor (VHTR) designs. The Advanced Graphite Creep (AGC) experiment consisting of six irradiation capsules will generate this irradiated graphite performance data for NGNP reactor operating conditions. All six AGC capsules in the experiment will be irradiated in the Advanced Test Reactor (ATR), disassembled in the Hot Fuel Examination Facility (HFEF), and examined at the INL Research Center (IRC) or Oak Ridge National Laboratory (ORNL). This is the first in a series of status reports on the progress of the AGC experiment. As the first capsule, AGC1 was irradiated from September 2009 to January 2011 to a maximum dose level of 6-7 dpa. The capsule was removed from ATR and transferred to the HFEF in April 2011 where the capsule was disassembled and test specimens extracted from the capsules. The first irradiated samples from AGC1 were shipped to the IRC in July 2011and initial post irradiation examination (PIE) activities were begun on the first 37 samples received. PIE activities continue for the remainder of the AGC1 specimen as they are received at the IRC.

  4. Post irradiation examination of thermal reactor fuels

    NASA Astrophysics Data System (ADS)

    Sah, D. N.; Viswanathan, U. K.; Ramadasan, E.; Unnikrishnan, K.; Anantharaman, S.

    2008-12-01

    The post irradiation examination (PIE) facility at the Bhabha Atomic Research Centre (BARC) has been in operation for more than three decades. Over these years this facility has been utilized for examination of experimental fuel pins and fuels from commercial power reactors operating in India. In a program to assess the performance of (U,Pu)O 2 MOX fuel prior to its introduction in commercial reactors, three experimental MOX fuel clusters irradiated in the pressurized water loop (PWL) of CIRUS up to burnup of 16 000 MWd/tU were examined. Fission gas release from these pins was measured by puncture test. Some of these fuel pins in the cluster contained controlled porosity pellets, low temperature sintered (LTS) pellets, large grain size pellets and annular pellets. PIE has also been carried out on natural UO 2 fuel bundles from Indian PHWRs, which included two high burnup (˜15 000 MWd/tU) bundles. Salient investigations carried out consisted of visual examination, leak testing, axial gamma scanning, fission gas analysis, microstructural examination of fuel and cladding, β, γ autoradiography of the fuel cross-section and fuel central temperature estimation from restructuring. A ThO 2 fuel bundle irradiated in Kakrapar Atomic Power Station (KAPS) up to a nominal fuel burnup of ˜11 000 MWd/tTh was also examined to evaluate its in-pile performance. The performance of the BWR fuel pins of Tarapur Atomic Power Stations (TAPS) was earlier assessed by carrying out PIE on 18 fuel elements selected from eight fuel assemblies irradiated in the two reactors. The burnup of these fuel elements varied from 5000 to 29 000 MWd/tU. This paper provides a brief review of some of the fuels examined and the results obtained on the performance of natural UO 2, enriched UO 2, MOX, and ThO 2 fuels.

  5. AGR-1 Post Irradiation Examination Final Report

    SciTech Connect

    Demkowicz, Paul Andrew

    2015-08-01

    The post-irradiation examination (PIE) of the Advanced Gas Reactor (AGR)-1 experiment was a multi-year, collaborative effort between Idaho National Laboratory (INL) and Oak Ridge National Laboratory (ORNL) to study the performance of UCO (uranium carbide, uranium oxide) tristructural isotropic (TRISO) coated particle fuel fabricated in the U.S. and irradiated at the Advanced Test Reactor at INL to a peak burnup of 19.6% fissions per initial metal atom. This work involved a broad array of experiments and analyses to evaluate the level of fission product retention by the fuel particles and compacts (both during irradiation and during post-irradiation heating tests to simulate reactor accident conditions), investigate the kernel and coating layer morphology evolution and the causes of coating failure, and explore the migration of fission products through the coating layers. The results have generally confirmed the excellent performance of the AGR-1 fuel, first indicated during the irradiation by the observation of zero TRISO coated particle failures out of 298,000 particles in the experiment. Overall release of fission products was determined by PIE to have been relatively low during the irradiation. A significant finding was the extremely low levels of cesium released through intact coatings. This was true both during the irradiation and during post-irradiation heating tests to temperatures as high as 1800°C. Post-irradiation safety test fuel performance was generally excellent. Silver release from the particles and compacts during irradiation was often very high. Extensive microanalysis of fuel particles was performed after irradiation and after high-temperature safety testing. The results of particle microanalysis indicate that the UCO fuel is effective at controlling the oxygen partial pressure within the particle and limiting kernel migration. Post-irradiation examination has provided the final body of data that speaks to the quality of the AGR-1 fuel, building

  6. US RERTR FUEL DEVELOPMENT POST IRRADIATION EXAMINATION RESULTS

    SciTech Connect

    A. B. Robinson; D. M. Wachs; D. E. Burkes; D. D. Keiser

    2008-10-01

    Post irradiation examinations of irradiated RERTR plate type fuel at the Idaho National Laboratory have led to in depth characterization of fuel behavior and performance. Both destructive and non-destructive examination capabilities at the Hot Fuels Examination Facility (HFEF) as well as recent results obtained are discussed herein. New equipment as well as more advanced techniques are also being developed to further advance the investigation into the performance of the high density U-Mo fuel.

  7. Advanced Post-Irradiation Examination Capabilities Alternatives Analysis Report

    SciTech Connect

    Jeff Bryan; Bill Landman; Porter Hill

    2012-12-01

    An alternatives analysis was performed for the Advanced Post-Irradiation Capabilities (APIEC) project in accordance with the U.S. Department of Energy (DOE) Order DOE O 413.3B, “Program and Project Management for the Acquisition of Capital Assets”. The Alternatives Analysis considered six major alternatives: ? No Action ? Modify Existing DOE Facilities – capabilities distributed among multiple locations ? Modify Existing DOE Facilities – capabilities consolidated at a few locations ? Construct New Facility ? Commercial Partnership ? International Partnerships Based on the alternatives analysis documented herein, it is recommended to DOE that the advanced post-irradiation examination capabilities be provided by a new facility constructed at the Materials and Fuels Complex at the Idaho National Laboratory.

  8. 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

  9. Post irradiation examination of the Spallation Neutron Source target vessels

    SciTech Connect

    McClintock, David A; Ferguson, Phillip D; Mansur, Louis K

    2010-01-01

    The Spallation Neutron Source (SNS) at Oak Ridge National Laboratory is an accelerator-based pulsed neutron source that produces high-energy spallation neutrons by bombarding liquid mercury flowing through a stainless steel target vessel. During operation the proton beam and spallation neutrons produce radiation damage in the AISI 316L austenitic stainless steel target vessel and water-cooled shroud. The beam pulses also cause rapid heating of the liquid mercury, which may produce cavitation erosion damage on the inner surface of the target vessel. The cavitation erosion rate is thought to be highly sensitive to beam power and predicted to be the primary life-limiting factor of target vessel. Though mitigation of cavitation erosion and radiation damage to the target vessel will be a critical for successful high-power operation of the SNS facility, the effects of radiation damage and cavitation erosion to target vessels in liquid metal spallation systems are not well known. Therefore preparations are being undertaken to perform post irradiation examination (PIE) of the liquid mercury target vessel and water-cooled shroud after end-of-life occurs. An overview of the planned PIE for the SNS target vessel is presented here, including proposed techniques for specimen acquisition and subsequent material properties characterization.

  10. RERTR-12 Post-irradiation Examination Summary Report

    SciTech Connect

    Rice, Francine; Williams, Walter; Robinson, Adam; Harp, Jason; Meyer, Mitch; Rabin, Barry

    2015-02-01

    The following report contains the results and conclusions for the post irradiation examinations performed on RERTR-12 Insertion 2 experiment plates. These exams include eddy-current testing to measure oxide growth; neutron radiography for evaluating the condition of the fuel prior to sectioning and determination of fuel relocation and geometry changes; gamma scanning to provide relative measurements for burnup and indication of fuel- and fission-product relocation; profilometry to measure dimensional changes of the fuel plate; analytical chemistry to benchmark the physics burnup calculations; metallography to examine the microstructural changes in the fuel, interlayer and cladding; and microhardness testing to determine the material-property changes of the fuel and cladding.

  11. Progress In Developing Laser Based Post Irradiation Examination Infrastructure

    SciTech Connect

    Smith, James A.; Scott, Clark L.; Benefiel, Brad C.

    2016-09-01

    To be able to understand the performance of reactor fuels and materials, irradiated materials must be characterized effectively and efficiently in a high rad environment. The characterization work must be performed remotely and in an environment hostile to instrumentation. Laser based characterization techniques provide the ability to be remote and robust in a hot-cell environment. Laser based instrumentation also can provide high spatial resolution suitable for scanning and imaging large areas. The INL is currently developing three laser based Post Irradiation Examination (PIE) stations for the Hot Fuel Examination Facility at the INL. These laser based systems will characterize irradiated materials and fuels. The characterization systems are the following: Laser Shock Laser based ultrasonic C-scan system Gas Assay, Sample, and Recharge system (GASR, up-grade to an existing system). The laser shock technique will characterize material properties and failure loads/mechanisms in various materials such as LWR fuel, plate fuel, and next generation fuel forms, for PIE in high radiation areas. The laser shock-technique induces large amplitude shock waves to mechanically characterize interfaces such as the fuel-clad bond. The shock wave travels as a compression wave through the material to the free (unconfined) back surface and reflects back through the material under test as a rarefaction (tensile) wave. This rarefaction wave is the physical mechanism that produces internal de-lamination failure. As part of the laser shock system, a laser-based ultrasonic C-scan system will be used to detect and characterize debonding caused by the laser shock technique. The laser ultrasonic system will be fully capable of performing classical non-destructive evaluation testing and imaging functions such as microstructure characterization, flaw detection and dimensional metrology in complex components. The purpose of the GASR is to measure the pressure/volume of the plenum of an

  12. NET-1.2 post-irradiation examination report

    SciTech Connect

    Rightley, M.; Ales, M.; Bourcier, S.

    1997-06-01

    The post-irradiation examination (PIE) of the NET-1.2 fuel element was completed in December, 1993. The goal of the PIE work was to gather data regarding the fracture of the hot frit during the experiment. Five cracks were observed in the hot frit at various locations although only two were believed to have initiated the overall component failure. These two cracks were complete circumferential failures and were located near the open and closed ends of the frit within the active flow region. The location and orientation of these fractures suggested that failure was the result of thermally-induced stresses that exceeded pre-test predictions. The cause of the failure was the temperature difference between the coolant flowing through the hot frit and the thermally massive end fittings. The resulting axial temperature gradients in the hot frit imposed thermal stresses that exceeded failure in the frit coating material. This coating fracture then propagated through the graphite substrate. Post-test analyses of the frit response based on measured data from the experiment verified that the frit coating failure stresses were exceeded. Additionally, the cold frit behaved unexpectedly. The PIE inspection of this component showed that a majority of the compliant panels were permanently deformed against the cold frit inner wall even though the transients that the bed was exposed to were not thought to be capable of creating this magnitude of bed expansion. No evidence of bed locking was observed. A calculational error in the prediction of the total bed expansion was found (post-PIE) which certainly contributed to the underestimation of the bed displacement. Additionally, temperature differences between the bulk of the frit and the panels created a bowing force which may have allowed some amount of bed settling at relatively low temperatures while particle thermal expansion was minimal.

  13. Nondestructive post-irradiation examination of Loop-1, S1 and B1 rods

    SciTech Connect

    Bratton, R.L.

    1997-05-01

    As a part of the Pacific Northwest National Laboratory`s Tritium Target Development Program, eleven tritium target rods were irradiated in the Advanced Test Reactor located at the Idaho National Engineering and Environmental Laboratory during 1991. Both nondestructive and destructive post-irradiation examination on all eleven rods was planned under the Tritium Target Development Program. Funding for the program was reduced in 1991 resulting in the early removal of the program experiments before reaching their irradiation goals. Post-irradiation examination was only performed on one of the irradiated rods at the Pacific Northwest National Laboratory before the program was terminated in 1992. On December 6, 1995, the Secretary of Energy announced the pursuit of the Commercial Light-Water Reactor option for producing tritium establishing the Tritium Target Qualification Program at the Pacific Northwest National Laboratory. This program decided to pursue nondestructive and destructive post-irradiation examination of the ten remaining rods from the previous program. The ten rods comprise three experiments. The Loop-1 experiment irradiated eight target rods in a loop configuration for 217 irradiation days. The other two rods were irradiated in two separate irradiation experiments, designated as S1 and B1 for 143 effective full-power days, but at different power levels. After the ten rods were transferred from the ATR Canal to the Hot Fuels Examination Facility, the following examinations were performed: (1) visual examination and photography; (2) neutron radiography; (3) axial gamma scanning; (4) contact profilometry measurement; (5) bow and length measurements; (6) rod puncture and plenum gas analysis/measurement of plenum gas quantity; (7) void volume determination; and (8) internal pressure determination. This report presents the data collected during these examinations.

  14. Post-Irradiation Examination of Array Targets - Part I

    SciTech Connect

    Icenhour, A.S.

    2004-01-23

    During FY 2001, two arrays, each containing seven neptunium-loaded targets, were irradiated at the Advanced Test Reactor in Idaho to examine the influence of multi-target self-shielding on {sup 236}Pu content and to evaluate fission product release data. One array consisted of seven targets that contained 10 vol% NpO{sub 2} pellets, while the other array consisted of seven targets that contained 20 vol % NpO{sub 2} pellets. The arrays were located in the same irradiation facility but were axially separated to minimize the influence of one array on the other. Each target also contained a dosimeter package, which consisted of a small NpO{sub 2} wire that was inside a vanadium container. After completion of irradiation and shipment back to the Oak Ridge National Laboratory, nine of the targets (four from the 10 vol% array and five from the 20 vol% array) were punctured for pressure measurement and measurement of {sup 85}Kr. These nine targets and the associated dosimeters were then chemically processed to measure the residual neptunium, total plutonium production, {sup 238}Pu production, and {sup 236}Pu concentration at discharge. The amount and isotopic composition of fission products were also measured. This report provides the results of the processing and analysis of the nine targets.

  15. Nuclear fuel post-irradiation examination equipment package

    SciTech Connect

    DeCooman, W.J.; Spellman, D.J.

    2007-07-01

    Hot cell capabilities in the U.S. are being reviewed and revived to meet today's demand for fuel reliability, tomorrow's demands for higher burnup fuel and future demand for fuel recycling. Fuel reliability, zero tolerance for failure, is more than an industry buzz. It is becoming a requirement to meet the rapidly escalating demands for the impending renaissance of nuclear power generation, fuel development, and management of new waste forms that will need to be dealt with from programs such as the Global Nuclear Energy Partnership (GNEP). Fuel performance data is required to license fuel for higher burnup; to verify recycled fuel performance, such as MOX, for wide-scale use in commercial reactors; and, possibly, to license fuel for a new generation of fast reactors. Additionally, fuel isotopic analysis and recycling technologies will be critical factors in the goal to eventually close the fuel cycle. This focus on fuel reliability coupled with the renewed interest in recycling puts a major spotlight on existing hot cell capabilities in the U.S. and their ability to provide the baseline analysis to achieve a closed fuel cycle. Hot cell examination equipment is necessary to determine the characteristics and performance of irradiated materials that are subjected to nuclear reactor environments. The equipment within the hot cells is typically operated via master-slave manipulators and is typically manually operated. The Oak Ridge National Laboratory is modernizing their hot cell nuclear fuel examination equipment, installing automated examination equipment and data gathering capabilities. Currently, the equipment has the capability to perform fuel rod visual examinations, length and diametrical measurements, eddy current examination, profilometry, gamma scanning, fission gas collection and void fraction measurement, and fuel rod segmentation. The used fuel postirradiation examination equipment was designed to examine full-length fuel rods for both Boiling Water

  16. Post-irradiation examination of capsule P13T

    SciTech Connect

    Scheffel, W.J.

    1981-08-01

    Postirradiation examination revealed excellent performance of the H-451 and TS-1240 graphite bodies and fuel rods irraidated to a peak fluence of 8.0 x 10/sup 25/ n/m/sup 2/ (E > 29 fJ)/sub HTGR/ and to a peak volume-average fuel rod temperature of 1215/sup 0/C. A range of fuel rod variables was tested matrix filler graphite, shim particles, compositions; no variable was detrimental to the rod integrity. Particle batches with coating designs representative of the LHTGR (Large HTGR) design requirements exhibited fair irradiation performance to full fast neutron exposure ((8.0 x 10/sup 25/ n/m/sup 2/) (E > 29 fJ)/sub HTGR/) and burnups of 75%. True in-service particle failures were concluded to be <0.3% for all P13T particles. The observed failure was attributed to the outer pyrolytic carbons (OPyC) layer. The failure fraction for 32 P13T fuel rods are greater than predicted, but the mean observed value is less than predicted up to fast fluences of approx. 6.0 x 10/sup 25/ n/m/sup 2/ (E > 29 fJ)/sub HTGT/ at 50% confidence. Incipient degradation of the SiC coating due to palladium attack was observed in the HEU UC/sub 2/-TRISO and the UCO (oxygen/uranium ratio (O/U) = 0.64) fuel rods.

  17. Post irradiation examination of tight fit garter springs from Indian PHWR

    NASA Astrophysics Data System (ADS)

    Dubey, J. S.; Shriwastaw, R. S.; Kumar, Ashwini; Shah, Priti Kotak; Rath, B. N.; Kumar, Sunil; Mishra, Prerna; Alur, V. D.; Mallik, G. K.; Anantharaman, S.

    2015-07-01

    Garter springs play an important role in maintaining the annulus gap between hot pressure tubes and cold calandria tubes of PHWRs. Post irradiation examination (PIE) was carried out on the garter springs removed from Indian PHWR after around 8 and 15 Hot Operating Years (HOY). PIE studies included visual examination, dimensional measurements, metallographic examination and relevant mechanical tests. The girdle wires of these garter springs were also examined and subjected to the tension and bend tests. This paper gives the results of the PIE investigations and discusses its relevance for continued performance of garter springs in PHWRs.

  18. An Assessment of ORNL PIE Capabilities for the AGR Program Capsule Post Irradiation Examination

    SciTech Connect

    Morris, Robert Noel

    2006-09-01

    ORNL has facilities and experienced staff that can execute +the Advanced Gas Reactor (AGR) Post Irradiation Examination (PIE) task. While the specific PIE breakdown needs to be more formally defined, the basic outline is clear and the existing capabilities can be assessed within the needs of the tasks defined in the program plan. A one-to-one correspondence between the program plan tasks and the current ORNL PIE status was conducted and while some shortcomings were identified, the general capability is available. Specific upgrade needs were identified and reviewed. A path forward was formulated. Building 3525 is available for this work and this building is currently receiving renewed attention from management so that it will be in good working order prior to the expected PIE start date. This building is equipped with the tools necessary for PIEs of this nature, but the long hiatus in coated particle fuel work has left it with aging analysis tools. This report identified several of these tools and rough estimates of what would be required to update and replace them. In addition, other ORNL buildings are available to support Building 3525 in specialized tasks along with the normal laboratory infrastructure. Before the AGR management embarks on any equipment development effort, the PIE tasks should be updated against current program (modeling and data) needs and better defined so that the items to be measured, their measurement uncertainties, and thru-put needs can be reviewed. A Data Task Matrix (DTM) should be prepared so that the program data needs can be compared against the identified PIE tasks and what is practical in the hot cell environment to make sure nothing is overlooked. Finally, thought should be given to the development of standardized equipment designs between sites to avoid redundant design efforts and different measurement techniques. This is a potentially cost saving effort that can also avoid data inconsistencies.

  19. Simple SE Methods Deployed in Revitalizing the Nuclear Post- Irradiation Examination Capability for the Idaho National Laboratory

    SciTech Connect

    Larry R. Zirker; R. Douglas Hamelin; Lori Braase

    2010-07-01

    The “crown jewels” of nuclear energy research facilities (i.e., hot cells, analysis systems, and scientists) have been centered at the Idaho National Laboratory for over 40 years, but in recent years, emphasis and funding for nuclear fuel research and development have declined to adversely affect the readiness and effectiveness of research facilities and equipment. Conversely, the current national nuclear renaissance forces the need for immediate enhancements in facilities, equipment, capabilities, and staff for the post-irradiation examination (PIE) of nuclear fuel. PIE characterizes the “burn-up” and structural integrity of fuel elements and defines the effectiveness of new fuels/alloys in search for optimum fuel burn-up and alloys for current and next generation nuclear reactors. This paper details how a team of system engineers adapted simple system engineering tools and techniques for a customer unfamiliar with the power and effectiveness of system engineering, to achieve project success.

  20. Post Irradiation Examination for Advanced Materials at Burnups Exceeding the Current Limit

    SciTech Connect

    John H. Strumpell

    2004-12-31

    Permitting fuel to be irradiated to higher burnups limits can reduce the amount of spent nuclear fuel (SNF) requiring storage and/or disposal and enable plants to operate with longer more economical cycle lengths and/or at higher power levels. Therefore, Framatome ANP (FANP) and the B&W Owner's Group (BWOG) have introduced a new fuel rod design with an advanced M5 cladding material and have irradiated several test fuel rods through four cycles. The U.S. Department of Energy (DOE) joined FANP and the BWOG in supporting this project during its final phase of collecting and evaluating high burnup data through post irradiation examination (PIE).

  1. KEY RESULTS FROM IRRADIATION AND POST-IRRADIATION EXAMINATION OF AGR-1 UCO TRISO FUEL

    SciTech Connect

    Demkowicz, Paul A.; Hunn, John D.; Petti, David A.; Morris, Robert N.

    2016-11-01

    The AGR-1 irradiation experiment was performed as the first test of tristructural isotropic (TRISO) fuel in the US Advanced Gas Reactor Fuel Development and Qualification Program. The experiment consisted of 72 right cylinder fuel compacts containing approximately 3×105 coated fuel particles with uranium oxide/uranium carbide (UCO) fuel kernels. The fuel was irradiated in the Advanced Test Reactor for a total of 620 effective full power days. Fuel burnup ranged from 11.3 to 19.6% fissions per initial metal atom and time average, volume average irradiation temperatures of the individual compacts ranged from 955 to 1136°C. This paper focuses on key results from the irradiation and post-irradiation examination, which revealed a robust fuel with excellent performance characteristics under the conditions tested and have significantly improved the understanding of UCO coated particle fuel irradiation behavior within the US program. The fuel exhibited a very low incidence of TRISO coating failure during irradiation and post-irradiation safety testing at temperatures up to 1800°C. Advanced PIE methods have allowed particles with SiC coating failure to be isolated and meticulously examined, which has elucidated the specific causes of SiC failure in these specimens. The level of fission product release from the fuel during irradiation and post-irradiation safety testing has been studied in detail. Results indicated very low release of krypton and cesium through intact SiC and modest release of europium and strontium, while also confirming the potential for significant silver release through the coatings depending on irradiation conditions. Focused study of fission products within the coating layers of irradiated particles down to nanometer length scales has provided new insights into fission product transport through the coating layers and the role various fission products may have on coating integrity. The broader implications of these results and the application of

  2. Detailed Destructive Post-Irradiation Examinations of Mixed Uranium and Plutonium Oxide Fuel

    SciTech Connect

    Delashmitt, Jeffrey {Jeff} S; Keever, Tamara {Tammy} Jo; Smith, Rob R; Hexel, Cole R; Ilgner, Ralph H

    2010-01-01

    The United States Department of Energy (DOE) Fissile Materials Disposition Program (FMDP) is pursuing disposal of surplus weapons-usable plutonium by reactor irradiation as the fissile constituent of MOX fuel. Lead test assemblies (LTAs) have been irradiated for approximately 36 months in Duke Energy's Catawba-1 nuclear power plant (NPP). Per the mixed oxide (MOX) fuel topical report, approved by the U.S. Nuclear Regulatory Commission (NRC), destructive post-irradiation examinations (PIEs) are to be performed on second cycle rods (irradiated to an average burnup of approximately 45 GWd/MTHM). The Radiochemical Analysis Group (RAG) at Oak Ridge National Laboratory (ORNL) is currently performing the detailed destructive post-irradiation examinations (PIE) on four of the mixed uranium and plutonium oxide fuel rods. The analytical process involves dissolution of designated fuel segments in a shielded hot cell for high precision quantification of select fission products and actinide isotopes employing isotope dilution mass spectrometry (IDMS) among other analyses. The hot cell dissolution protocol to include the collection and subsequent alkaline fusion digestion of the fuel's acid resistant metallic particulates will be presented. Although the IDMS measurements of the fission products and actinide isotopes will not be completed by the time of the 51st INMM meeting, the setup and testing of the HPLC chromatographic separations in preparation for these measurements will be discussed.

  3. AGR-1 Compact 5-3-1 Post-Irradiation Examination Results

    SciTech Connect

    Paul Demkowicz; Jason Harp; Phil Winston; Scott A. Ploger

    2016-12-01

    The Advanced Gas Reactor (AGR) Fuel Development and Qualification Program was established to perform the requisite research and development on tristructural isotropic (TRISO) coated particle fuel to support deployment of a high-temperature gas-cooled reactor (HTGR). The work continues as part of the Advanced Reactor Technologies (ART) TRISO Fuel program. The overarching program goal is to provide a baseline fuel qualification data set to support licensing and operation of an HTGR. To achieve these goals, the program includes the elements of fuel fabrication, irradiation, post-irradiation examination (PIE) and safety testing, fuel performance, and fission product transport (INL 2015). A series of fuel irradiation experiments is being planned and conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). These experiments will provide data on fuel performance under irradiation, support fuel process development, qualify the fuel for normal operating conditions, provide irradiated fuel for safety testing, and support the development of fuel performance and fission product transport models. The first of these irradiation tests, designated AGR-1, began in the ATR in December 2006 and ended in November 2009. This experiment was conducted primarily to act as a shakedown test of the multicapsule test train design and provide early data on fuel performance for use in fuel fabrication process development. It also provided samples for post-irradiation safety testing, where fission product retention of the fuel at high temperatures will be experimentally measured. The capsule design and details of the AGR-1 experiment have been presented previously.

  4. Summary of Post Irradiation Examination Results of the AFIP-6 Failure

    SciTech Connect

    Adam Robinson; Daniel M. Wachs; Francine Rice; Danielle Perez

    2011-10-01

    The AFIP-6 test assembly was irradiated for one cycle in the Advanced Test Reactor at Idaho National Laboratory. The experiment was designed to test two monolithic fuel plates at power and burn-ups which bounded the operating conditions of both ATR and HFIR driver fuel. Both plates contain a solid U-Mo fuel foil with a zirconium diffusion barrier between 6061-aluminum cladding plates bonded by hot isostatic pressing. The experiment was designed with an orifice to restrict the coolant flow in order to obtain prototypic coolant temperature conditions. While these coolant temperatures were obtained, flow restriction resulted in low heat transfer coefficients and the failure of the fuel plates. The results from the post irradiation examinations and some observations of the failure mechanisms are outlined herein.

  5. AGR-1 Compact 1-3-1 Post-Irradiation Examination Results

    SciTech Connect

    Demkowicz, Paul Andrew

    2016-12-01

    The Advanced Gas Reactor (AGR) Fuel Development and Qualification Program was established to perform the requisite research and development on tristructural isotropic (TRISO) coated particle fuel to support deployment of a high-temperature gas-cooled reactor (HTGR). The work continues as part of the Advanced Reactor Technologies (ART) TRISO Fuel program. The overarching program goal is to provide a baseline fuel qualification data set to support licensing and operation of an HTGR. To achieve these goals, the program includes the elements of fuel fabrication, irradiation, post-irradiation examination (PIE) and safety testing, fuel performance modeling, and fission product transport (INL 2015). A series of fuel irradiation experiments is being planned and conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). These experiments will provide data on fuel performance under irradiation, support fuel process development, qualify the fuel for normal operating conditions, provide irradiated fuel for safety testing, and support the development of fuel performance and fission product transport models. The first of these irradiation tests, designated AGR-1, began in the ATR in December 2006 and ended in November 2009. This experiment was conducted primarily to act as a shakedown test of the multicapsule test train design and provide early data on fuel performance for use in fuel fabrication process development. It also provided samples for post-irradiation safety testing, where fission product retention of the fuel at high temperatures will be experimentally measured. The capsule design and details of the AGR-1 experiment have been presented previously (Grover, Petti, and Maki 2010, Maki 2009).

  6. METAPHIX-1 non destructive post irradiation examinations in the irradiated elements cell at Phenix

    SciTech Connect

    Breton, Laurent; Masson, M.; Garces, E.; Desjardins, S.; Fontaine, B.; Lacroix, B.; Martella, T.; Loubet, L.; Ohta, H.; Yokoo, T.; Ougier, M.; Glatz, J.P.

    2007-07-01

    Central Research Institute of Electric Power Industry (CRIEPI) has been developing minor actinide (MA) transmutation technology in homogeneous loading mode by use of metal fuel fast reactors in cooperation with Institute for Transuranium Elements (ITU) and Commissariat a l'Energie Atomique (CEA). Fast reactor metal fuel pins of Uranium- Plutonium-Zirconium (U-Pu-Zr) alloy containing 2 wt% MAs and 2 wt% rare earth elements (REs), 5 wt% MAs, and 5 wt% MAs and 5 wt% REs were irradiated in the PHENIX French fast reactor as METAPHIX experiments. In these METAPHIX experiments, three rigs each consisting of three metal fuel experimental pins and sixteen oxide fuel driver pins were irradiated. The target burnup of the three rigs is 2.4 at%, 7 at% and 11 at% which corresponds to 120, 360 and 600 equivalent full power days (EFPD) in terms of irradiation periods, respectively. The low burnup rig of 2.4 at%, METAPHIX-1, was discharged from the core in August 2004. After cooling, the non-destructive post irradiation examinations (PIEs) of the rig (visual examination, measurement of rig length and deformation) and of the metal fuel pins (visual examination, measurement of pin length and deformation, {gamma}-spectrometry and neutron radiography) were conducted in the Irradiated Elements Cell (IEC) at PHENIX. (authors)

  7. Post-irradiation Examination of the AGR-1 Experiment: Plans and Preliminary Results

    SciTech Connect

    Paul Demkowicz

    2001-10-01

    Abstract – The AGR-1 irradiation experiment contains seventy-two individual cylindrical fuel compacts (25 mm long x 12.5 mm diameter) each containing approximately 4100 TRISO-coated uranium oxycarbide fuel particles. The experiment accumulated 620 effective full power days in the Advanced Test Reactor at the Idaho National Laboratory with peak burnups exceeding 19% FIMA. An extensive post-irradiation examination campaign will be performed on the AGR-1 fuel in order to characterize the irradiated fuel properties, assess the in-pile fuel performance in terms of coating integrity and fission metals release, and determine the fission product retention behavior during high temperature accident testing. PIE experiments will include dimensional measurements of fuel and irradiated graphite, burnup measurements, assessment of fission metals release during irradiation, evaluation of coating integrity using the leach-burn-leach technique, microscopic examination of kernel and coating microstructures, and accident testing of the fuel in helium at temperatures up to 1800°C. Activities completed to date include opening of the irradiated capsules, measurement of fuel dimensions, and gamma spectrometry of selected fuel compacts.

  8. Irradiation and post-irradiation examination of uranium-free nitride fuel

    NASA Astrophysics Data System (ADS)

    Hania, P. R.; Klaassen, F. C.; Wernli, B.; Streit, M.; Restani, R.; Ingold, F.; Fedorov, A. V.; Wallenius, J.

    2015-11-01

    Two identical Phénix-type 15-15Ti steel pinlets each containing a 70 mm Pu0.3Zr0.7N fuel stack in a 1-bar helium atmosphere have been irradiated in the HFR Petten at medium high linear power (46-47 kW/m at BOL) and an average cladding temperature of 505 °C. The pins were irradiated to a plutonium burn-up of 9.7% (88 MWd/kgHM) in 170 full power days. Both pins remained fully intact. Post-irradiation examination performed at NRG and PSI showed that the overall swelling rate of the fuel was 0.92 vol-%/%FIHMA. Fission gas release was 5-6%, while helium release was larger than 50%. No fuel restructuring was observed, and only mild cracking. EPMA measurements show a burn-up increase toward the pellet edge of up to 4 times. All investigated fission products except to some extent the noble metals were found to be evenly distributed over the matrix, indicating good solubility. Local formation of a secondary phase with high Pu content and hardly any Zr was observed. A general conclusion of this investigation is that ZrN is a suitable inert matrix for burning plutonium at high destruction rates.

  9. Post irradiation examination of irradiated americium oxide and uranium dioxide in magnesium aluminate spinel

    NASA Astrophysics Data System (ADS)

    Klaassen, F. C.; Bakker, K.; Schram, R. P. C.; Klein Meulekamp, R.; Conrad, R.; Somers, J.; Konings, R. J. M.

    2003-06-01

    To study MgAl 2O 4 spinel as inert matrix material for the transmutation of minor actinides, two capsules were irradiated at the high flux reactor in Petten, containing 12.5 wt% micro-dispersed 241AmO x in spinel and 25 wt% micro-dispersed enriched UO 2 in spinel. During irradiation, the initially present 241Am was converted for 99.8% to fission products (50%), plutonium (30%), curium (16%) and 243Am (4%). The UO 2 spinel target experienced a burn-up of 32% fission per initial metal atom. The post irradiation examination of the AmO x inert matrix target showed swelling of 27 vol.%, and a gas release of 48% for He and 16% for Xe and Kr. The UO 2 inert matrix target also showed a large volumetric swelling of 11%, directed mainly radially. Ceramography on the UO 2 inert matrix target revealed a complete restructuring of the spinel grains upon irradiation and the absence of porosity, suggesting that amorphisation is the main cause of the swelling.

  10. Status of Post Irradiation Examination of FCAB and FCAT Irradiation Capsules

    SciTech Connect

    Field, Kevin G.; Yamamoto, Yukinori; Howard, Richard H.

    2016-09-29

    A series of irradiation programs are ongoing to address the need for determining the radiation tolerance of FeCrAl alloys. These irradiation programs, deemed the FCAT and FCAB irradiation programs, use the High Flux Isotope Reactor (HFIR) to irradiate second generation wrought FeCrAl alloys and early-generation powder-metallurgy (PM) oxide dispersion-strengthened (ODS) FeCrAl alloys. Irradiations have been or are being performed at temperatures of 200°C, 330°C, and 550°C from doses of 1.8 dpa up to 16 dpa. Preliminary post-irradiation examination (PIE) on low dose (<2 dpa) irradiation capsules of tensile specimens has been performed. Analysis of co-irradiated SiC thermometry have shown reasonable matching between the nominal irradiation temperatures and the target irradiation temperatures. Room temperature tensile tests have shown typical radiation-induced hardening and embrittlement at irradiations of 200°C and 330°C, but a propensity for softening when irradiated to 550°C for the wrought alloys. The PM-ODS FeCrAl specimens showed less hardening compared to the wrought alloys. Future PIE includes high temperature tensile tests on the low dose irradiation capsules as well as the determination of reference fracture toughness transition temperature, To, in alloys irradiated to 7 dpa and higher.

  11. Post-irradiation examination of the Spallation Neutron Source target module

    NASA Astrophysics Data System (ADS)

    McClintock, D. A.; Ferguson, P. D.; Mansur, L. K.

    2010-03-01

    The Spallation Neutron Source (SNS) at Oak Ridge National Laboratory is an accelerator-based pulsed neutron source that produces high-energy spallation neutrons by bombarding liquid mercury flowing through a stainless steel target vessel. During operation the proton beam and spallation neutrons produce radiation damage in the AISI 316L austenitic stainless steel target vessel and water-cooled shroud. The beam pulses also cause rapid heating of the liquid mercury, which may produce cavitation erosion damage on the inner surface of the target vessel. The cavitation erosion rate is thought to be highly sensitive to beam power and predicted to be the primary life-limiting factor of the target module. Though cavitation erosion and radiation damage to the target vessel are expected to dictate its lifetime, the effects of radiation damage and cavitation erosion to target vessels in liquid metal spallation systems are not well known. Therefore preparations are being undertaken to perform post-irradiation examination (PIE) of the liquid mercury target vessel and water-cooled shroud after end-of-life occurs. An overview of the planned PIE for the SNS target vessel is presented here, including proposed techniques for specimen acquisition and subsequent material properties characterization.

  12. Iterative ct reconstruction from few projections for the nondestructive post irradiation examination of nuclear fuel assemblies

    NASA Astrophysics Data System (ADS)

    Abir, Muhammad Imran Khan

    The core components (e.g. fuel assemblies, spacer grids, control rods) of the nuclear reactors encounter harsh environment due to high temperature, physical stress, and a tremendous level of radiation. The integrity of these elements is crucial for safe operation of the nuclear power plants. The Post Irradiation Examination (PIE) can reveal information about the integrity of the elements during normal operations and off?normal events. Computed tomography (CT) is a tool for evaluating the structural integrity of elements non-destructively. CT requires many projections to be acquired from different view angles after which a mathematical algorithm is adopted for reconstruction. Obtaining many projections is laborious and expensive in nuclear industries. Reconstructions from a small number of projections are explored to achieve faster and cost-efficient PIE. Classical reconstruction algorithms (e.g. filtered back projection) cannot offer stable reconstructions from few projections and create severe streaking artifacts. In this thesis, conventional algorithms are reviewed, and new algorithms are developed for reconstructions of the nuclear fuel assemblies using few projections. CT reconstruction from few projections falls into two categories: the sparse-view CT and the limited-angle CT or tomosynthesis. Iterative reconstruction algorithms are developed for both cases in the field of compressed sensing (CS). The performance of the algorithms is assessed using simulated projections and validated through real projections. The thesis also describes the systematic strategy towards establishing the conditions of reconstructions and finds the optimal imaging parameters for reconstructions of the fuel assemblies from few projections.

  13. Post-irradiation Examination and Fission Product Inventory Analysis of AGR-1 Irradiation Capsules

    SciTech Connect

    J M Harp; P D Demkowicz; S A Ploger

    2012-10-01

    The AGR-1 experiment was the first in a series of Advanced Gas Reactor (AGR) experiments designed to test TRISO fuel under High Temperature Gas Reactor irradiation conditions. This experiment was irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) and is currently undergoing post-irradiation examination (PIE) at INL’s Materials and Fuels Complex (MFC). The inventory and distribution of fission products, especially Ag-110m, was assessed and analyzed for all the components of the AGR-1 capsules. This data should help inform the study of fission product migration in coated particle fuel. Gamma spectrometry was used to measure the activity of various different fission products in the different components of the AGR-1 test train. Each capsule contained: 12 fuel compacts, a graphite holder that kept the fuel compacts in place, graphite spacers that were above and below the graphite holders and fuel compacts, gas lines through which a helium neon gas mixture flowed in and out of each capsule, and the stainless steel shell that contained the experiment. Gamma spectrometry results and the experimental techniques used to capture these results will be presented for all the capsule components. The components were assayed to determine the total activity of different fission products present in or on them. These totals are compared to the total expected activity of a particular fission product in the capsule based on predictions from physics simulation. Based on this metric, a significant fraction of the Ag-110m was detected outside the fuel compacts, but the amount varied highly between the 6 capsules. Very small fractions of Cs-137 (<2E-5), Cs-134 (<1e-5), and Eu-154 (<4e-4) were detected outside of the fuel compacts. Additionally, the distribution of select fission products in some of the components including the fuel compacts and the graphite holders were measured and will be discussed.

  14. AGR-1 Fuel Compact 6-3-2 Post-Irradiation Examination Results

    SciTech Connect

    Paul demkowicz; jason Harp; Scott Ploger

    2012-12-01

    Destructive post-irradiation examination was performed on fuel Compact 6-3-2, which was irradiated in the AGR-1 experiment to a final compact average burnup of 11.3% FIMA and a time-average, volume-average temperature of 1070°C. The analysis of this compact was focused on characterizing the extent of fission product release from the particles and examining particles to determine the condition of the kernels and coating layers. The work included deconsolidation of the compact and leach-burn-leach analysis, visual inspection and gamma counting of individual particles, measurement of fuel burnup by several methods, metallurgical preparation of selected particles, and examination of particle cross-sections with optical microscopy. A single particle with a defective SiC layer was identified during deconsolidation-leach-burn-leach analysis, which is in agreement with previous measurements showing elevated cesium in the Capsule 6 graphite fuel holder associated with this fuel compact. The fraction of the compact europium inventory released from the particles and retained in the matrix was relatively high (approximately 6E-3), indicating release from intact particle coatings. The Ag-110m inventory in individual particles exhibited a very broad distribution, with some particles retaining =80% of the predicted inventory and others retaining less than 25%. The average degree of Ag-110m retention in 60 gamma counted particles was approximately 50%. This elevated silver release is in agreement with analysis of silver on the Capsule 6 components, which indicated an average release of 38% of the Capsule 6 inventory from the fuel compacts. In spite of the relatively high degree of silver release from the particles, virtually none of the Ag-110m released was found in the compact matrix, and presumably migrated out of the compact and was deposited on the irradiation capsule components. Release of all other fission products from the particles appears to be less than a single

  15. Post-irradiation examinations of a Zr2.5Nb pressure tube of the Karachi nuclear power plant (KANUPP)

    NASA Astrophysics Data System (ADS)

    Zaheer, Mohammed Sajjad; Akhtar, Javed Iqbal; Ahmad, Ejaz; Saleem, Muhammad; Hussain, Syed Mukarrum; Qureshi, Masroor Ahmad; Khan, Azmatullah; Ali, Rafaqat; Zafarullah, Muhammad

    1996-09-01

    The results of post-irradiation examinations of a pressure tube of fuel channel No. G-12 of KANUPP have been described. A detailed study was made in Canada by AECL. A parallel investigation on its seven rings of about 50 mm length each was also carried out at PINSTECH. Visual inspection showed normal oxidation effects. Gamma spectrometry showed the presence of 95Zr and 95Nb. Microstructural study revealed the characteristic alpha plus a transformed beta phase structure.

  16. AGR-1 Compact 4-1-1 Post-Irradiation Examination Results

    SciTech Connect

    Demkowicz, Paul Andrew; Harp, Jason M.; Winston, Philip L.; Ploger, Scott A.; van Rooyen, Isabella J.

    2016-02-01

    Destructive post-irradiation examination was performed on AGR-1 fuel Compact 4-1-1, which was irradiated to a final compact-average burnup of 19.4% FIMA (fissions per initial metal atom) and a time-average, volume-average temperature of 1072°C. The analysis of this compact focused on characterizing the extent of fission product release from the particles and examining particles to determine the condition of the kernels and coating layers. The work included deconsolidation of the compact and leach-burn-leach analysis, visual inspection and gamma counting of individual particles, metallurgical preparation of selected particles, and examination of particle cross-sections with optical microscopy, electron microscopy, and elemental analysis. Deconsolidation-leach-burn-leach (DLBL) analysis revealed no particles with failed TRISO or failed SiC layers (as indicated by very low uranium inventory in all of the leach solutions). The total fractions of the predicted compact inventories of fission products Ce-144, Cs-134, Cs-137, and Sr-90 that were present in the compact outside of the SiC layers were <2×10-6, based on DLBL data. The Ag-110m fraction in the compact outside the SiC layers was 3.3×10-2, indicating appreciable release of silver through the intact coatings and subsequent retention in the OPyC layers or matrix. The Eu-154 fraction was 2.4×10-4, which is equivalent to the inventory in one average particle, and indicates a small but measurable level of release from the intact coatings. Gamma counting of 61 individual particles indicated no particles with anomalously low fission product retention. The average ratio of measured inventory to calculated inventory was close to a value of 1.0 for several fission product isotopes (Ce-144, Cs-134, and Cs-137), indicating good retention and reasonably good agreement with the predicted inventories. Measured-to-calculated (M/C) activity ratios for fission products Eu-154, Eu-155, Ru-106, Sb

  17. Final Report on MEGAPIE Target Irradiation and Post-Irradiation Examination

    SciTech Connect

    Yong, Dai

    2015-06-30

    Megawatt pilot experiment (MEGAPIE) was successfully performed in 2006. One of the important goals of MEGAPIE is to understand the behaviour of structural materials of the target components exposed to high fluxes of high-energy protons and spallation neutrons in flowing LBE (liquid lead-bismuth eutectic) environment by conducting post-irradiation examination (PIE). The PIE includes four major parts: non-destructive test, radiochemical analysis of production and distribution of radionuclides produced by spallation reaction in LBE, analysis of LBE corrosion effects on structural materials, T91 and SS 316L steels, and mechanical testing of the T91 and SS 316L steels irradiated in the lower part of the target. The non-destructive test (NDT) including visual inspection and ultrasonic measurement was performed in the proton beam window area of the T91 calotte of the LBE container, the most intensively irradiated part of the MEGAPIE target. The visual inspection showed no visible failure and the ultrasonic measurement demonstrated no detectable change in thickness in the beam window area. Gamma mapping was also performed in the proton beam window area of the AlMg3 safety-container. The gamma mapping results were used to evaluate the accumulated proton fluence distribution profile, the input data for determining irradiation parameters. Radiochemical analysis of radionuclides produced by spallation reaction in LBE is to improve the understanding of the production and distribution of radionuclides in the target. The results demonstrate that the radionuclides of noble metals, 207Bi, 194Hg/Au are rather homogeneously distributed within the target, while radionuclides of electropositive elements are found to be deposited on the steel-LBE interface. The corrosion effect of LBE on the structural components under intensive irradiation was investigated by metallography. The results show that no evident corrosion damages. However, unexpected deep

  18. Interim report on the post irradiation examination of capsules 2 and 3 of the HFR-B1 experiment

    SciTech Connect

    Myers, B.F.; Pott, G.; Schenk, W.; Schroeder, R.; Kuehlein, W.; Buecker, H.J.; Dahmen, H.; Landsgesell, K.; Nieveler, F.

    1994-09-01

    This is an interim report on the post irradiation examination (PIE) of capsules 2 and 3 of the HFR-B1 experiment The PIE has been conducted by the Forschungszentrum Juelich and is nearing completion. After disassembly of the capsules, the examination focused on capsule components including fuel compacts, inert compacts fired in different media, graphite cylinders of different grades, unbonded coated fuel particles and unfueled graphite; in addition, heating experiments with intermittent injections of water vapor were conducted using fuel compacts and the kernels of uranium oxycarbide. Measurement involved gamma scanning and counting, photography, metallography, dimensional and weight changes, burnup determination and fission product release.

  19. MOX capsule post-irradiation examination. Volume 2: Test plan for 30-GWd/MT burnup fuel

    SciTech Connect

    Morris, R.N.

    1997-12-01

    This test plan is a Level-2 document as defined in the Fissile Materials Disposition Program Light-Water Reactor Mixed-Oxide Fuel Irradiation Test Project Plan. The planned post-irradiation examination (PIE) work to be performed on the mixed uranium and plutonium oxide fuel capsules that have received burnups of approximately 30 GWd/MT is described. The major emphasis of this PIE task will be material interactions, particularly indications of gallium transport and interactions. This PIE will include gamma scanning, ceramography, metallography, pellet radial gallium analysis, and clad gallium analysis. A preliminary PIE report will be generated before all the work is completed so that the progress of the fuel irradiation may be known in a timely manner.

  20. Post-irradiation-examination of irradiated fuel outside the hot cell

    SciTech Connect

    Dawn E. Janney; Adam B. Robinson; Thomas P. O'Holleran; R. Paul Lind; Marc Babcock; Laurence C. Brower; Julie Jacobs; Pamela K. Hoggan

    2007-09-01

    Because of their high radioactivity, irradiated fuels are commonly examined in a hot cell. However, the Idaho National Laboratory (INL) has recently investigated irradiated U-Mo-Al metallic fuel from the Reduced Enrichment for Research and Test Reactors (RERTR) project using a conventional unshielded scanning electron microscope outside a hot cell. This examination was possible because of a two-step sample-preparation approach in which a small volume of fuel was isolated in a hot cell and shielding was introduced during later stages of sample preparation. The resulting sample contained numerous sample-preparation artifacts but allowed analysis of microstructures from selected areas.

  1. Preliminary results of post-irradiation examination of the AGR-1 TRISO fuel compacts

    SciTech Connect

    Paul Demkowicz; John Hunn; Robert Morris; Jason Harp; Philip Winston; Charles Baldwin; Fred Montgomery; Scott Ploger; Isabella van Rooyen

    2012-10-01

    Five irradiated fuel compacts from the AGR-1 experiment have been examined in detail in order to assess in-pile fission product release behavior. Compacts were electrolytically deconsolidated and analyzed using the leach-burn-leach technique to measure fission product inventory in the compact matrix and identify any particles with a defective SiC layer. Loose particles were then gamma counted to measure the fission product inventory. One particle with a defective SiC layer was found in the five compacts examined. The fractional release of Ag 110m from the particles was significant. The total fraction of silver released from all the particles within a compact ranged from 0-0.63 and individual particles within a single compact often exhibited a very wide range of silver release. The average fractional release of Eu-154 from all particles in a compact was 2.4×10-4—1.3×10-2, which is indicative of release through intact coatings. The fractional Cs-134 inventory in the compact matrix was <2×10-5 when all coatings remained intact, indicating good cesium retention. Approximately 1% of the palladium inventory was found in the compact matrix for two of the compacts, indicating significant release through intact coatings.

  2. Post irradiation examination of simulated fission product doped hyperstoichiometric mixed oxide fuel pins*1

    NASA Astrophysics Data System (ADS)

    Götzmann, O.; Kleykamp, H.

    1980-03-01

    Two miniature fuel pins containing uranium-plutonium oxide with a hyperstoichiometric oxygen-to-metal ratio and selective fission product elements have been irradiated in the BR 2 reactor at Mol, Belgium, for two reactor cycles (46 days). One of the pins had a niobium metal coating on the inner cladding surface to act as oxygen getter. Both pins were subjected to a detailed examination by ceramography and electronprobe microanalysis. The results have been interpreted in the light of a recently published thermochemical model for the cladding attack. The very different oxygen potential environments in the two pins produced entirely different clad corrosion phenomena probably due to different cladding attack mechanisms. The niobium coating worked well in reducing the oxygen potential. However, there exists a draw back with niobium due to the formation of relatively stable intermetallic phases with noble metal fission products.

  3. Post-Irradiation Examination of 237Np Targets for 238Pu Production

    SciTech Connect

    Morris, Robert Noel; Baldwin, Charles A; Hobbs, Randy W; Schmidlin, Joshua E

    2015-01-01

    Oak Ridge National Laboratory is recovering the US 238Pu production capability and the first step in the process has been to evaluate the performance of a 237Np target cermet pellet encased in an aluminum clad. The process proceeded in 3 steps; the first step was to irradiate capsules of single pellets composed of NpO2 and aluminum power to examine their shrinkage and gas release. These pellets were formed by compressing sintered NpO2 and aluminum powder in a die at high pressure followed by sintering in a vacuum furnace. Three temperatures were chosen for sintering the solution precipitated NpO2 power used for pellet fabrication. The second step was to irradiate partial targets composed of 8 pellets in a semi-prototypical arrangement at the two best performing sintering temperatures to determine which temperature gave a pellet that performed the best under the actual planned irradiation conditions. The third step was to irradiate ~50 pellets in an actual target configuration at design irradiation conditions to assess pellet shrinkage and gas release, target heat transfer, and dimensional stability. The higher sintering temperature appeared to offer the best performance after one cycle of irradiation by having the least shrinkage, thus keeping the heat transfer gap between the pellets and clad small minimizing the pellet operating temperature. The final result of the testing was a target that can meet the initial production goals, satisfy the reactor safety requirements, and can be fabricated in production quantities. The current focus of the program is to verify that the target can be remotely dissembled, the pellets dissolved, and the 238Pu recovered. Tests are being conducted to examine these concerns and to compare results to code predictions. Once the performance of the full length targets has been quantified, the pellet 237Np loading will be revisited to determine if it can be

  4. Post-irradiation examination of prototype Al-64 wt% U{sub 3}Si{sub 2} fuel rods from NRU

    SciTech Connect

    Sears, D.F.; Primeau, M.F.; Buchanan, C.; Rose, D.

    1997-08-01

    Three prototype fuel rods containing Al-64 wt% U{sub 3}Si{sub 2} (3.15 gU/cm{sup 3}) have been irradiated to their design burnup in the NRU reactor without incident. The fuel was fabricated using production-scale equipment and processes previously developed for Al-U{sub 3}Si fuel fabrication at Chalk River Laboratories, and special equipment developed for U{sub 3}Si{sub 2} powder production and handling. The rods were irradiated in NRU up to 87 at% U-235 burnup under typical driver fuel conditions; i.e., nominal coolant inlet temperature 37{degrees}C, inlet pressure 654 kPa, mass flow 12.4 L/s, and element linear power ratings up to 73 kW/m. Post-irradiation examinations showed that the fuel elements survived the irradiation without defects. Fuel core diametral increases and volumetric swelling were significantly lower than that of Al-61 wt% U{sub 3}Si fuel irradiated under similar conditions. This irradiation demonstrated that the fabrication techniques are adequate for full-scale fuel manufacture, and qualified the fuel for use in AECL`s research reactors.

  5. INL Initial Input to the Mission Need for Advanced Post-Irradiation Examination Capability A Non-Major System Acquisition Project

    SciTech Connect

    Vince Tonc

    2010-04-01

    Consolidated and comprehensive post-irradiation examination (PIE) capabilities will enable the science and engineering understanding needed to develop the innovative nuclear fuels and materials that are critical to the success of the U.S. Department of Energy’s (DOE) Office of Nuclear Energy (NE) programs. Existing PIE capabilities at DOE Laboratories, universities, and in the private sector are widely distributed, largely antiquated, and insufficient to support the long-range mission needs. In addition, DOE’s aging nuclear infrastructure was not designed to accommodate modern, state-of-the-art equipment and instrumentation. Currently, the U.S. does not have the capability to make use of state-of-the-art technology in a remote, hot cell environment to characterize irradiated fuels and materials on the micro, nano, and atomic scale. This “advanced PIE capability” to make use of state-of-the-art scientific instruments in a consolidated nuclear operating environment will enable comprehensive characterization and investigation that is essential for effectively implementing the nuclear fuels and materials development programs in support of achieving the U.S. DOE-NE Mission.

  6. Determining the americium transmutation rate and fission rate by post-irradiation examination within the scope of the ECRIX-H experiment

    NASA Astrophysics Data System (ADS)

    Lamontagne, J.; Pontillon, Y.; Esbelin, E.; Béjaoui, S.; Pasquet, B.; Bourdot, P.; Bonnerot, J. M.

    2013-09-01

    The ECRIX-H experiment aims to assess the feasibility of transmuting americium micro-dispersed in an inert magnesia matrix under a locally moderated neutron flux in the Phénix reactor. A first set of examinations demonstrated that pellet behaviour was satisfactory with moderate swelling at the end of the irradiation. Additional post-irradiation examinations needed to be conducted to confirm the high transmutation rate so as to definitively conclude on the success of the ECRIX-H experiment. This article presents and discusses the results of these new examinations. They confirm the satisfactory behaviour of the MgO matrix not only during the basic irradiation but also during post-irradiation thermal transients. These examinations also provide additional information on the behaviour of fission products both in the americium-based particles and in the MgO matrix. These results particularly validate the transmutation rate predicted by the calculation codes using several different analytical techniques. The fission rate is also determined. Moderate pellet swelling under irradiation (6.7 vol.%), while only 23% of the produced He and 4% of the fission gases were released from the fuel. No interaction between the pellets and the cladding. Formation of bubbles due to the precipitation of fission gases and He mainly in bubbles located inside the americium-based particles. These bubbles are the main cause of macroscopic swelling in the pellets. Well-crystallised structure of the MgO matrix which shows no amorphisation after irradiation despite the presence of fission products. The absence of any reaction of MgO with the americium-based phase, Formation of a PuO2-type crystalline phase from AmO1.62 particles following the Am transmutation process. A shielded electron probe micro-analyser (EPMA) 'CAMECA' Camebax equipped to collect and exploit the measurements using the 'SAMx' system. A Philips XL30 scanning electron microscope (SEM). Field acquisitions were performed thanks to

  7. Performance evaluation and post-irradiation examination of a novel LWR fuel composed of U0.17ZrH1.6 fuel pellets bonded to Zircaloy-2 cladding by lead bismuth eutectic

    NASA Astrophysics Data System (ADS)

    Balooch, Mehdi; Olander, Donald R.; Terrani, Kurt A.; Hosemann, Peter; Casella, Andrew M.; Senor, David J.; Buck, Edgar C.

    2017-04-01

    A novel light water reactor fuel has been designed and fabricated at the University of California, Berkeley; irradiated at the Massachusetts Institute of Technology Reactor; and examined within the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory. This fuel consists of U0.17ZrH1.6 fuel pellets core-drilled from TRIGA reactor fuel elements that are clad in Zircaloy-2 and bonded with lead-bismuth eutectic. The performance evaluation and post irradiation examination of this fuel are presented here.

  8. Post Irradiation Capabilities at the Idaho National Laboratory

    SciTech Connect

    J. L. Schulthess; K. E. Rosenberg

    2011-05-01

    The U.S. Department of Energy (DOE), Office of Nuclear Energy (NE) oversees the efforts to ensure nuclear energy remains a viable option for the United States. A significant portion of these efforts are related to post-irradiation examinations (PIE) of highly activated fuel and materials that are subject to the extreme environment inside a nuclear reactor. As the lead national laboratory, Idaho National Laboratory (INL) has a rich history, experience, workforce and capabilities for performing PIE. However, new advances in tools and techniques for performing PIE now enable understanding the performance of fuels and materials at the nano-scale and smaller level. Examination at this level is critical since this is the scale at which irradiation damage occurs. The INL is on course to adopt these advanced tools and techniques to develop a comprehensive nuclear fuels and materials characterization capability that is unique in the world. Because INL has extensive PIE capabilities currently in place, a strong foundation exist to build upon as new capabilities are implemented and work load increases. In the recent past, INL has adopted significant capability to perform advanced PIE characterization. Looking forward, INL is planning for the addition of two facilities that will be built to meet the stringent demands of advanced tools and techniques for highly activated fuels and materials characterization. Dubbed the Irradiated Materials Characterization Laboratory (IMCL) and Advanced Post Irradiation Examination Capability , these facilities are next generation PIE laboratories designed to perform the work of PIE that cannot be performed in current DOE facilities. In addition to physical capabilities, INL has recently added two significant contributors to the Advanced Test Reactor-National Scientific User Facility (ATR-NSUF), Oak Ridge National Laboratory and University of California, Berkeley.

  9. Design of the fuels and materials examination facility (FMEF) neutron radiography facility for irradiated fuel. [LMFBR

    SciTech Connect

    Tomlinson, R.L.; Henshall, J.B.

    1981-11-01

    The Fuels and Materials Examination Facility (FMEF) is a breeder reactor program facility currently under construction at the Hanford Reservation. Major activities carried out in the FMEF are post-irradiation examination of breeder reactor subassemblies, fuel and control pins, and materials; test pin fabrication for use in the Fast Flux Test Facility (FFTF); and Secure Automated Fabrication (SAF) of FFTF and Clinch River Breeder Reactor fuel. An important feature of the FMEF is the neutron radiography examination facility which will examine full or partial fuel assemblies at short decay times following long-term reactor irradiation. The neutron source is a one-megawatt TRIGA reactor which supplies intense neutron beams to the two neutron radiography exposure facilities. These two exposure facilities operate simultaneously and independently so that both full fuel assemblies and individual fuel pins can be neutron radiographed in the separate exposure facilities at the same time using collimation systems that are continuously and remotely variable over a wide range of resolutions.

  10. Design of an Online Fission Gas Monitoring System for Post-irradiation Examination Heating Tests of Coated Fuel Particles for High-Temperature Gas-Cooled Reactors

    SciTech Connect

    Dawn Scates

    2010-10-01

    A new Fission Gas Monitoring System (FGMS) has been designed at the Idaho National Laboratory (INL) for use of monitoring online fission gas-released during fuel heating tests. The FGMS will be used with the Fuel Accident Condition Simulator (FACS) at the Hot Fuels Examination Facility (HFEF) located at the Materials and Fuels Complex (MFC) within the INL campus. Preselected Advanced Gas Reactor (AGR) TRISO (Tri-isotropic) fuel compacts will undergo testing to assess the fission product retention characteristics under high temperature accident conditions. The FACS furnace will heat the fuel to temperatures up to 2,000ºC in a helium atmosphere. Released fission products such as Kr and Xe isotopes will be transported downstream to the FGMS where they will accumulate in cryogenically cooledcollection traps and monitored with High Purity Germanium (HPGe) detectors during the heating process. Special INL developed software will be used to monitor the accumulated fission products and will report data in near real-time. These data will then be reported in a form that can be readily available to the INL reporting database. This paper describes the details of the FGMS design, the control and acqusition software, system calibration, and the expected performance of the FGMS. Preliminary online data may be available for presentation at the High Temperature Reactor (HTR) conference.

  11. AFC-1 Transmutation Fuels Post-Irradiation Hot Cell Examination 4-8 at.% - Final Report (Irradiation Experiments AFC-1B, -1F and -1Æ)

    SciTech Connect

    Bruce Hilton; Douglas Porter; Steven Hayes

    2006-09-01

    The AFC-1B, AFC-1F and AFC-1Æ irradiation tests are part of a series of test irradiations designed to evaluate the feasibility of the use of actinide bearing fuel forms in advanced fuel cycles for the transmutation of transuranic elements from nuclear waste. The tests were irradiated in the Idaho National Laboratory’s (INL) Advanced Test Reactor (ATR) to an intermediate burnup of 4 to 8 at% (2.7 - 6.8 x 1020 fiss/cm3). The tests contain metallic and nitride fuel forms with non-fertile (i.e., no uranium) and low-fertile (i.e., uranium bearing) compositions. Results of postirradiation hot cell examinations of AFC-1 irradiation tests are reported for eleven metallic alloy transmutation fuel rodlets and five nitride transmutation fuel rodlets. Non-destructive examinations included visual examination, dimensional inspection, gamma scan analysis, and neutron radiography. Detailed examinations, including fission gas puncture and analysis, metallography / ceramography and isotopics and burnup analyses, were performed on five metallic alloy and three nitride transmutation fuels. Fuel performance of both metallic alloy and nitride fuel forms was best correlated with fission density as a burnup metric rather than at.% depletion. The actinide bearing transmutation metallic alloy compositions exhibit irradiation performance very similar to U-xPu-10Zr fuel at equivalent fission densities. The irradiation performance of nitride transmutation fuels was comparable to limited data published on mixed nitride systems.

  12. 33 CFR 154.120 - Facility examinations.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Facility examinations. 154.120...) POLLUTION FACILITIES TRANSFERRING OIL OR HAZARDOUS MATERIAL IN BULK General § 154.120 Facility examinations. (a) The facility operator shall allow the Coast Guard, at any time, to make any examination and...

  13. Post Irradiation Capabilities at the Idaho National Laboratory

    SciTech Connect

    Schulthess, J.L.; Robert D. Mariani; Rory Kennedy; Doug Toomer

    2011-08-01

    The U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) oversees the research, development, and demonstration activities that ensure nuclear energy remains a viable energy option for the United States. Fuel and material development through fabrication, irradiation, and characterization play a significant role in accomplishing the research needed to support nuclear energy. All fuel and material development requires the understanding of irradiation effects on the fuel performance and relies on irradiation experiments ranging from tests aimed at targeted scientific questions to integral effects under representative and prototypic conditions. The DOE recently emphasized a solution-driven, goal-oriented, science-based approach to nuclear energy development. Nuclear power systems and materials were initially developed during the latter half of the 20th century and greatly facilitated by the United States’ ability and willingness to conduct large-scale experiments. Fifty-two research and test reactors with associated facilities for performing fabrication and pre and post irradiation examinations were constructed at what is now Idaho National Laboratory (INL), another 14 at Oak Ridge National Laboratory (ORNL), and a few more at other national laboratory sites. Building on the scientific advances of the last several decades, our understanding of fundamental nuclear science, improvements in computational platforms, and other tools now enable technological advancements with less reliance on large-scale experimentation.

  14. Post Irradiation Capabilities at the Idaho National Laboratory

    SciTech Connect

    Schulthess, J.L.

    2011-08-01

    The U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) oversees the research, development, and demonstration activities that ensure nuclear energy remains a viable energy option for the United States. Fuel and material development through fabrication, irradiation, and characterization play a significant role in accomplishing the research needed to support nuclear energy. All fuel and material development requires the understanding of irradiation effects on the fuel performance and relies on irradiation experiments ranging from tests aimed at targeted scientific questions to integral effects under representative and prototypic conditions. The DOE recently emphasized a solution-driven, goal-oriented, science-based approach to nuclear energy development. Nuclear power systems and materials were initially developed during the latter half of the 20th century and greatly facilitated by the United States ability and willingness to conduct large-scale experiments. Fifty-two research and test reactors with associated facilities for performing fabrication and pre and post irradiation examinations were constructed at what is now Idaho National Laboratory (INL), another 14 at Oak Ridge National Laboratory (ORNL), and a few more at other national laboratory sites. Building on the scientific advances of the last several decades, our understanding of fundamental nuclear science, improvements in computational platforms, and other tools now enable technological advancements with less reliance on large-scale experimentation.

  15. Post-Irradiation Study of the Alanine Dosimeter

    PubMed Central

    Desrosiers, Marc F.

    2014-01-01

    Post-irradiation stability of high-dose dosimeters has traditionally been an important measurement influence quantity. Though the exceptional stability of the alanine dosimeter response with time has rendered this factor a non-issue for routine work, the archival quality of the alanine dosimeter has not been characterized. Here the alanine pellet dosimeter response is measured up to seven years post-irradiation for a range of absorbed doses. This long-term study is accompanied by an examination of the environmental influence quantities (e.g., ambient light) on the relatively short-term (3–4 month) stability of both pellet and film commercial dosimeters. Both dosimeter types demonstrated exceptional stability in the short term and proved to be relatively insensitive to common influence quantities. The long-term data revealed a complex dose-dependent response trend. PMID:26601033

  16. AGC-2 Specimen Post Irradiation Data Package Report

    SciTech Connect

    Windes, William Enoch; Swank, W. David; Rohrbaugh, David T.; Cottle, David L.

    2015-08-01

    This report documents results of the post-irradiation examination material property testing of the creep, control, and piggyback specimens from the irradiation creep capsule Advanced Graphite Creep (AGC)-2 are reported. This is the second of a series of six irradiation test trains planned as part of the AGC experiment to fully characterize the neutron irradiation effects and radiation creep behavior of current nuclear graphite grades. The AGC-2 capsule was irradiated in the Idaho National Laboratory Advanced Test Reactor at a nominal temperature of 600°C and to a peak dose of 5 dpa (displacements per atom). One-half of the creep specimens were subjected to mechanical stresses (an applied stress of either 13.8, 17.2, or 20.7 MPa) to induce irradiation creep. All post-irradiation testing and measurement results are reported with the exception of the irradiation mechanical strength testing, which is the last destructive testing stage of the irradiation testing program. Material property tests were conducted on specimens from 15 nuclear graphite grades using a similar loading configuration as the first AGC capsule (AGC-1) to provide easy comparison between the two capsules. However, AGC-2 contained an increased number of specimens (i.e., 487 total specimens irradiated) and replaced specimens of the minor grade 2020 with the newer grade 2114. The data reported include specimen dimensions for both stressed and unstressed specimens to establish the irradiation creep rates, mass and volume data necessary to derive density, elastic constants (Young’s modulus, shear modulus, and Poisson’s ratio) from ultrasonic time-of-flight velocity measurements, Young’s modulus from the fundamental frequency of vibration, electrical resistivity, and thermal diffusivity and thermal expansion data from 100–500°C. No data outliers were determined after all measurements were completed. A brief statistical analysis was performed on the irradiated data and a limited comparison between

  17. Characterization of the 309 fuel examination facility

    SciTech Connect

    Greenhalgh, W.O.; Cornwell, B.C.

    1997-07-09

    This document identifies radiological, chemical and physical conditions inside the Fuel Examination Facility. It is located inside the Plutonium Recycle Test Reactor containment structure (309 Building.) The facility was a hot cell used for examination of PRTR fuel and equipment during the 1960`s. Located inside the cell is a PRTR shim rod assembly, reported are radiological conditions of the sample. The conditions were assessed as part of overall 309 Building transition.

  18. Post irradiation effects (PIE) in integrated circuits

    NASA Technical Reports Server (NTRS)

    Shaw, D. C.; Lowry, L.; Barnes, C.; Zakharia, M.; Agarwal, S.; Rax, B.

    1991-01-01

    Post-irradiation effects (PIE) ranging from normal recovery to catastrophic failure have been observed in integrated circuits during the PIE period. Data presented show failure due to rebound after a 10 krad(Si) dose. In particular, five device types are investigated with varying PIE response. Special attention has been given to the HI1-507A analog multiplexer because its PIE response is extreme. X-ray diffraction has been uniquely employed to measure physical stress in the HI1-507A metallization. An attempt has been made to show a relationship between stress relaxation and radiation effects. All data presented support the current MIL-STD Method 1019.4 but demonstrate the importance of performing PIE measurements, even when mission doses are as low as 10 krad(Si).

  19. Post irradiation effects (PIE) in integrated circuits

    NASA Technical Reports Server (NTRS)

    Shaw, D. C.; Lowry, L.; Barnes, C.; Zakharia, M.; Agarwal, S.; Rax, B.

    1991-01-01

    Post-irradiation effects (PIE) ranging from normal recovery to catastrophic failure have been observed in integrated circuits during the PIE period. Data presented show failure due to rebound after a 10 krad(Si) dose. In particular, five device types are investigated with varying PIE response. Special attention has been given to the HI1-507A analog multiplexer because its PIE response is extreme. X-ray diffraction has been uniquely employed to measure physical stress in the HI1-507A metallization. An attempt has been made to show a relationship between stress relaxation and radiation effects. All data presented support the current MIL-STD Method 1019.4 but demonstrate the importance of performing PIE measurements, even when mission doses are as low as 10 krad(Si).

  20. Wuenscher Examines Sky lab Experiment Facility

    NASA Technical Reports Server (NTRS)

    1972-01-01

    Hans F. Wuenscher, assistant director for Advanced Space Projects Engineering Laboratory at Marshall Space Flight Center (MSFC), examined the facility to be used by Skylab astronauts in performing a number of experiments in material science and manufacturing in space. The equipment shown here is a duplicate of the M512 Experiment hardware flown in the Multiple Docking Adapter section of the Sky lab. This equipment, itself an experiment, was be used for conducting 5 other experiments in the round vacuum chamber. Inside was a cavity which held the M518 Multipurpose Electric Furnace, a facility which was used for conducting other experiments. In all, a total of 17 experiments were conducted using this facility and furnace.

  1. Wuenscher Examines Sky lab Experiment Facility

    NASA Technical Reports Server (NTRS)

    1972-01-01

    Hans F. Wuenscher, assistant director for Advanced Space Projects Engineering Laboratory at Marshall Space Flight Center (MSFC), examined the facility to be used by Skylab astronauts in performing a number of experiments in material science and manufacturing in space. The equipment shown here is a duplicate of the M512 Experiment hardware flown in the Multiple Docking Adapter section of the Sky lab. This equipment, itself an experiment, was be used for conducting 5 other experiments in the round vacuum chamber. Inside was a cavity which held the M518 Multipurpose Electric Furnace, a facility which was used for conducting other experiments. In all, a total of 17 experiments were conducted using this facility and furnace.

  2. Hot Fuel Examination Facility/South

    SciTech Connect

    Not Available

    1990-05-01

    This document describes the potential environmental impacts associated with proposed modifications to the Hot Fuel Examination Facility/South (HFEF/S). The proposed action, to modify the existing HFEF/S at the Argonne National Laboratory-West (ANL-W) on the Idaho National Engineering Laboratory (INEL) in southeastern Idaho, would allow important aspects of the Integral Fast Reactor (IFR) concept, offering potential advantages in nuclear safety and economics, to be demonstrated. It would support fuel cycle experiments and would supply fresh fuel to the Experimental Breeder Reactor-II (EBR-II) at the INEL. 35 refs., 12 figs., 13 tabs.

  3. VIEW OF BUILDING 122 EXAMINATION FACILITIES THAT SUPPORT ROUTINE EMPLOYEE ...

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

    VIEW OF BUILDING 122 EXAMINATION FACILITIES THAT SUPPORT ROUTINE EMPLOYEE AND SUBCONTRACTOR PHYSICAL EXAMINATIONS. (10/85) - Rocky Flats Plant, Emergency Medical Services Facility, Southwest corner of Central & Third Avenues, Golden, Jefferson County, CO

  4. Post-irradiation effects in polyethylenes irradiated under various atmospheres

    NASA Astrophysics Data System (ADS)

    Suljovrujic, E.

    2013-08-01

    If a large amount of polymer free radicals remain trapped after irradiation of polymers, the post-irradiation effects may result in a significant alteration of physical properties during long-term shelf storage and use. In the case of polyethylenes (PEs) some failures are attributed to the post-irradiation oxidative degradation initiated by the reaction of residual free radicals (mainly trapped in crystal phase) with oxygen. Oxidation products such as carbonyl groups act as deep traps and introduce changes in carrier mobility and significant deterioration in the PEs electrical insulating properties. The post-irradiation behaviour of three different PEs, low density polyethylene (LDPE), linear low density polyethylene (LLDPE) and high density polyethylene (HDPE) was studied; previously, the post-irradiation behaviour of the PEs was investigated after the irradiation in air (Suljovrujic, 2010). In this paper, in order to investigate the influence of different irradiation media on the post-irradiation behaviour, the samples were irradiated in air and nitrogen gas, to an absorbed dose of 300 kGy. The annealing treatment of irradiated PEs, which can substantially reduce the concentration of free radicals, is used in this study, too. Dielectric relaxation behaviour is related to the difference in the initial structure of PEs (such as branching, crystallinity etc.), to the changes induced by irradiation in different media and to the post-irradiation changes induced by storage of the samples in air. Electron spin resonance (ESR), differential scanning calorimetry (DSC), infra-red (IR) spectroscopy and gel measurements were used to determine the changes in the free radical concentration, crystal fraction, oxidation and degree of network formation, respectively.

  5. Towards evaluating post-irradiation tissue alterations

    NASA Astrophysics Data System (ADS)

    Daar, Eman; Bradley, D. A.; Alkhorayef, M.; Al-Mugren, K. S.; Abdallat, R. G.; Al-Dousari, H.

    2017-08-01

    There is apaucity of data concerning irradiation effects on the extracellular matrix and on organised tissues. Examples of such research are cited as are some of the limiting factors towards obtaining meaningful results. This would engender a range of research towards further improving the quality of life, most pointedly of those receiving radiotherapy. As cancer survivor rates increase, survivors are more likely to experience side effects of radiotherapy. This study examines the effects of radiotherapy doses on the extracellular matrix as hyaluronic acid (HA) and pericardium.

  6. Post-Irradiation Polymerization of a Silorane Composite

    DTIC Science & Technology

    2013-04-26

    Post-Irradiation Polymerization of a Silorane Composite A THESIS Presented to the Faculty of The Air Force Postgraduate Dental School...Oral Biology By Bryan Michael Wilson, BS, MS, DDS Dunn Dental Clinic JBSA-Lackland, TX 26 Apr 2013 2 ii Poet-Irradiation...Postgraduate Dental School (AFPDS) 4. Phone: 210-671-9822 5. Type of clearance: _Paper _Article_ Book _x_Poster _Presentation _Other 6. Title: Post

  7. Post-irradiation stability of polyvinyl chloride at sterilizing doses

    NASA Astrophysics Data System (ADS)

    Naimian, F.; Katbab, A. A.; Nazokdast, H.

    1994-12-01

    Post-irradiation stability of plasticized PVC irradiated by 60Co gamma ray at sterilizing doses has been studied. Effects of irradiation upon chemical structure, mechanical properties and rheological behaviour of samples contained different amounts of Di(2-ethylhexyl)phthalate as plasticizer have been investigated. Formation of conjugated double bonds, carbonyl and hydroxyl groups have been followed by UV and FTIR spectrometers up to 6 months after irradiation. FTIR spectra of irradiated samples showed no significant changes in carbonyl and hydroxyl groups even 6 months after irradiation. However, changes in UV-visible spectra was observed for the irradiated samples up to 6 months post-irradiation. This has been attributed to the formation of polyenes which leads to the discoloration of this polymer. Despite a certain degree of discoloration, it appears that the mechanical properties of PVC are not affected by irradiation at sterilizing doses. No change in the melt viscosity of the irradiated PVC samples with post-irradiation was observed, which is in consistent with the IR results.

  8. Race, ethnicity, and noxious facilities: Environmental racism re- examined

    SciTech Connect

    Nieves, A.L. |; Nieves, L.A.

    1992-10-01

    The charge has been made that hazardous facilities tend to be located in proximity to minority populations. This study uses a facility density measure for three categories of noxious facilities to examine the relationship between facilities and minority population concentrations. County-level data are used in a correlation analysis for African Americans, Hispanics, and Asians in the four major regions of the US. Even controlling for income and housing value, and limiting the data set to urban areas, consistent patterns of moderate to strong association of facility densities with minority population percentages are found.

  9. Post Irradiation Evaluation of Thermal Control Coatings and Solid Lubricants to Support Fission Surface Power Systems

    NASA Technical Reports Server (NTRS)

    Bowman, Cheryl L.; Jaworske, Donald A.; Stanford, Malcolm K.; Persinger, Justin A.; Khorsandi, Behrooz; Blue, Thomas E.

    2007-01-01

    The development of a nuclear power system for space missions, such as the Jupiter Icy Moons Orbiter or a lunar outpost, requires substantially more compact reactor design than conventional terrestrial systems. In order to minimize shielding requirements and hence system weight, the radiation tolerance of component materials within the power conversion and heat rejection systems must be defined. Two classes of coatings, thermal control paints and solid lubricants, were identified as material systems for which limited radiation hardness information was available. Screening studies were designed to explore candidate coatings under a predominately fast neutron spectrum. The Ohio State Research Reactor Facility staff performed irradiation in a well characterized, mixed energy spectrum and performed post irradiation analysis of representative coatings for thermal control and solid lubricant applications. Thermal control paints were evaluated for 1 MeV equivalent fluences from 10(exp 13) to 10(exp 15) n per square centimeters. No optical degradation was noted although some adhesive degradation was found at higher fluence levels. Solid lubricant coatings were evaluated for 1 MeV equivalent fluences from 10(exp 15) to 10(exp 16) n per square centimeters with coating adhesion and flexibility used for post irradiation evaluation screening. The exposures studied did not lead to obvious property degradation indicating the coatings would have survived the radiation environment for the previously proposed Jupiter mission. The results are also applicable to space power development programs such as fission surface power for future lunar and Mars missions.

  10. Post Irradiation Evaluation of Thermal Control Coatings and Solid Lubricants to Support Fission Surface Power Systems

    NASA Astrophysics Data System (ADS)

    Bowman, Cheryl L.; Jaworske, Donald A.; Stanford, Malcolm K.; Persinger, Justin A.; Khorsandi, Behrooz; Blue, Thomas E.

    2007-01-01

    The development of a nuclear power system for space missions, such as the Jupiter Icy Moons Orbiter or a lunar outpost, requires substantially more compact reactor design than conventional terrestrial systems. In order to minimize shielding requirements and hence system weight, the radiation tolerance of component materials within the power conversion and heat rejection systems must be defined. Two classes of coatings, thermal control paints and solid lubricants, were identified as material systems for which limited radiation hardness information was available. Screening studies were designed to explore candidate coatings under a predominately fast neutron spectrum. The Ohio State Research Reactor Facility staff performed irradiation in a well characterized, mixed energy spectrum and performed post irradiation analysis of representative coatings for thermal control and solid lubricant applications. Thermal control paints were evaluated for 1 MeV equivalent fluences from 1013 to 1015 n/cm2. No optical degradation was noted although some adhesive degradation was found at higher fluence levels. Solid lubricant coatings were evaluated for 1 MeV equivalent fluences from 1015 to 1016 n/cm2 with coating adhesion and flexibility used for post irradiation evaluation screening. The exposures studied did not lead to obvious property degradation indicating the coatings would have survived the radiation environment for the previously proposed Jupiter mission. The results are also applicable to space power development programs such as fission surface power for future lunar and Mars missions.

  11. Post Irradiation Evaluation of Thermal Control Coatings and Solid Lubricants to Support Fission Surface Power Systems

    SciTech Connect

    Bowman, Cheryl L.; Jaworske, Donald A.; Stanford, Malcolm K.; Persinger, Justin A.; Khorsandi, Behrooz; Blue, Thomas E.

    2007-01-30

    The development of a nuclear power system for space missions, such as the Jupiter Icy Moons Orbiter or a lunar outpost, requires substantially more compact reactor design than conventional terrestrial systems. In order to minimize shielding requirements and hence system weight, the radiation tolerance of component materials within the power conversion and heat rejection systems must be defined. Two classes of coatings, thermal control paints and solid lubricants, were identified as material systems for which limited radiation hardness information was available. Screening studies were designed to explore candidate coatings under a predominately fast neutron spectrum. The Ohio State Research Reactor Facility staff performed irradiation in a well characterized, mixed energy spectrum and performed post irradiation analysis of representative coatings for thermal control and solid lubricant applications. Thermal control paints were evaluated for 1 MeV equivalent fluences from 1013 to 1015 n/cm2. No optical degradation was noted although some adhesive degradation was found at higher fluence levels. Solid lubricant coatings were evaluated for 1 MeV equivalent fluences from 1015 to 1016 n/cm2 with coating adhesion and flexibility used for post irradiation evaluation screening. The exposures studied did not lead to obvious property degradation indicating the coatings would have survived the radiation environment for the previously proposed Jupiter mission. The results are also applicable to space power development programs such as fission surface power for future lunar and Mars missions.

  12. An Examination of Special Focus Facility Nursing Homes

    ERIC Educational Resources Information Center

    Castle, Nicholas G.; Engberg, John

    2010-01-01

    Purpose: Nursing facilities that are determined to have a greater number of quality problems, more serious problems than average, and a demonstrated pattern of quality problems are included in the Special Focus Facility (SFF) initiative. The purpose of this research was to provide descriptive information on these SFFs and to examine the quality…

  13. An Examination of Special Focus Facility Nursing Homes

    ERIC Educational Resources Information Center

    Castle, Nicholas G.; Engberg, John

    2010-01-01

    Purpose: Nursing facilities that are determined to have a greater number of quality problems, more serious problems than average, and a demonstrated pattern of quality problems are included in the Special Focus Facility (SFF) initiative. The purpose of this research was to provide descriptive information on these SFFs and to examine the quality…

  14. Post-irradiation crosslinking of partially cured unsaturated polyester resin

    NASA Astrophysics Data System (ADS)

    Jurkin, Tanja; Pucić, Irina

    2006-09-01

    The post-irradiation crosslinking of unsaturated polyester (UP) resin samples irradiated to different doses was monitored during the 15-days period. The post-reaction sensitivity of three experimental techniques was evaluated. Significant changes were detected by extraction analysis that also included determination of the free styrene content. The most substantial changes were detected by differential scanning calorimetry, even up to 5 days after the irradiation. The sensitivity and reproducibility of FTIR was the lowest. The first two techniques detected the influence of particular reaction periods, at which the radiation crosslinking was terminated, on the post-reaction.

  15. Overview of Idaho National Laboratory's Hot Fuels Examination Facility

    SciTech Connect

    Adam B. Robinson; R. Paul Lind; Daniel M. Wachs

    2007-09-01

    The Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) of the Idaho National Laboratory was constructed in the 1960’s and opened for operation in the 1975 in support of the liquid metal fast breeder reactor research. Specifically the facility was designed to handle spent fuel and irradiated experiments from the Experimental Breeder Reactor EBRII, the Fast Flux Test Facility (FFTF), and the Transient Reactor Test Facility (TREAT). HFEF is a large alpha-gamma facility designed to remotely characterize highly radioactive materials. In the late 1980’s the facility also began support of the US DOE waste characterization including characterizing contact-handled transuranic (CH-TRU) waste. A description of the hot cell as well as some of its primary capabilities are discussed herein.

  16. Post-Irradiation Non-Destructive Analyses of the AFIP-7 Experiment

    NASA Astrophysics Data System (ADS)

    Williams, W. J.; Robinson, A. B.; Rabin, B. H.

    2017-08-01

    This article reports the results and interpretation of post-irradiation non-destructive examinations performed on four curved full-size fuel plates that comprise the AFIP-7 experiment. These fuel plates, having a U-10 wt.%Mo monolithic design, were irradiated under moderate operating conditions in the Advanced Test Reactor to assess fuel performance for geometries that are prototypic of research reactor fuel assemblies. Non-destructive examinations include visual examination, neutron radiography, profilometry, and precision gamma scanning. This article evaluates the qualitative and quantitative data taken for each plate, compares corresponding data sets, and presents the results of swelling analyses. These characterization results demonstrate that the fuel meets established irradiation performance requirements for mechanical integrity, geometric stability, and stable and predictable behavior.

  17. A flight test facility design for examining digital information transfer

    NASA Technical Reports Server (NTRS)

    Knox, Charles E.

    1990-01-01

    Information is given in viewgraph form on a flight test facility design for examining digital information transfer. Information is given on aircraft/ground exchange, data link research activities, data link display format, a data link flight test, and the flight test setup.

  18. Microstructure evolution during helium irradiation and post-irradiation annealing in a nanostructured reduced activation steel

    NASA Astrophysics Data System (ADS)

    Liu, W. B.; Ji, Y. Z.; Tan, P. K.; Zhang, C.; He, C. H.; Yang, Z. G.

    2016-10-01

    Severe plastic deformation, intense single-beam He-ion irradiation and post-irradiation annealing were performed on a nanostructured reduced activation ferritic/martensitic (RAFM) steel to investigate the effect of grain boundaries (GBs) on its microstructure evolution during these processes. A surface layer with a depth-dependent nanocrystalline (NC) microstructure was prepared in the RAFM steel using surface mechanical attrition treatment (SMAT). Microstructure evolution after helium (He) irradiation (24.8 dpa) at room temperature and after post-irradiation annealing was investigated using Transmission Electron Microscopy (TEM). Experimental observation shows that GBs play an important role during both the irradiation and the post-irradiation annealing process. He bubbles are preferentially trapped at GBs/interfaces during irradiation and cavities with large sizes are also preferentially trapped at GBs/interfaces during post-irradiation annealing, but void denuded zones (VDZs) near GBs could not be unambiguously observed. Compared with cavities at GBs and within larger grains, cavities with smaller size and higher density are found in smaller grains. The average size of cavities increases rapidly with the increase of time during post-irradiation annealing at 823 K. Cavities with a large size are observed just after annealing for 5 min, although many of the cavities with small sizes also exist after annealing for 240 min. The potential mechanism of cavity growth behavior during post-irradiation annealing is also discussed.

  19. Post-irradiation polymerization of composites containing bis-GMA and TEGDMA.

    PubMed

    Tarumi, H; Imazato, S; Ehara, A; Kato, S; Ebi, N; Ebisu, S

    1999-07-01

    This study was conducted to evaluate the effect of the amount of TEGDMA on post-irradiation polymerization of bis-GMA based composites. Four experimental composites containing bis-GMA and TEGDMA at the ratios (w/w) of 75/25, 70/30, 67/33, and 50/50 were prepared. The degree of conversion of each composite was measured by Fourier transformation infrared spectroscopy immediately after being cured and after 24 h of storage, and the post-irradiation polymerization was determined. In addition, the change in respective amounts of residual bis-GMA and TEGDMA in cured specimens over 24 h was determined by high performance liquid chromatography. Data were analyzed by means of ANOVA, followed by a Fisher's PLSD test at a significance level of 0.05. At both stages of as-cured and after 24 h-sotrage, the composites containing greater amounts of TEGDMA showed a greater degree of conversion. The amount of post-irradiation polymerization decreased as the content of the incorporated TEGDMA increased. The reduction in the amount of TEGDMA remaining unreacted during post-irradiation polymerization also decreased as the content of TEGDMA increased, while the amount of unreacted bis-GMA showed almost constant values. An increase in the amount of TEGDMA-incorporation in bis-GMA based composites resulted in less post-irradiation polymerization. As the change in the amount of residual unreacted TEGDMA in cured specimens showed the same trend as the results of the post-irradiation polymerization. TEGDMA is considered to be the main contributor to post-irradiation polymerization of bis-GMA based composites.

  20. Post-irradiation otitis media, rhinosinusitis, and their interrelationship in nasopharyngeal carcinoma patients treated by IMRT.

    PubMed

    Hsin, Chung-Han; Tseng, Hsien-Chun; Lin, Huang-Pin; Chen, Tsai-Hsin

    2016-02-01

    This study aimed to investigate the occurrences of post-irradiation chronic suppurative otitis media (CSOM), otitis media with effusion (OME), chronic rhinosinusitis (CRS), and their interrelationship in nasopharyngeal carcinoma (NPC) patients treated by intensity-modulated radiotherapy (IMRT). A retrospective review of medical records and magnetic resonance imaging for NPC patients across a 5-year follow-up was conducted. Rhinosinusitis was diagnosed and staged by Lund-Mackay system. A total of 102 patients were enrolled in the study. On the 5th year following IMRT, 8 patients (7.8 %), 30 patients (29.4 %), and 17 patients (16.7 %) suffered from IMRT-induced CSOM, post-irradiation OME, and CRS, respectively. Analysis by logistic regression showed a lack of association between the occurrence of post-irradiation OME and CRS (P = 0.06). These observations indicated that the modern radiotherapy technique exhibits capability in decreasing the incidences of CSOM and CRS comparing to the data of traditional radiotherapy. But post-irradiation OME was still encountered in more than one-quarter of long-term survivors of NPC. Of note, rhinosinusitis in NPC survivors does not predispose to the development of post-irradiation OME, suggesting nasal irrigation might be unnecessary for the management of OME following radiotherapy.

  1. Fuel Accident Condition Simulator (FACS) Furnace for Post-Irradiation Heating Tests of VHTR Fuel Compacts

    SciTech Connect

    Paul A Demkowicz; Paul Demkowicz; David V Laug

    2010-10-01

    Abstract –Fuel irradiation testing and post-irradiation examination are currently in progress as part of the Next Generation Nuclear Plant Fuels Development and Qualification Program. The PIE campaign will include extensive accident testing of irradiated very high temperature reactor fuel compacts to verify fission product retention characteristics at high temperatures. This work will be carried out at both the Idaho National Laboratory (INL) and the Oak Ridge National Laboratory, beginning with accident tests on irradiated fuel from the AGR-1 experiment in 2010. A new furnace system has been designed, built, and tested at INL to perform high temperature accident tests. The Fuel Accident Condition Simulator furnace system is designed to heat fuel specimens at temperatures up to 2000°C in helium while monitoring the release of volatile fission metals (e.g. Cs, Ag, Sr, Eu, and I) and fission gases (Kr, Xe). Fission gases released from the fuel to the sweep gas are monitored in real time using dual cryogenic traps fitted with high purity germanium detectors. Condensable fission products are collected on a plate attached to a water-cooled cold finger that can be exchanged periodically without interrupting the test. Analysis of fission products on the condensation plates involves dry gamma counting followed by chemical analysis of selected isotopes. This paper will describe design and operational details of the Fuel Accident Condition Simulator (FACS) furnace system, as well as preliminary system calibration results.

  2. School Facilities in Arizona: An Examination of the Relationships between and among School Facilities Characteristics and Educational Outcomes.

    ERIC Educational Resources Information Center

    2000

    This report examines the relations between school design and student productivity and informs policy decisions. It contains three analytic sections: an analysis of school facilities characteristics and student productivity, a review of other research examining school facilities and student productivity, and an analysis of the need for school…

  3. High post-irradiation ductility thermomechanical treatment for precipitation strengthened austenitic alloys

    DOEpatents

    Laidler, James J.; Borisch, Ronald R.; Korenko, Michael K.

    1982-01-01

    A method for improving the post-irradiation ductility is described which prises a solution heat treatment following which the materials are cold worked. They are included to demonstrate the beneficial effect of this treatment on the swelling resistance and the ductility of these austenitic precipitation hardenable alloys.

  4. Pre- and post-irradiation characterization and properties measurements of ZrC coated surrogate TRISO particles

    SciTech Connect

    Vasudevamurthy, Gokul; Katoh, Yutai; Hunn, John D; Snead, Lance Lewis

    2010-09-01

    Zirconium carbide is a candidate to either replace or supplement silicon carbide as a coating material in TRISO fuel particles for high temperature gas-cooled reactor fuels. Six sets of ZrC coated surrogate microsphere samples, fabricated by the Japan Atomic Energy Agency using the fluidized bed chemical vapor deposition method, were irradiated in the High Flux Isotope Reactor at the Oak Ridge National Laboratory. These developmental samples available for the irradiation experiment were in conditions of either as-fabricated coated particles or particles that had been heat-treated to simulate the fuel compacting process. Five sets of samples were composed of nominally stoichiometric compositions, with the sixth being richer in carbon (C/Zr = 1.4). The samples were irradiated at 800 and 1250 C with fast neutron fluences of 2 and 6 dpa. Post-irradiation, the samples were retrieved from the irradiation capsules followed by microstructural examination performed at the Oak Ridge National Laboratory's Low Activation Materials Development and Analysis Laboratory. This work was supported by the US Department of Energy Office of Nuclear Energy's Advanced Gas Reactor program as part of International Nuclear Energy Research Initiative collaboration with Japan. This report includes progress from that INERI collaboration, as well as results of some follow-up examination of the irradiated specimens. Post-irradiation examination items included microstructural characterization, and nanoindentation hardness/modulus measurements. The examinations revealed grain size enhancement and softening as the primary effects of both heat-treatment and irradiation in stoichiometric ZrC with a non-layered, homogeneous grain structure, raising serious concerns on the mechanical suitability of these particular developmental coatings as a replacement for SiC in TRISO fuel. Samples with either free carbon or carbon-rich layers dispersed in the ZrC coatings experienced negligible grain size

  5. Effects of salts and temperatures on post-irradiation growth of Penicillium exposed to ultraviolet

    SciTech Connect

    Valdez, R.; Siegel, B.Z.; Siegel, S.M.

    1981-01-01

    The growth of Penicillium notatum colonies after uv irradiation of dried mycelium or spores was studied in relation to post-irradiation temperature and salt environment. Dried mycelium and spores behaved differently with respect to sensitivity to temperature, salts and uv, especially the latter. Threshold inhibitory doses for spores were modified markedly either at 4 C or in magnesium and calcium chlorides. It is suggested that these temperature and salt effects are related to prevention of photochemical membrane damage.

  6. A new integrated test structure for on-chip post-irradiation annealing in MOS devices

    SciTech Connect

    Chabrerie, C.; Flament, O.; Boudenot, J.C.

    1998-06-01

    The authors have developed a prototype test structure (named THERMOS) demonstrating the feasibility and the interest of the on-chip heating in a Silicon-On-Insulator technology. This circuit has been specially designed for the study of post-irradiation effects in a radiation-hardened CMOS technology. Preliminary results are presented here for the on-chip annealing of irradiated n-channel transistors.

  7. Scanning electron microscope facility for examination of radioactive materials

    SciTech Connect

    Gibson, J.R.; Braski, D.N.

    1985-02-01

    An AMRAY model 1200B scanning electron microscope was modified to permit remote examination of radioactive specimens. Features of the modification include pneumatic vibration isolation of the column, motorized stage controls, improvements for monitoring vacuum, and a system for changing filaments without entering the hot cell.

  8. 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.

  9. ECRIX-H experiment: Synthesis of post-irradiation examinations and simulations

    NASA Astrophysics Data System (ADS)

    Béjaoui, S.; Lamontagne, J.; Esbelin, E.; Bonnerot, J. M.; Brunon, E.; Bourdot, P.

    2011-08-01

    The purpose of the ECRIX-H experiment is to study the behaviour of a composite ceramic target made of AmO 1.62 microdispersed in an MgO matrix irradiated for 318 EFPD in the Phenix sodium-cooled fast reactor (SFR), in a specific carrier sub-assembly equipped with annular blocks of CaH x acting as a neutron moderator. Results indicate that magnesia-based inert matrix targets display satisfactory behaviour and moderate swelling under irradiation, even for significant quantities of helium produced and a high burn-up. On this basis, the design of transmutation fuel pins for recycling of minor actinides (MA) in accelerator-driven systems (ADS) or in fast neutron reactors (FR) could be optimised so as to increase their performance level (initial MA content, burn-up, etc.). The measured Am fission rate (25 at.%) was found to be lower than that predicted by neutronic simulations probably due to the inaccuracies linked to the complexity of neutron modelling and the uncertainties on nuclear data related to moderated neutron spectrum. In addition, as most of the initial Am transmuted into Pu under irradiation, a PuO x-type phase was created within the initial AmO 1.62 particles, leading to the incomplete dissolution of the irradiated targets under standard reprocessing conditions. This issue will have to be considered and investigated in greater detail for all transmutation fuels and targets devoted to the multi-recycling of MA.

  10. Post Irradiation Examination Plan for High-Burnup Demonstration Project Sister Rods

    SciTech Connect

    Scaglione, John M; Montgomery, Rose; Bevard, Bruce Balkcom

    2016-04-01

    This test plan describes the experimental work to be implemented by the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) to characterize high burnup (HBU) spent nuclear fuel (SNF) in conjunction with the High Burnup Dry Storage Cask Research and Development Project and serves to coordinate and integrate the multi-year experimental program to collect and develop data regarding the continued storage and eventual transport of HBU (i.e., >45 GWd/MTU) SNF. The work scope involves the development, performance, technical integration, and oversight of measurements and collection of relevant data, guided by analyses and demonstration of need.

  11. Performance of AGR-1 high-temperature reactor fuel during post-irradiation heating tests

    SciTech Connect

    Morris, Robert N.; Baldwin, Charles A.; Demkowicz, Paul A.; Hunn, John D.; Reber, Edward L.

    2016-05-18

    The fission product retention of irradiated low-enriched uranium oxide/uranium carbide tri-structural isotropic (TRISO) fuel compacts from the Advanced Gas-Cooled Reactor 1 (AGR-1) experiment has been evaluated at temperatures of 1600–1800 °C during post-irradiation safety tests. Fourteen compacts (a total of ~58,000 particles) with a burnup ranging from 13.4% to 19.1% fissions per initial metal atom (FIMA) have been tested using dedicated furnace systems at Idaho National Laboratory and Oak Ridge National Laboratory. The release of fission products 110mAg, 134Cs, 137Cs, 154Eu, 155Eu, 90Sr, and 85Kr was monitored while heating the fuel specimens in flowing helium. The behavior of silver, europium, and strontium appears to be dominated by inventory that was originally released through intact SiC coating layers during irradiation, but was retained in the compact at the end of irradiation and subsequently released during the safety tests. However, at a test temperature of 1800 °C, the data suggest that release of these elements through intact coatings may become significant after ~100 h. Cesium was very well retained by intact SiC layers, with a fractional release <5 × 10–6 after 300 h at 1600 °C or 100 h at 1800 °C. However, it was rapidly released from individual particles if the SiC layer failed, and therefore the overall cesium release fraction was dominated by the SiC defect and failure fractions in the fuel compacts. No complete TRISO coating layer failures were observed after 300 h at 1600 or 1700 °C, and 85Kr release was very low during the tests (particles with failed SiC, but intact outer pyrocarbon, retained most of their krypton). Krypton release from TRISO failures was only observed after ~210 h at 1800 °C in one compact. As a result, post-safety-test examination of fuel compacts and particles has focused on identifying specific particles from each compact with notable fission product release and detailed analysis of the coating

  12. Performance of AGR-1 high-temperature reactor fuel during post-irradiation heating tests

    SciTech Connect

    Morris, Robert N.; Baldwin, Charles A.; Demkowicz, Paul A.; Hunn, John D.; Reber, Edward L.

    2016-05-18

    The fission product retention of irradiated low-enriched uranium oxide/uranium carbide tri-structural isotropic (TRISO) fuel compacts from the Advanced Gas-Cooled Reactor 1 (AGR-1) experiment has been evaluated at temperatures of 1600–1800 °C during post-irradiation safety tests. Fourteen compacts (a total of ~58,000 particles) with a burnup ranging from 13.4% to 19.1% fissions per initial metal atom (FIMA) have been tested using dedicated furnace systems at Idaho National Laboratory and Oak Ridge National Laboratory. The release of fission products 110mAg, 134Cs, 137Cs, 154Eu, 155Eu, 90Sr, and 85Kr was monitored while heating the fuel specimens in flowing helium. The behavior of silver, europium, and strontium appears to be dominated by inventory that was originally released through intact SiC coating layers during irradiation, but was retained in the compact at the end of irradiation and subsequently released during the safety tests. However, at a test temperature of 1800 °C, the data suggest that release of these elements through intact coatings may become significant after ~100 h. Cesium was very well retained by intact SiC layers, with a fractional release <5 × 10–6 after 300 h at 1600 °C or 100 h at 1800 °C. However, it was rapidly released from individual particles if the SiC layer failed, and therefore the overall cesium release fraction was dominated by the SiC defect and failure fractions in the fuel compacts. No complete TRISO coating layer failures were observed after 300 h at 1600 or 1700 °C, and 85Kr release was very low during the tests (particles with failed SiC, but intact outer pyrocarbon, retained most of their krypton). Krypton release from TRISO failures was only observed after ~210 h at 1800 °C in one compact. As a result, post-safety-test examination of fuel compacts and particles has focused on identifying specific particles from each compact with notable fission product release and detailed analysis of the coating

  13. Performance of AGR-1 high-temperature reactor fuel during post-irradiation heating tests

    DOE PAGES

    Morris, Robert N.; Baldwin, Charles A.; Demkowicz, Paul A.; ...

    2016-05-18

    The fission product retention of irradiated low-enriched uranium oxide/uranium carbide tri-structural isotropic (TRISO) fuel compacts from the Advanced Gas-Cooled Reactor 1 (AGR-1) experiment has been evaluated at temperatures of 1600–1800 °C during post-irradiation safety tests. Fourteen compacts (a total of ~58,000 particles) with a burnup ranging from 13.4% to 19.1% fissions per initial metal atom (FIMA) have been tested using dedicated furnace systems at Idaho National Laboratory and Oak Ridge National Laboratory. The release of fission products 110mAg, 134Cs, 137Cs, 154Eu, 155Eu, 90Sr, and 85Kr was monitored while heating the fuel specimens in flowing helium. The behavior of silver, europium,more » and strontium appears to be dominated by inventory that was originally released through intact SiC coating layers during irradiation, but was retained in the compact at the end of irradiation and subsequently released during the safety tests. However, at a test temperature of 1800 °C, the data suggest that release of these elements through intact coatings may become significant after ~100 h. Cesium was very well retained by intact SiC layers, with a fractional release <5 × 10–6 after 300 h at 1600 °C or 100 h at 1800 °C. However, it was rapidly released from individual particles if the SiC layer failed, and therefore the overall cesium release fraction was dominated by the SiC defect and failure fractions in the fuel compacts. No complete TRISO coating layer failures were observed after 300 h at 1600 or 1700 °C, and 85Kr release was very low during the tests (particles with failed SiC, but intact outer pyrocarbon, retained most of their krypton). Krypton release from TRISO failures was only observed after ~210 h at 1800 °C in one compact. As a result, post-safety-test examination of fuel compacts and particles has focused on identifying specific particles from each compact with notable fission product release and detailed analysis of the coating layers

  14. Performance of AGR-1 High-Temperature Reactor Fuel During Post-Irradiation Heating Tests

    SciTech Connect

    Morris, Robert Noel; Baldwin, Charles A; Hunn, John D; Demkowicz, Paul; Reber, Edward

    2014-01-01

    The fission product retention of irradiated low-enriched uranium oxide/uranium carbide TRISO fuel compacts from the AGR-1 experiment has been evaluated at temperatures of 1600 1800 C during post-irradiation safety tests. Fourteen compacts (a total of ~58,000 particles) with a burnup ranging from 13.4 to 19.1% FIMA have been tested using dedicated furnace systems at Idaho National Laboratory and Oak Ridge National Laboratory. The release of fission products 110mAg, 134Cs, 137Cs, 154Eu, 155Eu, 90Sr, and 85Kr was monitored while heating the fuel specimens in flowing helium. The behavior of silver, europium, and strontium appears to be dominated by inventory that was originally released through intact SiC coating layers during irradiation, but was retained in the compact at the end of irradiation and subsequently released during the safety tests. However, at a test temperature of 1800 C, the data suggest that release of these elements through intact coatings may become significant after ~100 h. Cesium was very well retained by intact SiC layers, with a fractional release <5 10-6 after 300 h at 1600 C or 100 h at 1800 C. However, it was rapidly released from individual particles if the SiC layer failed, and therefore the overall cesium release fraction was dominated by the SiC defect and failure fractions in the fuel compacts. No complete TRISO coating layer failures were observed after 300 h at 1600 or 1700 C, and 85Kr release was very low during the tests (particles with breached SiC, but intact outer pyrocarbon, retained most of their krypton). Krypton release from TRISO failures was only observed after ~210 h at 1800 C in one compact. Post-safety-test examination of fuel compacts and particles has focused on identifying specific particles from each compact with notable fission product release and detailed analysis of the coating layers to understand particle behavior.

  15. Peculiarities of post-irradiation annealing of MgO crystals

    NASA Astrophysics Data System (ADS)

    Kvatchadze, V. G.; Kalabegishvili, T. L.; Abramishvili, M. G.; Akhvlediani, Z. G.; Galustashvili, M. V.; Garibashvili, K. I.

    The influence of high-temperature annealing on absorption spectra of nominally pure and impure MgO crystals irradiated in a nuclear reactor has been investigated. In nominally pure crystals, as a whole, the accumulation of defect aggregates of non-monotonous character takes place during the whole cycle of the action of radiation plus post-irradiation annealing: the creation of defects in the process of irradiation, their destruction by annealing at 700 °C and repeated creation at higher annealing temperature. In irradiated impure crystals, where the mentioned defects exist in larger quantities, their thermal reanimation is not observed after the decay at 700 °C.

  16. Molecular structure effects on the post irradiation diffusion in polymer gel dosimeters.

    PubMed

    Mattea, Facundo; Romero, Marcelo R; Vedelago, José; Quiroga, Andrés; Valente, Mauro; Strumia, Miriam C

    2015-06-01

    Polymer gel dosimeters have specific advantages for recording 3D radiation dose distribution in diagnostic and therapeutic medical applications. But, even in systems where the 3D structure is usually maintained for long periods of time after irradiation, it is still not possible to eliminate the diffusion of the different species in the regions of dose gradients within the gel. As a consequence, information of the dose loses quality over time. In the pursuit of a solution and to improve the understanding of this phenomenon a novel system based on itaconic acid and N-N'-methylene-bisacrylamide (BIS) is hereby proposed. Effects of changes in the chemical structure of the monomers over the dosimetric sensitivity and over the post-irradiation diffusion of species was studied. In this study, one of the carboxylic groups of the itaconic acid molecule was modified with aniline to obtain molecules with similar reactivity but different molecular sizes. Then, dosimeters based on these modified species and on the original ITA molecules were irradiated in an X-ray tomography apparatus at different doses up to 173Gy. Afterwards, the resulting dosimeters were characterized by Raman spectroscopy and optical absorbance in order to study their feasibility and capabilities as dosimetric systems, and by optical-CT to analyze the post irradiation diffusion. Copyright © 2015 Elsevier Ltd. All rights reserved.

  17. Fast Flux Test Facility interim examination and maintenance cell: Past, present, and future

    SciTech Connect

    Vincent, J.R.

    1990-09-01

    The Fast Flux Test Facility Interim Examination and Maintenance Cell was designed to perform interim examination and/or disassembly of experimental core components for final analysis elsewhere, as well as maintenance of sodium-wetted or neutron-activated internal reactor parts and plant support hardware. The Interim Examination and Maintenance Cell equipment developed and used for the first ten years of operation has been primarily devoted to the disassembly and examination of core component test assemblies. While no major reactor equipment has required remote repair or maintenance, the Interim Examina Examination and Maintenance Cell has served as the remote repair facility for its own in-cell equipment, and several innovative remote repairs have been accomplished. The Interim Examination and Maintenance Cell's demonstrated versatility has shown its capability to support a challenging future. 12 refs., 9 figs.

  18. Stability of uncapped gold nanoparticles produced by laser ablation in deionized water: The effect of post-irradiation

    NASA Astrophysics Data System (ADS)

    Kim, Kuk Ki; Kwon, Hye Jin; Shin, Seung Keun; Song, Jae Kyu; Park, Seung Min

    2013-11-01

    Gold nanoparticle (AuNP) solution prepared by laser ablation in liquid (LAL) was irradiated by ns laser pulses to investigate the wavelength dependence on the size distribution of AuNPs and long-term stability of post-irradiated AuNP solutions. We have employed 266, 355, 532, and 1064 nm lasers for post-irradiation source and found considerable wavelength dependence in the size distribution and stability of laser-generated AuNPs. Post-irradiation at 355 nm was most effective to reduce the size distribution and to enhance the stability. The classical Derjaguin-Landau-Verwey-Overbeek theory was employed to explain the anomalous stability at 355 nm.

  19. 42 CFR 476.88 - Examination of the operations and records of health care facilities and practitioners.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... care facilities and practitioners. 476.88 Section 476.88 Public Health CENTERS FOR MEDICARE & MEDICAID... health care facilities and practitioners. (a) Authorization to examine records. A facility claiming...— (i) DRG validation; (ii) Outlier review in facilities under a prospective payment system; and (iii...

  20. Post-irradiation dietary vitamin E does not affect the development of radiation-induced lung damage in rats.

    PubMed

    Wiegman, Erwin M; van Gameren, Mieke M; Kampinga, Harm H; Szabó, Ben G; Coppes, Rob P

    2004-07-01

    The purpose of this study was to investigate whether application of post-irradiation vitamin E, an anti-oxidant, could prevent the development of radiation induced lung damage. Wistar rats were given vitamin E enriched or vitamin E deprived food starting from 4 weeks after 18Gy single dose irradiation of the right thorax. Neither breathing frequencies nor CT density measurements revealed differences between the groups. It is concluded that post-irradiation vitamin E does not influence radiation-induced fibrosis to the lung.

  1. Proposed power upgrade of the Hot Fuel Examination Facility's neutron radiography reactor. [NRAD reactor

    SciTech Connect

    Pruett, D.P.; Richards, W.J.; Heidel, C.C.

    1984-01-01

    The Hot Fuel Examination Facility, HFEF, is one of several facilities located at the Argonne Site. HFEF comprises a large hot cell where both non-destructive and destructive examination of highly-irradiated reactor fuels are conducted in support of the LMFBR program. One of the non-destructive examination techniques utilized at HFEF is neutron radiography. Neutron radiography is provided by the NRAD reactor facility, which is located beneath the HFEF hot cell. The NRAD reactor is a TRIGA reactor and is operated at a steady state power level of 250 kW solely for neutron radiography and the development of radiography techniques. When the NRAD facility was designed and constructed, an operating power level of 250 kW was considered to be adequate for obtaining radiographs of the type of specimens envisaged at that time. A typical radiograph required approximately a twenty-minute exposure time. Specimens were typically single fuel rods placed in an aluminum tray. Since that time, however, several things have occurred that have tended to increase radiography exposure times to as much as 90 minutes each. In order to decrease exposure times, the reactor power level is to be increased from 250 kw to 1 MW. This increase in power will necessitate several engineering and design changes. These changes are described.

  2. Older women's attitudes towards breast disease, self examination, and screening facilities: implications for communication.

    PubMed Central

    Leathar, D S; Roberts, M M

    1985-01-01

    Qualitative research techniques were used in two studies in Edinburgh to explore older women's attitudes and motivations towards breast disease, self examination, and screening, with a view to identifying appropriate strategies for communication. The results indicated that knowledge of breast disease and screening facilities was poor and that many psychological and emotional issues inhibited self examination. Increasing information about self examination and clinics is unlikely to influence uptake unless it is presented together with emotional support rather than through conventional mass media channels. Such support may best be provided by setting breast screening within general health screening rather than emphasising the single disease. PMID:3918709

  3. Improving Thermal Model Prediction Through Statistical Analysis of Irradiation and Post-Irradiation Data from AGR Experiments

    SciTech Connect

    Dr. Binh T. Pham; Grant L. Hawkes; Jeffrey J. Einerson

    2012-10-01

    As part of the Research and Development program for Next Generation High Temperature Reactors (HTR), a series of irradiation tests, designated as Advanced Gas-cooled Reactor (AGR), have been defined to support development and qualification of fuel design, fabrication process, and fuel performance under normal operation and accident conditions. The AGR tests employ fuel compacts placed in a graphite cylinder shrouded by a steel capsule and instrumented with thermocouples (TC) embedded in graphite blocks enabling temperature control. The data representing the crucial test fuel conditions (e.g., temperature, neutron fast fluence, and burnup) while impossible to obtain from direct measurements are calculated by physics and thermal models. The irradiation and post-irradiation examination (PIE) experimental data are used in model calibration effort to reduce the inherent uncertainty of simulation results. This paper is focused on fuel temperature predicted by the ABAQUS code’s finite element-based thermal models. The work follows up on a previous study, in which several statistical analysis methods were adapted, implemented in the NGNP Data Management and Analysis System (NDMAS), and applied for improving qualification of AGR-1 thermocouple data. The present work exercises the idea that the abnormal trends of measured data observed from statistical analysis may be caused by either measuring instrument deterioration or physical mechanisms in capsules that may have shifted the system thermal response. As an example, the uneven reduction of the control gas gap in Capsule 5 revealed by the capsule metrology measurements in PIE helps justify the reduction in TC readings instead of TC drift. This in turn prompts modification of thermal model to better fit with experimental data, thus help increase confidence, and in other word reduce model uncertainties in thermal simulation results of the AGR-1 test.

  4. Improving Thermal Model Prediction Through Statistical Analysis of Irradiation and Post-Irradiation Data from AGR Experiments

    SciTech Connect

    Binh T. Pham; Grant L. Hawkes; Jeffrey J. Einerson

    2014-05-01

    As part of the High Temperature Reactors (HTR) R&D program, a series of irradiation tests, designated as Advanced Gas-cooled Reactor (AGR), have been defined to support development and qualification of fuel design, fabrication process, and fuel performance under normal operation and accident conditions. The AGR tests employ fuel compacts placed in a graphite cylinder shrouded by a steel capsule and instrumented with thermocouples (TC) embedded in graphite blocks enabling temperature control. While not possible to obtain by direct measurements in the tests, crucial fuel conditions (e.g., temperature, neutron fast fluence, and burnup) are calculated using core physics and thermal modeling codes. This paper is focused on AGR test fuel temperature predicted by the ABAQUS code's finite element-based thermal models. The work follows up on a previous study, in which several statistical analysis methods were adapted, implemented in the NGNP Data Management and Analysis System (NDMAS), and applied for qualification of AGR-1 thermocouple data. Abnormal trends in measured data revealed by the statistical analysis are traced to either measuring instrument deterioration or physical mechanisms in capsules that may have shifted the system thermal response. The main thrust of this work is to exploit the variety of data obtained in irradiation and post-irradiation examination (PIE) for assessment of modeling assumptions. As an example, the uneven reduction of the control gas gap in Capsule 5 found in the capsule metrology measurements in PIE helps identify mechanisms other than TC drift causing the decrease in TC readings. This suggests a more physics-based modification of the thermal model that leads to a better fit with experimental data, thus reducing model uncertainty and increasing confidence in the calculated fuel temperatures of the AGR-1 test.

  5. 42 CFR 476.88 - Examination of the operations and records of health care facilities and practitioners.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... care facilities and practitioners. 476.88 Section 476.88 Public Health CENTERS FOR MEDICARE & MEDICAID... health care facilities and practitioners. (a) Authorization to examine records. A facility claiming... information on charges) that are pertinent to health care services furnished to Medicare beneficiaries and are...

  6. 42 CFR 476.88 - Examination of the operations and records of health care facilities and practitioners.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... care facilities and practitioners. 476.88 Section 476.88 Public Health CENTERS FOR MEDICARE & MEDICAID... health care facilities and practitioners. (a) Authorization to examine records. A facility claiming... information on charges) that are pertinent to health care services furnished to Medicare beneficiaries and are...

  7. 42 CFR 476.88 - Examination of the operations and records of health care facilities and practitioners.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... care facilities and practitioners. 476.88 Section 476.88 Public Health CENTERS FOR MEDICARE & MEDICAID... health care facilities and practitioners. (a) Authorization to examine records. A facility claiming... information on charges) that are pertinent to health care services furnished to Medicare beneficiaries and are...

  8. Neutron, gamma ray and post-irradiation thermal annealing effects on power semiconductor switches

    SciTech Connect

    Schwarze, G.E.; Frasca, A.J.

    1994-09-01

    The effects of neutrons and gamma rays on the electrical and switching characteristics of power semiconductor switches must be known and understood by the designer of the power conditioning, control, and transmission subsystem of space nuclear power systems. The SP-100 radiation requirements at 25 m from the nuclear source are a neutron fluence of 10{sup 13} n/cm {sup 2} and a gamma dose of 0.5 Mrads. Experimental data showing the effects of neutrons and gamma rays on the performance characteristics of power-type NPN Bipolar Junction Transistors (BJTs), Metal-Oxide-Semiconductor Field Effect Transistors (MOSFETs), and Static Induction Transistors (SITs) are given in this paper. These three types of devices were tested at radiation levels which met or exceeded the SP-100 requirements. For the SP-100 radiation requirements, the BJTs were found to be most sensitive to neutrons, the MOSFETs were most sensitive to gamma rays, and the SITs were only slightly sensitive to neutrons. Post-irradiation thermal anneals at 300 K and up to 425 K were done on these devices and the effectiveness of these anneals are also discussed.

  9. Modeling plastic deformation of post-irradiated copper micro-pillars

    NASA Astrophysics Data System (ADS)

    Crosby, Tamer; Po, Giacomo; Ghoniem, Nasr M.

    2014-12-01

    We present here an application of a fundamentally new theoretical framework for description of the simultaneous evolution of radiation damage and plasticity that can describe both in situ and ex situ deformation of structural materials [1]. The theory is based on the variational principle of maximum entropy production rate; with constraints on dislocation climb motion that are imposed by point defect fluxes as a result of irradiation. The developed theory is implemented in a new computational code that facilitates the simulation of irradiated and unirradiated materials alike in a consistent fashion [2]. Discrete Dislocation Dynamics (DDD) computer simulations are presented here for irradiated fcc metals that address the phenomenon of dislocation channel formation in post-irradiated copper. The focus of the simulations is on the role of micro-pillar boundaries and the statistics of dislocation pinning by stacking-fault tetrahedra (SFTs) on the onset of dislocation channel and incipient surface crack formation. The simulations show that the spatial heterogeneity in the distribution of SFTs naturally leads to localized plastic deformation and incipient surface fracture of micro-pillars.

  10. Neutron, gamma ray and post-irradiation thermal annealing effects on power semiconductor switches

    NASA Technical Reports Server (NTRS)

    Schwarze, G. E.; Frasca, A. J.

    1991-01-01

    The effects of neutron and gamma rays on the electrical and switching characteristics of power semiconductor switches must be known and understood by the designer of the power conditioning, control, and transmission subsystem of space nuclear power systems. The SP-100 radiation requirements at 25 m from the nuclear source are a neutron fluence of 10(exp 13) n/sq cm and a gamma dose of 0.5 Mrads. Experimental data showing the effects of neutrons and gamma rays on the performance characteristics of power-type NPN Bipolar Junction Transistors (BJTs), Metal-Oxide-Semiconductor Field Effect Transistors (MOSFETs), and Static Induction Transistors (SITs) are presented. These three types of devices were tested at radiation levels which met or exceeded the SP-100 requirements. For the SP-100 radiation requirements, the BJTs were found to be most sensitive to neutrons, the MOSFETs were most sensitive to gamma rays, and the SITs were only slightly sensitive to neutrons. Post-irradiation thermal anneals at 300 K and up to 425 K were done on these devices and the effectiveness of these anneals are also discussed.

  11. Caspase 3 in dying tumor cells mediates post-irradiation angiogenesis

    PubMed Central

    Zhang, Zhengxiang; Yu, Yang; Cheng, Jin; Gong, Yanping; Li, Chuan-Yuan; Huang, Qian

    2015-01-01

    Cytotoxic radiotherapy unfavorably induces tumor cells to generate various proangiogenic substances, promoting post-irradiation angiogenesis (PIA), which is one of major causes of radiotherapy failure. Though several studies have reported some mechanisms behind PIA, they have not yet described the beginning proangiogenic motivator buried in the irradiated microenvironment. In this work, we revealed that dying tumor cells induced by irradiation prompted PIA via a caspase 3 dependent mechanism. Proteolytic inactivation of caspase 3 in dying tumor cells by transducing a dominant-negative version weakened proangiogenic effects in vitro and in vivo. In addition, inhibition of caspase 3 activity suppressed tumor angiogenesis and tumorigenesis in xenograft mouse model. Importantly, we identified vascular endothelial growth factor (VEGF)-A as a downstream proangiogenic factor regulated by caspase 3 possibly through Akt signaling. Collectively, these findings indicated that besides acting as a key executioner in apoptosis, caspase 3 in dying tumor cells may play a central role in driving proangiogenic response after irradiation. Thus, radiotherapy in combination with caspase 3 inhibitors may be a novel promising therapeutic strategy to reduce tumor recurrence due to restrained PIA. PMID:26431328

  12. Recovery from Hematopoietic Injury by Modulating Prostaglandin E2 Signaling Post-Irradiation

    PubMed Central

    Hoggatt, Jonathan; Singh, Pratibha; Stilger, Kayla N.; Plett, P. Artur; Sampson, Carol H.; Chua, Hui Lin; Orschell, Christie M.; Pelus, Louis M.

    2012-01-01

    While high dose total body irradiation (TBI) is used therapeutically, the proliferation of nuclear weapons, increasing use of nuclear power, and worldwide radical terrorism underscore the need to develop countermeasures to a radiological mass casualty event. The hematopoietic syndrome of the acute radiation syndrome (HS-ARS) results from severe compromise to the hematopoietic system, including lymphocytopenia, neutropenia, thrombocytopenia, and possible death from infection and/or hemorrhage. Given adequate time to recover, expand, and appropriately differentiate, bone marrow hematopoietic stem cells (HSC) and progenitor cells (HPC) may overcome HS-ARS and restore homeostasis of the hematopoietic system. Prostaglandin E2 (PGE2) has been shown to have pleiotropic effects on hematopoiesis, acting to inhibit apoptosis and promote self-renewal of HSC, while inhibiting HPC proliferation. We assessed the radio-mitigating potential of modulating PGE2 signaling in a mouse model of HS-ARS. Treatment with the PGE2 analog 16,16 dimethyl PGE2 (dmPGE2) 6 hours post-irradiation or inhibition of PGE2 synthesis via delayed administration of the non-steroidal anti-inflammatory drug (NSAID) Meloxicam resulted in increased survival of lethally irradiated mice. Both early dmPGE2 and delayed Meloxicam treatment were associated with increased HPC activity 35 days following irradiation, demonstrating enhanced recovery of hematopoiesis. Our results define two different treatment modalities that are highly effective and safe to administer, and can be readily available. PMID:23206586

  13. Bacterial brain abscess formation in post-irradiated patients: What is the possible pathogenesis?

    PubMed

    Chuang, Jimmy Ming-Jung; Lin, Wei-Che; Fang, Fu-Min; Huang, Yu-Jie; Ho, Jih-Tsun; Lu, Cheng-Hsien

    2015-09-01

    Until recently, post-radiotherapy brain abscess was considered rare, but it has become an increasingly important aetiology. Discussions of the relationship between bacterial brain abscess and radiotherapy (RT) are rare in the literature. Our clinical study was conducted to analyse the role of RT in the pathogenesis of bacterial brain abscess. For our retrospective study, 146 patients with bacterial brain abscess were recruited. Ten patients with a history of RT before brain abscess formation were reviewed. Eight of these patients underwent RT treatment for nasopharyngeal carcinoma, one for olfactory neuroblastoma, and another for nasal plasmacytoma. Three showed presence of temporal lobe radiation necrosis neighbouring abscess. Eight patients were shown to have the evidence of tumour invasion. Seven had evidence of nasal infection or otitis media. Statistically significant differences between the RT and non-RT patients were observed for radionecrosis, bone defects between the middle fossa/sphenoid sinus, and the presence of nasal infection/otitis media. The mortality rate was 30%. This study shows possible pathogenesis of bacterial brain abscess formation in post-irradiated patients, which is complicated by both radiation effects and tumour effects. Skull base deficits (either from tumour erosion or osteonecrosis) and nasal/ear infection were significantly different in patients who received radiation vs. those who did not. Radiation-related temporal lobe necrosis was also a predisposing factor. Further study based on a proper patient cohort is warranted. Copyright © 2015 Elsevier B.V. All rights reserved.

  14. Engineering Task Plan for the Integrity Assessment Examination of Double Contained Receiver Tanks (DCRT) Catch Tanks and Ancillary facilities

    SciTech Connect

    BECKER, D.L.

    2000-05-23

    This Engineering Task Plan (ETP) presents the integrity assessment examination of three DCRTs, seven catch tanks, and two ancillary facilities located in the 200 East and West Areas of the Hanford Site. The integrity assessment examinations, as described in this ETP, will provide the necessary information to enable the independently qualified registered professional engineer (IQRPE) to assess the condition and integrity of these facilities. The plan is consistent with the Double-Shell Tank Waste Transfer Facilities Integrity Assessment Plan.

  15. 42 CFR 476.88 - Examination of the operations and records of health care facilities and practitioners.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... care facilities and practitioners. 476.88 Section 476.88 Public Health CENTERS FOR MEDICARE & MEDICAID... Functions § 476.88 Examination of the operations and records of health care facilities and practitioners. (a... examine its operation and records (including information on charges) that are pertinent to health care...

  16. REPORT OF THE WORKSHOP ON NUCLEAR FACILITY DESIGN INFORMATION EXAMINATION AND VERIFICATION FOR SAFEGUARDS

    SciTech Connect

    Richard Metcalf; Robert Bean

    2009-10-01

    Executive Summary The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA’s Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility’s general character, purpose, capacity, and location; (2) Description of the facility’s layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards

  17. Rat Models of Post-Irradiation Recovery of Spermatogenesis: Interstrain Differences

    PubMed Central

    Abuelhija, Mahmoud; Weng, Connie C.; Shetty, Gunapala; Meistrich, Marvin L.

    2012-01-01

    Recently we reported large differences between rat strains in spermatogenesis recovery at 10 weeks after 5-Gy irradiation suggesting that there are interstrain as well as interspecies differences in testicular radiation response. To determine whether these interstrain differences in sensitivity might be a result of the particular dose and time-point chosen, we performed dose-response and time-course studies on sensitive Brown-Norway (BN) and more resistant spontaneously hypertensive (SHR) and Sprague-Dawley (SD) rats. Type A spermatogonia were observed in atrophic tubules at 10 weeks after irradiation in all strains indicating that tubular atrophy was caused by a block in their differentiation, but the doses to produce the block ranged from 4.0 Gy in BN to 10 Gy in SD rats. Although the numbers of type A spermatogonial were unaffected at doses below 6 Gy, higher doses reduced their number, indicating that stem cell killing also contributed to the failure of recovery. After 10 weeks, there was no further recovery and even a decline in spermatogonial differentiation in BN rats, but in SHR rats, sperm production returned to control levels by 20 weeks after 5.0 Gy and, after 7.5 Gy, differentiation resumed in 60% of tubules by 30 weeks. Suppression of testosterone and gonadotropins after irradiation restored production of differentiated cells in nearly all tubules in BN rats and in all tubules in SHR rats. Thus the differences in recovery of spermatogenesis between strains were a result of both quantitative differences in their sensitivities to a radiation-induced, hormone-dependent block of spermatogonial differentiation and qualitative interstrain differences in the progression of post-irradiation recovery. The progression of recovery in SHR rats was similar to the prolonged delays in recovery of human spermatogenesis after cytotoxic agent exposure and thus may be a system for investigating a phenomenon also observed in men. PMID:23413134

  18. Evolution of the nanostructure of VVER-1000 RPV materials under neutron irradiation and post irradiation annealing

    NASA Astrophysics Data System (ADS)

    Miller, M. K.; Chernobaeva, A. A.; Shtrombakh, Y. I.; Russell, K. F.; Nanstad, R. K.; Erak, D. Y.; Zabusov, O. O.

    2009-04-01

    A high nickel VVER-1000 (15Kh2NMFAA) base metal (1.34 wt% Ni, 0.47% Mn, 0.29% Si and 0.05% Cu), and a high nickel (12Kh2N2MAA) weld metal (1.77 wt% Ni, 0.74% Mn, 0.26% Si and 0.07% Cu) have been characterized by atom probe tomography to determine the changes in the microstructure during neutron irradiation to high fluences. The base metal was studied in the unirradiated condition and after neutron irradiation to fluences between 2.4 and 14.9 × 10 23 m -2 ( E > 0.5 MeV), and the weld metal was studied in the unirradiated condition and after neutron irradiation to fluences between 2.4 and 11.5 × 10 23 m -2 ( E > 0.5 MeV). High number densities of ˜2-nm-diameter Ni-, Si- and Mn-enriched nanoclusters were found in the neutron irradiated base and weld metals. No significant copper enrichment was associated with these nanoclusters and no copper-enriched precipitates were observed. The number densities of these nanoclusters correlate with the shifts in the ΔT 41 J ductile-to-brittle transition temperature. These nanoclusters were present after a post irradiation anneal of 2 h at 450 °C, but had dissolved into the matrix after 24 h at 450 °C. Phosphorus, nickel, silicon and to a lesser extent manganese were found to be segregated to the dislocations.

  19. Evolution of the nanostructure OF VVER-1000 RPV materials under neutron irradiation and post irradiation annealing

    SciTech Connect

    Miller, Michael K; Chernobaeva, A. A.; Shtrombakh, Ya.; Erak, D.; Zabusov, Oleg O.; Russell, Kaye F; Nanstad, Randy K

    2009-01-01

    A high nickel VVER-1000 (15Kh2NMFAA) base metal (1.34 wt% Ni, 0.47% Mn, 0.29% Si and 0.05% Cu), and a high nickel (12Kh2N2MAA) weld metal (1.77 wt% Ni, 0.74% Mn, 0.26% Si and 0.07% Cu) have been characterized by atom probe tomography to determine the changes in the microstructure during neutron irradiation to high fluences. The base metal was studied in the unirradiated condition and after neutron irradiation to fluences between 2.4 and 14.9 x 10{sup 23} m{sup -2} (E > 0.5 MeV), and the weld metal was studied in the unirradiated condition and after neutron irradiation to fluences between 2.4 and 11.5 x 10{sup 23} m{sup -2} (E > 0.5 MeV). High number densities of 2-nm-diameter Ni-, Si- and Mn-enriched nanoclusters were found in the neutron irradiated base and weld metals. No significant copper enrichment was associated with these nanoclusters and no copper-enriched precipitates were observed. The number densities of these nanoclusters correlate with the shifts in the {Delta}T{sub 41 J} ductile-to-brittle transition temperature. These nanoclusters were present after a post irradiOffice of Science (US)C, but had dissolved into the matrix after 24 h at 450 C. Phosphorus, nickel, silicon and to a lesser extent manganese were found to be segregated to the dislocations.

  20. Examining the accuracy of visual diagnosis of tinea pedis and tinea unguium in aged care facilities.

    PubMed

    Goto, T; Nakagami, G; Takehara, K; Nakamura, T; Kawashima, M; Tsunemi, Y; Sanada, H

    2017-04-02

    The aim of this study was to examine the accuracy of visual diagnosis of tinea pedis (Athlete's foot) and tinea unguium (fungal nail infection), as well as to provide information on skin abnormalities that could help identify these diseases in aged care facilities (long-term care facilities (LTCFs) and nursing homes). A multicentre, cross-sectional observational study was conducted in a LTCF and two nursing homes. A dermatologist observed the skin abnormalities in the participants' interdigital and plantar areas, to screen for tinea pedis, and in the participants' toenails, to screen for tinea unguium. If abnormalities were noted, samples such as scales or toenails were collected and examined using direct microscopy. The accuracy of the macroscopic observation for each skin abnormality was examined. A total of 173 residents were recruited. The accuracy of clinical diagnosis using macroscopic observation was relatively low. The sensitivities and specificities for clinical diagnosis were 0.37 and 0.95 for tinea pedis in the interdigital areas, 0.47 and 0.94 for tinea pedis in the plantar areas, and 0.80 and 0.61 for tinea unguium in toenails, respectively. Scales in the plantar areas and discoloration of the toenails were more frequently observed in residents with tinea pedis and tinea unguium than in those without them. Several skin abnormalities were observed in the residents recruited in this study, but there was insufficient correlation with tinea pedis and tinea unguium to be used for screening.

  1. Fast Flux Test Facility interim examination and maintenance cell - past, present, and future

    SciTech Connect

    Vincent, J.R.

    1990-01-01

    The Fast Flux Test Facility (FFTF) interim examination and maintenance (IEM) cell was designed to perform interim examination and/or disassembly of experimental core components for final analysis elsewhere, as well as maintenance of sodium-wetted or neutron-activated internal reactor parts and plant support hardware. The first 10 yr of operation were mainly devoted to the disassembly and examination of core component test assemblies. While some maintenance was performed on reactor support equipment, such as the closed-loop ex-vessel machine (CLEM) sodium-wetted grapple, 90% of IEM cell availability has been devoted to core component tests. Some test assemblies originally considered for processing in the IEM cell have not been irradiated; others, not originally planned, have been designed, irradiated, and processed. While no major reactor equipment has required remote repair or maintenance, the IEM cell has served as the remote repair facility for its own in-cell equipment, and several innovative remote repairs have been accomplished and are described.

  2. Effects of ablation energy and post-irradiation on the structure and properties of titanium dioxide nanomaterials

    NASA Astrophysics Data System (ADS)

    Guillén, G. García; Shaji, S.; Palma, M. I. Mendivil; Avellaneda, D.; Castillo, G. A.; Roy, T. K. Das; Gutiérrez, D. I. García; Krishnan, B.

    2017-05-01

    Nanomaterials of titanium oxide were prepared by pulsed laser ablation of a titanium metal target in distilled water. The ablation was performed at different laser energy (fluence) using a nanosecond pulsed Nd:YAG laser output of 1064 and 532 nm. A post-irradiation of titanium oxide nanocolloids obtained by ablation using 532 nm was carried out to explore its effects on the structure and properties. Analysis of morphology, crystalline phase, elemental composition, chemical state, optical and luminescent properties were performed using Transmission Electron Microscopy (TEM), X-Ray Diffraction (XRD), X-Ray Photoelectron Spectroscopy (XPS), UV-vis absorption spectroscopy and room temperature photoluminescence spectroscopy. It was found that titanium oxide nanomaterial morphologies and optical properties were determined by ablation wavelength and fluence. Further, nanocolloids prepared by 532 nm ablation showed a crystalline phase change by laser post-irradiation. The results showed that pulsed laser ablation in liquid as well as post-irradiation were effective in modifying the final structure and properties of titanium oxide nanocolloids.

  3. Post-irradiation hardening of dual-cured and light-cured resin cements through machinable ceramics.

    PubMed

    Yoshida, Keiichi; Atsuta, Mitsuru

    2006-10-01

    To evaluate the surface hardness (Knoop Hardness Number) of the thin layer in three light-cured and dual-cured resin cements irradiated through or not through 2.0 mm thick machinable ceramics. A piece of adhesive polyethylene tape with a circular hole was positioned on the surface of the ceramic plate to control the cement layer (approximately 50 microm). The cement paste was placed on the ceramic surface within the circle. The ceramic plate with resin cement paste was placed on a clear micro cover glass over a zirconia ceramic block to obtain a flat surface, and the material was polymerized using a visible-light-curing unit. The surface hardness was recorded at a series of time intervals up to 5 days, starting from the end of a light-irradiation period. The hardness steadily increased with post-irradiation time and tended towards a maximum, usually reached after 1 or 2 days. In all cases, the increase in hardness was relatively rapid over the first 30 minutes and continued at a lower rate thereafter. The dual-cured resin cement for each material showed a significantly higher hardness value than the light-cured resin cement irradiated either through or not through ceramics at all post-irradiation times. The resin cements cured through ceramic for each material were significantly less hard compared with those cured not through ceramics at all post-irradiation times.

  4. Effect of neutron irradiation and post-irradiation annealing on microstructure and mechanical properties of OFHC-copper

    NASA Astrophysics Data System (ADS)

    Singh, B. N.; Edwards, D. J.; Toft, P.

    2001-12-01

    Specimens of oxygen-free high conductivity (OFHC) copper were irradiated in the DR-3 reactor at Risø at 100 °C to doses in the range 0.01-0.3 dpa (NRT). Some of the specimens were tensile tested in the as-irradiated condition at 100 °C whereas others were given a post-irradiation annealing treatment at 300 °C for 50 h and subsequently tested at 100 °C. The microstructure of specimens was characterized in the as-irradiated as well as irradiated and annealed conditions both before and after tensile deformation. While the interstitial loop microstructure coarsens with irradiation dose, no significant changes were observed in the population of stacking fault tetrahedra (SFT). The post-irradiation annealing leads to only a partial recovery and the level of recovery depends on the irradiation dose level. However, the post-irradiation annealing eliminates the yield drop and reinstates enough uniform elongation to render the material useful again. These results are discussed in terms of the cascade-induced source hardening (CISH) model.

  5. The neighborhood recreational environment and physical activity among urban youth: an examination of public and private recreational facilities.

    PubMed

    Ries, Amy V; Yan, Alice F; Voorhees, Carolyn C

    2011-08-01

    Recreational facility availability has been shown to associate positively with youth physical activity levels. Nonetheless, little is known about additional facility characteristics affecting their use for physical activity as well as differences between private and public facilities. This study examines (1) perceptions and use of public and private recreational facilities and (2) environmental and individual-level correlates of both facility use and physical activity among urban adolescents. Physical activity was assessed using accelerometry, objective measures of facility availability were obtained using Geographical Information Systems data, and facility use and perceptions were measured with a survey (N = 327). Adolescents were more likely to use public than private facilities despite perceiving that private facilities were of higher quality. Adolescents' use of both public and private facilities was associated with perceived (but not objective) availability, perceived quality, and use by friends and family. Public, but not private, facility use was associated with physical activity. This study reveals the importance of public facilities to the physical activity of urban youth.

  6. Examination of Listeria monocytogenes in Seafood Processing Facilities and Smoked Salmon in the Republic of Ireland.

    PubMed

    Leong, Dara; Alvarez-Ordóñez, Avelino; Zaouali, Sarah; Jordan, Kieran

    2015-12-01

    Listeria monocytogenes is a foodborne pathogen that causes listeriosis, a relatively rare but life-threatening disease primarily affecting immunocompromised individuals. The aim of this study was to determine the prevalence of L. monocytogenes in the seafood processing industry in the Republic of Ireland. The occurrence of L. monocytogenes was determined by regular sampling of both food samples and processing environment swabs at eight seafood processing facilities over two calendar years. All samples were analyzed by the International Organization for Standardization 11290-1 standard method, and the isolates were characterized by PCR, pulsed-field gel electrophoresis, serotyping, and the occurrence of some genes related to survival under stress (SSI-1, Tn6188, and bcrABC). A prevalence of 2.5% in 508 samples (433 environmental swabs and 75 food samples) was found. From the isolates obtained, eight different pulsed-field gel electrophoresis profiles were identified, two occurring in more than one facility and one occurring in food and the environment. Five of the eight pulsotypes identified contained at least one of the three stress survival-related genes tested. The tolerance of the isolates to benzalkonium chloride, a representative quaternary ammonium compound, was also examined and ranged from 5.5 ± 0.5 to 8.5 ± 0.5 ppm of benzalkonium chloride. To evaluate the ability of smoked salmon to support the growth of L. monocytogenes, including the T4 widespread pulsotype that was isolated, a challenge test was performed on cold-smoked salmon obtained from two separate producers. The results showed clearly that both types of smoked salmon supported the growth of L. monocytogenes. Although occurrence of L. monocytogenes on seafood was low, this study showed that the smoked salmon used in this study can support the growth of L. monocytogenes; therefore, vigilance is required in the processing facilities to reduce the associated risk.

  7. Multilevel examination of facility characteristics, social integration, and health for older adults living in nursing homes.

    PubMed

    Leedahl, Skye N; Chapin, Rosemary K; Little, Todd D

    2015-01-01

    Testing a model based on past research and theory, this study assessed relationships between facility characteristics (i.e., culture change efforts, social workers) and residents' social networks and social support across nursing homes; and examined relationships between multiple aspects of social integration (i.e., social networks, social capital, social engagement, social support) and mental and functional health for older adults in nursing homes. Data were collected at nursing homes using a planned missing data design with random sampling techniques. Data collection occurred at the individual-level through in-person structured interviews with older adult nursing home residents (N = 140) and at the facility-level (N = 30) with nursing home staff. The best fitting multilevel structural equation model indicated that the culture change subscale for relationships significantly predicted differences in residents' social networks. Additionally, social networks had a positive indirect relationship with mental and functional health among residents primarily via social engagement. Social capital had a positive direct relationship with both health outcomes. To predict better social integration and mental and functional health outcomes for nursing homes residents, study findings support prioritizing that close relationships exist among staff, residents, and the community as well as increased resident social engagement and social trust. © The Author 2014. Published by Oxford University Press on behalf of The Gerontological Society of America. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  8. HOLDUP MEASUREMENTS FOR THREE VISUAL EXAMINATION AND TRU REMEDIATION GLOVEBOX FACILITIES AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Dewberry, R; Donald Pak, D

    2007-05-04

    Visual Examination (VE) gloveboxes are used to remediate transuranic waste (TRU) drums at three separate facilities at the Savannah River Site. Noncompliant items are removed before the drums undergo further characterization in preparation for shipment to the Waste Isolation Pilot Plant (WIPP). Maintaining the flow of drums through the remediation process is critical to the program's seven-days-per-week operation. Conservative assumptions are used to ensure that glovebox contamination from this continual operation is below acceptable limits. Holdup measurements using cooled HPGe spectrometers are performed in order to confirm that these assumptions are conservative. {sup 239}Pu is the main nuclide of interest; however, {sup 241}Pu, equilibrium {sup 237}Np/{sup 233}Pa and {sup 238}Pu (if detected) are typically assayed. At the Savannah River National Laboratory (SRNL) facility {sup 243,244,245}Cm are also generally observed and are always reported at either finite levels or at limits of detection. A complete assay at each of the three facilities includes a measure of TRU content in the gloveboxes and HEPA filters in the glovebox exhaust. This paper includes a description of the {gamma}-PHA acquisitions, of the modeling, and of the calculations of nuclide content. Because each of the remediation facilities is unique and ergonomically unfavorable to {gamma}-ray acquisitions, we have constructed custom detector support devices specific to each set of acquisitions. This paper includes a description and photographs of these custom devices. The description of modeling and calculations include determination and application of container and matrix photon energy dependent absorption factors and also determination and application of geometry factors relative to our detector calibration geometry. The paper also includes a discussion of our measurements accuracy using off-line assays of two SRNL HEPA filters. The comparison includes assay of the filters inside of 55-gallon

  9. Effect of the hydrolytic state of dietary protein on post-irradiation morbidity and mucosal cell regeneration

    SciTech Connect

    Beitler, M.K.; Mahler, P.A.; Yamanaka, W.K.; Guy, D.G.; Hutchinson, M.L.

    1987-03-01

    Diets containing hydrolyzed casein have been observed to enhance post-irradiation intestinal mucosal recovery. The intake and the composition of such diets were not carefully controlled. This study attempted to do so. Male specific pathogen-free Sprague-Dawley rats were randomized to receive either an enzymatically hydrolyzed casein semi-purified diet (EHC), a whole casein semi-purified diet (WC), or powdered lab chow (C). All diets were isonitrogenous, and the WC and C rats were pair-fed to the ad libitum fed EHC rats. Seven days after initiation of feeding, the rats were abdominally irradiated with a single 9.0 Gy dose of 137Cs gamma rays. The rats were continued on the diets for another 5 days. Intestinal mucosa from transverse segments at the duodenum, jejunum, proximal ileum, and distal ileum were measured for incorporation of (/sup 3/H methyl) thymidine 1 hour after intraperitoneal injection. Incorporation reached a maximum by day 4 post-irradiation regardless of diet or segment. Incorporation in the duodenum was enhanced by the EHC diet compared to the C diet, while the incorporation in the jejunum was initially suppressed by the EHC diet compared to the WC diet. In the jejunum, the number of mitoses per crypt of 25 anti-mesenteric crypts post-irradiation was increased by the EHC diet. Prior to irradiation, all groups gained similar amounts of weight. After irradiation, the C rats lost weight, while the EHC and WC rats remained the same or gained weight. Guaiac tests for occult blood were negative prior to irradiation, but positive for all rats on days 1-5 postirradiation. When calorie and protein intakes were controlled, different areas of the small intestine responded differently to EHC.

  10. Examining the Association between Hazardous Waste Facilities and Rural "Brain Drain"

    ERIC Educational Resources Information Center

    Hunter, Lori M.; Sutton, Jeannette

    2004-01-01

    Rural communities are increasingly being faced with the prospect of accepting facilities characterized as "opportunity-threat," such as facilities that generate, treat, store, or otherwise dispose of hazardous wastes. Such facilities may offer economic gains through jobs and tax revenue, although they may also act as environmental "disamenities."…

  11. Examining the Association between Hazardous Waste Facilities and Rural "Brain Drain"

    ERIC Educational Resources Information Center

    Hunter, Lori M.; Sutton, Jeannette

    2004-01-01

    Rural communities are increasingly being faced with the prospect of accepting facilities characterized as "opportunity-threat," such as facilities that generate, treat, store, or otherwise dispose of hazardous wastes. Such facilities may offer economic gains through jobs and tax revenue, although they may also act as environmental "disamenities."…

  12. Post-irradiation Examination Plan for ORNL and University of California Santa Barbara Assessment of UCSB ATR-2 Irradiation Experiment

    SciTech Connect

    Nanstad, R. K.; Yamamoto, T.; Sokolov, M. A.

    2014-01-25

    New and existing databases will be combined to support development of physically based models of transition temperature shifts (TTS) for high fluence-low flux (φ < 10{sup 11}n/cm{sup 2}-s) conditions, beyond the existing surveillance database, to neutron fluences of at least 1×10{sup 20} n/cm{sup 2} (>1 MeV). All references to neutron flux and fluence in this report are for fast neutrons (>1 MeV). The reactor pressure vessel (RPV) task of the Light Water Reactor Sustainability (LWRS) Program is working with various organizations to obtain archival surveillance materials from commercial nuclear power plants to allow for comparisons of the irradiation-induced microstructural features from reactor surveillance materials with those from similar materials irradiated under high flux conditions in test reactors

  13. Gamma-tocopherol-N,N-dimethylglycine ester as a potent post-irradiation mitigator against whole body X-irradiation-induced bone marrow death in mice.

    PubMed

    Anzai, Kazunori; Ueno, Megumi; Matsumoto, Ken-Ichiro; Ikota, Nobuo; Takata, Jiro

    2014-01-01

    We examined the radioprotective and mitigative effects of gamma-tocopherol-N,N-dimethylglycine ester (GTDMG), a novel water-soluble gamma-tocopherol derivative, against X-irradiation-induced bone marrow death in mice. Mice (C3H, 10 weeks, male) were injected intraperitoneally with GTDMG suspended in a 0.5% methyl cellulose solution before or after receiving of 7.5-Gy whole body X-irradiation. GTDMG significantly enhanced the 30-day survival rate when given 30 min before or immediately after the irradiation. Its mitigative activity (administered after exposure) was examined further in detail. The optimal concentration of GTDMG given immediately after irradiation was around 100 mg/kg body weight (bw) and the 30-day survival rate was 97.6 ± 2.4%. When GTDMG was administered 1, 10 and 24 h post-irradiation, the survival rate was 85.7 ± 7.6, 75.0 ± 9.7 and 36.7 ± 8.8%, respectively, showing significant mitigation even at 24 h after irradiation (P < 0.05). The value of the dose reduction factor (100 mg/kg bw, given intraperitoneally (i.p.) immediately after irradiation) was 1.25. GTDMG enhanced the recovery of red blood cell-, white blood cell-, and platelet-counts after irradiation and significantly increased the number of endogenous spleen colonies (P < 0.05). Subcutaneous (s.c.) administration also had mitigative effects. In conclusion, GTDMG is a potent radiation mitigator.

  14. THE INFLUENCE OF PRE- AND POST-IRRADIATION ANNEALING ON LiF:Mg,Cu,P STABILITY.

    PubMed

    Matusiak, Katarzyna; Patora, Aneta; Jung, Aleksandra

    2016-11-01

    The influence of pre- and post-irradiation annealing procedures on LiF:Mg,Cu,P (trade name MCP-N) thermoluminescent detector stability was investigated. The detectors were processed in four groups, undergoing complete or incomplete preparation cycles (containing pre- and/or post-irradiation annealing in various combinations). Each cycle was repeated 10 times. The decrease in the stability was observed in groups with pre-irradiation annealing procedure, and not observed in other groups that were found to be apparently stable. The influence of the thermal history on the properties of the detectors was also investigated by swapping the chosen groups of detectors with respect to the annealing cycles. Changes in the properties of the detectors were observed after next 10 cycles of measurements too. Exponential model was proposed to describe the trends observed at two parts of the experiment. Its application for the dose corrections related to the cycle number of the readout improves the accuracy of final dose determination. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  15. Measurement of Volatile Radionuclides Production and Release Yields followed by a Post-Irradiation Analysis of a Pb/Bi Filled Ta Target at ISOLDE

    NASA Astrophysics Data System (ADS)

    Zanini, L.; Köster, U.; David, J. C.; Tall, Y.; Andersson, M.; Berg, K.; Cormon, S.; Fallot, M.; Foucher, Y.; Frånberg, H.; Gröschel, F.; Guertin, A.; Kirchner, T.; Leray, S.; Manfrin, E.; Noah, E.; Ravn, H.; Stora, T.; Thiollière, N.; Wohlmuther, M.

    2014-05-01

    A crucial requirement in the development of liquid-metal spallation neutron target is knowledge of the composition and amount of volatile radionuclides that are released from the target during operation. It is also important to know the total amount produced, which could be released if there was an accident. One type is the lead-bismuth eutectic (LBE) target where different radionuclides can be produced following interaction with a high-energy proton beam, notably noble gases (Ar, Kr, Xe isotopes) and other relative volatile isotopes such as Hg and At. The results of an irradiation experiment performed at ISOLDE on a LBE target are compared with predictions from the MCNPX code using the latest developments on the Liège Intranuclear Cascade model (INCL4.6) and the CEM03 model. The calculations are able to reproduce the mass distribution of the radioisotopes produced, including the At production, where there is a significant contribution from secondary reactions. Subsequently, a post-irradiation examination of the irradiated target was performed. Investigations of both the tantalum target structure, in particular the beam window, and the lead-bismuth eutectic were performed using several experimental techniques. No sign of severe irradiation damage, previously observed in other ISOLDE targets, was found.

  16. Post-irradiation hypoxic incubation of X-irradiated MOLT-4 cells reduces apoptotic cell death by changing the intracellular redox state and modulating SAPK/JNK pathways.

    PubMed

    Hamasu, T; Inanami, O; Tsujitani, M; Yokoyama, K; Takahashi, E; Kashiwakura, I; Kuwabara, M

    2005-05-01

    To elucidate radiobiological effects of hypoxia on X-ray-induced apoptosis, MOLT-4 cells were treated under four set of conditions: (1) both X irradiation and incubation under normoxia, (2) X irradiation under hypoxia and subsequent incubation under normoxia, (3) X irradiation under normoxia and subsequent incubation under hypoxia, and (4) both X irradiation and incubation under hypoxia, and the induction of apoptosis was examined by fluorescence microscopy. About 28-33% apoptosis was observed in cells treated under conditions 1 and 2, but this value was significantly reduced to around 18-20% in cells treated under conditions 3 and 4, suggesting that post-irradiation hypoxic incubation rather than hypoxic irradiation mainly caused the reduction of apoptosis. The activation and expression of apoptosis signal-related molecules SAPK/JNK, Fas and caspase-3 were also suppressed by hypoxic incubation. Effects of hypoxic incubation were canceled when cells were treated under conditions 3 and 4 with an oxygen-mimicking hypoxic cell radiosensitizer, whereas the addition of N-acetyl-L-cysteine again reduced the induction of apoptosis. From these results it was concluded that hypoxia reduced the induction of apoptosis by changing the intracellular redox state, followed by the regulation of apoptotic signals in X-irradiated MOLT-4 cells.

  17. FFTF/IEM (Fast Flux Test Facility/Interim Examination and Maintenance) cell fuel pin weighing system

    SciTech Connect

    Gibbons, P.W.

    1987-01-01

    The Interim Examination and Maintenance (IEM) cell in the Fast Flux Test Facility (FFTF) is used for remote dissassembly of irradiated fuel and materials experiments. For those fuel experiments where the FFTF tag-gas detection system has indicated a fuel pin cladding breach, a weighing system is used in identifying that fuel pin with a reduced weight due to the escape of gaseous and volatile fission products. A fuel pin weighing machine, originally purchased for use in the Fuels and Materials Examination Facility (FMEF), was the basis for the IEM cell system. Design modifications to the original equipment were centered around adapting the machine to the differences between the two facilities and correcting deficiencies discovered during functional testing in the IEM cell mock-up.

  18. Phase-field simulations of intragranular fission gas bubble evolution in UO2 under post-irradiation thermal annealing

    SciTech Connect

    Li, Yulan; Hu, Shenyang Y.; Montgomery, Robert O.; Gao, Fei; Sun, Xin

    2013-05-15

    Fission gas bubble is one of evolving microstructures, which affect thermal mechanical properties such as thermo-conductivity, gas release, volume swelling, and cracking, in operating nuclear fuels. Therefore, fundamental understanding of gas bubble evolution kinetics is essential to predict the thermodynamic property and performance changes of fuels. In this work, a generic phasefield model was developed to describe the evolution kinetics of intra-granular fission gas bubbles in UO2 fuels under post-irradiation thermal annealing conditions. Free energy functional and model parameters are evaluated from atomistic simulations and experiments. Critical nuclei size of the gas bubble and gas bubble evolution were simulated. A linear relationship between logarithmic bubble number density and logarithmic mean bubble diameter is predicted which is in a good agreement with experimental data.

  19. Phenomenon of PDT-induced post-irradiation apoptosis in biological liquids cancer cells using sulphonated phthalocyanine aluminum photosensitizer

    NASA Astrophysics Data System (ADS)

    Douplik, Alexandre Y.; Loschenov, Victor B.; Vorozhtsov, Georgy N.; Kogan, Eugenia A.; Kusin, Michael; Ablitsov, Y.; Ilyina, O. S.

    1997-12-01

    Discovered during last year's phenomenon of PDT-induced apoptosis (programmed cell destruction) in cell culture immediately after light irradiation using phthalocyanine photosensitizers can be used for treatment of cancer. Experiments were carried out on mice with ascites. Ascitic liquid with the added photosensitizer was irradiated by light source with wavelength 660 - 680 nm and used according to ex vivo procedure. Actuation and development of apoptosis process in ascitic liquid were estimated by cytomorphological tests. It has been observed the phenomenon of growth of relative fraction of cells damage level expressed mainly as apoptosis after PDT procedure ex vivo. We suggest to call this phenomenon as PDT-induced post-irradiation apoptosis (PIP- apoptosis). Dependence between level of expressing of PIP- apoptosis and sulphonated phthalocyanine aluminum photosensitizer (Photosense) concentration at used photosensitizer concentrations has not been found out.

  20. The Importance of Getting Started Right: Further Examination of the Facility-to-Community Transition of Formerly Incarcerated Youth

    ERIC Educational Resources Information Center

    Bullis, Michael; Yovanoff, Paul; Havel, Emily

    2004-01-01

    This study examined the facility-to-community transition of 531 incarcerated youth following their release from Oregon's juvenile correctional system, for a period of 12 months. Data on the sample were gathered through phone interviews, while they were still in custody and then every 6 months after their parole. The interviewees were asked to…

  1. An Examination of Health Profile, Service Use and Care Needs of Older Adults in Residential Care Facilities

    ERIC Educational Resources Information Center

    Aminzadeh, F.; Salziel, William B.; Molnar, F. J.; Alie, J.

    2004-01-01

    Private, unregulated residential care facilities have become an increasingly important component of the continuum of housing and care for frail older adults in Canada. To date, this growing segment of the older population has received very little research attention. This study involved an in-depth examination of the functional/health profile,…

  2. Examining physicians' preparedness for tobacco cessation services in India: Findings from primary care public health facilities in two Indian states.

    PubMed

    Panda, Rajmohan; Jena, Pratap Kumar

    2013-01-01

    A total of 275 million tobacco users live throughout India and are in need of tobacco cessation services. However, the preparation of physicians to deliver this service at primary care health facilities remains unknown. The study aimed to examine the primary care physicians' preparedness to deliver tobacco cessation services in two Indian states. Researchers surveyed physicians working in primary care public health facilities, primarily in rural areas using a semistructured interview schedule. Physicians' preparedness was defined in the study as those possessing knowledge of tobacco cessation methods and exhibiting a positive attitude towards the benefits of tobacco cessation counselling as well as being willing to be part of tobacco prevention or cessation program. Overall only 17% of physicians demonstrated adequate preparation to provide tobacco cessation services at primary care health facilities in both the States. The findings revealed minimal tobacco cessation training during formal medical education (21.3%) and on-the-job training (18.9%). Factors, like sex and age of service provider, type of health facility, location of health facility and number of patients attended by the service provider, failed to show significance during bivariate and regression analysis. Preparedness was significantly predicted by state health system. The study highlights a lack of preparedness of primary care physicians to deliver tobacco cessation services. Both the curriculum in medical school and on-the-job training require an addition of a learning component on tobacco cessation. The addition of this component will enable existing primary care facilities to deliver tobacco cessation services.

  3. Facilities

    NASA Technical Reports Server (NTRS)

    1999-01-01

    An expansion of medical data collection facilities was necessary to implement the Extended Duration Orbiter Medical Project (EDOMP). The primary objective of the EDOMP was to ensure the capability of crew members to reenter the Earth's atmosphere, land, and egress safely following a 16-day flight. Therefore, access to crew members as soon as possible after landing was crucial for most data collection activities. Also, with the advent of EDOMP, the quantity of investigations increased such that the landing day maximum data collection time increased accordingly from two hours to four hours. The preflight and postflight testing facilities at the Johnson Space Center (JSC) required only some additional testing equipment and minor modifications to the existing laboratories in order to fulfill EDOMP requirements. Necessary modifications at the landing sites were much more extensive.

  4. Race, region and risk: An examination of minority proximity to noxious facilities

    SciTech Connect

    Nieves, A.L. |; Nieves, L.A.

    1996-04-01

    The past decade has given rise to terms like environmental racism, eco-racism, and environmental inequities to characterize a disproportional distribution of environmental disamenities among minority communities. Much of the literature supports the contention that racial and ethnic minorities and low-income groups bear a disproportionate burden of risk from hazardous activities and substances in the environment. This study expands the scope of prior studies by employing county-level data for the entire nation and including a broad range of facility types associated with environmental disamenities. In addition, it addresses the issue of the distribution of noxious facilities among white and non-white populations in an attempt to determine the relative exposure to risk among different racial and ethnic groups. In addition, the authors also explore the relative importance of nonurban versus urban residence.

  5. Results of examination of silvered Teflon from the Long Duration Exposure Facility

    NASA Technical Reports Server (NTRS)

    Rousslang, Ken W.; Crutcher, E. Russ; Pippin, H. Gary

    1991-01-01

    Pieces of silvered Teflon thermal control blanket from seventeen locations on the Long Duration Exposure Facility (LDEF) were studied. Results of the measurements of surface texturing, and mechanical, electrical and thermal properties are presented. Photos of the blankets, scanning electron microscope pictures, infrared spectra, and surface analysis results are presented. Contamination issues relative to performance of the blankets are discussed. The variation in measured properties are reported as a function of exposure conditions.

  6. Light Water Breeder end-of-life component examinations at Shippingport Atomic Power Station and module visual and dimensional examinations at Expended Core Facility (LWBR Development Program)

    SciTech Connect

    Wargo, J.E.

    1987-10-01

    This report presents highlights of visual and dimensional examinations of the Light Water Breeder Reactor fuel assemblies and selected core components following five years of power operation in which the core achieved 29,047 effective full power hours. Each type of fuel assembly (seed, blanket, and reflector) is described, and the end-of-life conditions are documented in photographs and data plots. Fuel modules were examined immediately after removal from the reactor vessel at the Shippingport Atomic Power Station and after shipment to the Expended Core Facility at the Naval Reactors Facility in Idaho. Further inspection was performed on one seed and one reflector assembly after their external support shells were removed. Module length changes and bow data are presented for selected assemblies. Structural component examinations include magnetic particle testing and ultrasonic test inspection of the LWBR reactor vessel closure head. Visual inspections were also performed on compression sleeves and guide tube extensions which formed part of the guide path for the movable fuel assemblies. 4 refs., 103 figs., 5 tabs.

  7. Post-Irradiation Bladder Syndrome After Radiotherapy of Malignant Neoplasm of Small Pelvis Organs: An Observational, Non-Interventional Clinical Study Assessing VESIcare®/Solifenacin Treatment Results.

    PubMed

    Jaszczyński, Janusz; Kojs, Zbigniew; Stelmach, Andrzej; Wohadło, Łukasz; Łuczyńska, Elzbieta; Heinze, Sylwia; Rys, Janusz; Jakubowicz, Jerzy; Chłosta, Piotr

    2016-07-30

    BACKGROUND Radiotherapy is explicitly indicated as one of the excluding factors in diagnosing overactive bladder syndrome (OAB). Nevertheless, symptoms of OAB such as urgent episodes, incontinence, pollakiuria, and nocturia, which are consequences of irradiation, led us to test the effectiveness of VESIcare®/Solifenacin in patients demonstrating these symptoms after radiation therapy of small pelvis organs due to malignant neoplasm. MATERIAL AND METHODS We conducted an observatory clinical study including 300 consecutive patients with symptoms of post-irradiation bladder; 271 of those patients completed the study. The observation time was 6 months and consisted of 3 consecutive visits taking place at 12-week intervals. We used VESIcare® at a dose of 5 mg a day. Every sixth patient was examined urodynamically at the beginning and at the end of the observation period, with an inflow speed of 50 ml/s. RESULTS We noticed improvement and decline in the average number of episodes a day in the following parameters: number of micturitions a day (-36%, P<0.01), nocturia (-50%, P<0.01), urgent episodes (-41%, P<0.03), and episodes of incontinence (-43%, P<0.01). The patients' quality of life improved. The average maximal cystometric volume increased by 34 ml (21%, p<0.01), average bladder volume of "first desire" increased by 42 ml (49%, P<0.01), and average detrusor muscle pressure at maximal cystometric volume diminished by 9 cmH2O (-36%, P<0.03). CONCLUSIONS The substance is well-tolerated. Solifenacin administered long-term to patients with symptoms of OAB after radiotherapy of a malignant neoplasm of the small pelvis organs has a daily impact in decreasing number of urgent episodes, incontinence, pollakiuria, and nocturia.

  8. Post-Irradiation Bladder Syndrome After Radiotherapy of Malignant Neoplasm of Small Pelvis Organs: An Observational, Non-Interventional Clinical Study Assessing VESIcare®/Solifenacin Treatment Results

    PubMed Central

    Jaszczyński, Janusz; Kojs, Zbigniew; Stelmach, Andrzej; Wohadło, Łukasz; Łuczyńska, Elżbieta; Heinze, Sylwia; Rys, Janusz; Jakubowicz, Jerzy; Chłosta, Piotr

    2016-01-01

    Background Radiotherapy is explicitly indicated as one of the excluding factors in diagnosing overactive bladder syndrome (OAB). Nevertheless, symptoms of OAB such as urgent episodes, incontinence, pollakiuria, and nocturia, which are consequences of irradiation, led us to test the effectiveness of VESIcare®/Solifenacin in patients demonstrating these symptoms after radiation therapy of small pelvis organs due to malignant neoplasm. Material/Methods We conducted an observatory clinical study including 300 consecutive patients with symptoms of post-irradiation bladder; 271 of those patients completed the study. The observation time was 6 months and consisted of 3 consecutive visits taking place at 12-week intervals. We used VESIcare® at a dose of 5 mg a day. Every sixth patient was examined urodynamically at the beginning and at the end of the observation period, with an inflow speed of 50 ml/s. Results We noticed improvement and decline in the average number of episodes a day in the following parameters: number of micturitions a day (−36%, P<0.01), nocturia (−50%, P<0.01), urgent episodes (−41%, P<0.03), and episodes of incontinence (−43%, P<0.01). The patients’ quality of life improved. The average maximal cystometric volume increased by 34 ml (21%, p<0.01), average bladder volume of “first desire” increased by 42 ml (49%, P<0.01), and average detrusor muscle pressure at maximal cystometric volume diminished by 9 cmH2O (−36%, P<0.03). Conclusions The substance is well-tolerated. Solifenacin administered long-term to patients with symptoms of OAB after radiotherapy of a malignant neoplasm of the small pelvis organs has a daily impact in decreasing number of urgent episodes, incontinence, pollakiuria, and nocturia. PMID:27474270

  9. An algorithm for pre- and post-irradiation fade in the Thermo 8802 LiF:Mg,Ti thermoluminescent dosimeter.

    PubMed

    Hill, Carolyn D

    2005-05-01

    The diminished response of thermoluminescent phosphors over time is a well-documented challenge to thermoluminescent dosimetry. Wide ranges in fading rates for various phosphor types have been reported, making it necessary for many external dosimetry programs to perform individual studies on thermoluminescent fade. Sandia National Laboratories currently uses the Thermo 8802 LiF:Mg,Ti thermoluminescent dosimeter (TLD) in its personnel external dosimetry program. Doses received in the field are calculated by applying a fade algorithm published by the manufacturer to TLD readings. Since the algorithm was established by characterizing the diminished response of a TLD similar to the 8802, Sandia chose to model its fade study after the analysis done by Thermo. As a result, the parameters of each experiment were comparable, and data from the two studies were compared to determine whether or not the current algorithm should be modified specifically for use at Sandia. Cards were irradiated using an internal Sr/Y source, and pre- and post-irradiation fading rates were monitored over a period of 18 wk. While significant fading was demonstrated, results closely matched those found in the original Thermo study.

  10. Results of examination of silvered Teflon from the Long Duration Exposure Facility

    NASA Technical Reports Server (NTRS)

    Rousslang, Ken; Crutcher, E. Russ; Pippin, H. Gary

    1992-01-01

    A significant effort to determine the effects of low earth orbit (LEO) exposure on silver backed fluorinated ethylene-propylene (FEP) blankets from the Long Duration Exposure Facility (LDEF) was performed, and the results of this investigation are described. Extensive measurements of surface, optical, chemical, and mechanical properties were conducted. Effects of contamination and erosion rates of the FEP layer were determined. Specific results are reported on solar absorptance, thermal emittance, diffuse reflectance, cross sectional microphotography, secondary ion mass spectroscopy, electron scattering for chemical analysis, scanning electron microscopy, percent elongation, and tensile strength. These measurements show the effects of two distinctly different exposure environments, solar exposure, and simultaneous atomic oxygen (AO) and solar exposure.

  11. Advanced Test Reactor National Scientific User Facility Partnerships

    SciTech Connect

    Frances M. Marshall; Todd R. Allen; Jeff B. Benson; James I. Cole; Mary Catherine Thelen

    2012-03-01

    In 2007, the United States Department of Energy designated the Advanced Test Reactor (ATR), located at Idaho National Laboratory, as a National Scientific User Facility (NSUF). This designation made test space within the ATR and post-irradiation examination (PIE) equipment at INL available for use by researchers via a proposal and peer review process. The goal of the ATR NSUF is to provide researchers with the best ideas access to the most advanced test capability, regardless of the proposer's physical location. Since 2007, the ATR NSUF has expanded its available reactor test space, and obtained access to additional PIE equipment. Recognizing that INL may not have all the desired PIE equipment, or that some equipment may become oversubscribed, the ATR NSUF established a Partnership Program. This program enables and facilitates user access to several university and national laboratories. So far, seven universities and one national laboratory have been added to the ATR NSUF with capability that includes reactor-testing space, PIE equipment, and ion beam irradiation facilities. With the addition of these universities, irradiation can occur in multiple reactors and post-irradiation exams can be performed at multiple universities. In each case, the choice of facilities is based on the user's technical needs. Universities and laboratories included in the ATR NSUF partnership program are as follows: (1) Nuclear Services Laboratories at North Carolina State University; (2) PULSTAR Reactor Facility at North Carolina State University; (3) Michigan Ion Beam Laboratory (1.7 MV Tandetron accelerator) at the University of Michigan; (4) Irradiated Materials at the University of Michigan; (5) Harry Reid Center Radiochemistry Laboratories at University of Nevada, Las Vegas; (6) Characterization Laboratory for Irradiated Materials at the University of Wisconsin-Madison; (7) Tandem Accelerator Ion Beam. (1.7 MV terminal voltage tandem ion accelerator) at the University of Wisconsin

  12. Effect of Ar+ ion post-irradiation on crystal structure, magnetic behavior and optical band gap of Co-implanted ZnO wafers

    NASA Astrophysics Data System (ADS)

    Xu, N. N.; Li, G. P.; Lin, Q. L.; Liu, H.; Bao, L. M.

    2016-12-01

    Single crystals wurtzite ZnO with (001) orientation were implanted with Co+ ions at room temperature (RT). To tune their magnetic behavior as well as the band gap of the implanted wafers, Ar+ ion post-irradiation (PI) was performed using the calculated energy and ion dose. The formed Co clusters present in the high dose Co-implanted ZnO wafer were observed to be absent after the PI, which is quite different from the low dose doped one. It is found that all the implanted samples showed a giant magnetic moment and a narrowing optical band gap, and that the post-irradiated ones exhibited an even further redshifted absorption edge and ferromagnetic behavior but with saturation magnetization (MS) drastically decreased.

  13. Post-Irradiation Fracture Toughness of Unalloyed Molybdenum, ODS molybdenum, and TZM molybdenum following irradiation at 244C to 507C

    SciTech Connect

    Cockeram, Brian V; Byun, Thak Sang; Leonard, Keith J; Snead, Lance Lewis

    2013-01-01

    Commercially available unalloyed molybdenum (Low Carbon Arc Cast (LCAC)), Oxide Dispersion Strengthened (ODS) molybdenum, and TZM molybdenum were neutron irradiated at temperatures of nominally 244 C, 407 C, and 509 C to neutron fluences between 1.0 to 4.6x1025 n/m2 (E>0.1 MeV). Post-irradiation fracture toughness testing was performed. All alloys exhibited a Ductile to Brittle Transition Temperature that was defined to occur at 30 4 MPa-m1/2. The highest post-irradiated fracture toughness values (26-107 MPa-m1/2) and lowest DBTT (100-150 C) was observed for ODS molybdenum in the L-T orientation. The finer grain size for ODS molybdenum results in fine laminates that improve the ductile laminate toughening. The results for ODS molybdenum are anisotropic with lower post-irradiated toughness values (20-30 MPa-m1/2) and higher DBTT (450-600 C) in the T-L orientation. The results for T-L ODS molybdenum are consistent or slightly better than those for LCAC molybdenum (21-71 MPa-m1/2 and 450-800 C DBTT). The fracture toughness values measured for LCAC and T-L ODS molybdenum at temperatures below the DBTT were determined to be 8-18 MPa-m1/2. Lower non-irradiated fracture toughness values were measured for TZM molybdenum that are attributed to the large carbide precipitates serving as preferential fracture initiation sites. The role of microstructure and grain size on post-irradiated fracture toughness was evaluated by comparing the results for LCAC molybdenum and ODS molybdenum.

  14. Measurement of the Tracer Gradient and Sampling System Bias of the Hot Fuel Examination Facility Stack Air Monitoring System

    SciTech Connect

    Glissmeyer, John A.; Flaherty, Julia E.

    2011-07-20

    This report describes tracer gas uniformity and bias measurements made in the exhaust air discharge of the Hot Fuel Examination Facility at Idaho National Laboratory. The measurements were a follow-up on earlier measurements which indicated a lack of mixing of the two ventilation streams being discharged via a common stack. The lack of mixing is detrimental to the accuracy of air emission measurements. The lack of mixing was confirmed in these new measurements. The air sampling probe was found to be out of alignment and that was corrected. The suspected sampling bias in the air sample stream was disproved.

  15. Post-irradiation viability and cytotoxicity of natural killer cells isolated from human peripheral blood using different methods.

    PubMed

    Hietanen, Tenho; Pitkänen, Maunu; Kapanen, Mika; Kellokumpu-Lehtinen, Pirkko-Liisa

    2016-01-01

    Purpose We compared the pre- and post-irradiation viability and cytotoxicity of human peripheral natural killer cell (NK) populations obtained using different isolation methods. Material and methods Three methods were used to enrich total NK cells from buffy coats: (I) a Ficoll-Paque gradient, plastic adherence and a nylon wool column; (II) a discontinuous Percoll gradient; or (III) the Dynal NK cell isolation kit. Subsequently, CD16(+) and CD56(+) NK cell subsets were collected using (IV) flow cytometry or (V) magnetic-activated cell sorting (MACS) NK cell isolation kits. The yield, viability, purity and cytotoxicity of the NK cell populations were measured using trypan blue exclusion, flow cytometry using propidium iodide and (51)Cr release assays after enrichments as well as viability and cytotoxicity after a single radiation dose. Results The purity of the preparations, as measured by the CD16(+) and CD56(+) cell content, was equally good between methods I-III (p = 0.323), but the content of CD16(+) and CD56(+) cells using these methods was significantly lower than that using methods IV and V (p = 0.005). The viability of the cell population enriched via flow cytometry (85.5%) was significantly lower than that enriched via other methods (99.4-98.0%, p = 0.003). The cytotoxicity of NK cells enriched using methods I-III was significantly higher than that of NK cells enriched using methods IV and V (p = 0.000). In vitro the NK cells did not recover cytotoxic activity following irradiation. In addition, we detected considerable inter-individual variation in yield, cytotoxicity and radiation sensitivity between the NK cells collected from different human donors. Conclusions The selection of the appropriate NK cell enrichment method is very important for NK cell irradiation studies. According to our results, the Dynal and MACS NK isolation kits best retained the killing capacity and the viability of irradiated NK cells.

  16. THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES

    SciTech Connect

    Ann M. Beauchesne

    1999-01-31

    Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: (1) Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; (2) Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; (3) Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; (4) Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; (5) Interstate waste and materials shipments; and (6) Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from October 1, 1998 through January 31, 1999, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: (1) maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; (2) maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and EM Integration activities; and (3

  17. THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES

    SciTech Connect

    Ann B. Beauchesne

    1998-09-30

    Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: (1) Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; (2) Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; (3) Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; (4) Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; (5) Interstate waste and materials shipments; and (6) Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from June 1, 1998 through September 30, 1998, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: (1) maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; (2) maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and EM Integration activities; and (3

  18. Public awareness and knowledge of prostate cancer in Japan: results of a survey at short-stay examination facilities.

    PubMed

    Egawa, S; Suyama, K; Shitara, T; Uchida, T; Koshiba, K

    1998-03-01

    This study was undertaken to determine public awareness and knowledge of prostate cancer, which has not been adequately studied in Japan. Assessment was made of public awareness and perception of prostate cancer in Japan, based on health examination data for participants in a short-stay physical examination program ("human dry dock"). A multiple-choice, thirty-point questionnaire survey was conducted at 3 "human dry dock" medical facilities situated in urban areas. Many Japanese adults appeared to be inadequately aware of prostate cancer and of the means available for its early detection. One third of the participants were unfamiliar with this malignancy. Logistic regression analysis indicated smoking to be the only covariate associated with lack of knowledge of prostate cancer (P< 0.05). Seventy-one percent of the subjects had heard of digital rectal examination, but only 16% and 8%, respectively, were familiar with the terms transrectal ultrasonography and PSA testing. Japanese people may possibly be less informed about prostate cancer than African-American males. Both "human dry dock" facilities and subject gender were significantly associated with knowledge of digital rectal examination (P< 0.05). Knowledge of transrectal ultrasonography was found to depend on participation in "human dry dock" programs and level of education (P< 0.05). Smoking, participation in "human dry dock" programs under employer direction, and health status were all identified as determinants for knowledge of PSA testing (P< 0.05). Educational programs should be established and put into effect to instill adequate awareness of prostate cancer in Japan. In a better-informed society, more effort would be directed toward prevention and thus early stage prostate cancer would be detected more often.

  19. Recovery behavior of high purity cubic SiC polycrystals by post-irradiation annealing up to 1673 K after low temperature neutron irradiation

    NASA Astrophysics Data System (ADS)

    Idris, Mohd Idzat; Yamazaki, Saishun; Yoshida, Katsumi; Yano, Toyohiko

    2015-10-01

    Two kinds of high purity cubic (β) SiC polycrystals, PureBeta-SiC and CVD-SiC, were irradiated in the BR2 reactor (Belgium) up to a fluence of 2.0-2.5 × 1024 (E > 0.1 MeV) at 333-363 K. Changes in macroscopic lengths were examined by post-irradiation thermal annealing using a precision dilatometer up to 1673 K with a step-heating method. The specimen was held at each temperature step for 6 h and the change in length of the specimen was recorded during each isothermal annealing step from 373 K to 1673 K with 50 K increments. The recovery curves were analyzed with the first order model, and rate constants at each annealing step were obtained. Recovery of defects, induced by neutron irradiation in high purity β-SiC, has four stages of different activation energies. At 373-573 K, the activation energy of PureBeta-SiC and CVD-SiC was in the range of 0.17-0.24 eV and 0.12-0.14 eV; 0.002-0.04 eV and 0.006-0.04 eV at 723-923 K; 0.20-0.27 eV and 0.26-0.31 eV at 923-1223 K; and 1.37-1.38 eV and 1.26-1.29 eV at 1323-1523 K, respectively. Below ∼1223 K the recombination occurred possibly for closely positioned C and Si Frenkel pairs, and no long range migration is deemed essential. Nearly three-fourths of recovery, induced by neutron irradiation, occur by this mechanism. In addition, at 1323-1523 K, recombination of slightly separated C Frenkel pairs and more long-range migration of Si interstitials may have occurred for PureBeta-SiC and CVD-SiC specimens. Migration of both vacancies may be restricted up to ∼1523 K. Comparing to hexagonal α-SiC, high purity β-SiC recovered more quickly in the lower annealing temperature range of less than 873 K, in particular less than 573 K.

  20. Modified clearing technique to identify lymph node metastases in post-irradiated surgical specimens from rectal adenocarcinoma.

    PubMed

    Sanchez, W; Luna-Perez, P; Alvarado, I; Labastida, S; Herrera, L

    1996-01-01

    The aim of this study is to describe a modification of the original method of clearing lymph nodes in specimens from rectal adenocarcinoma and its yield in comparison to a control group whose specimens were studied by a manual technique. There were 32 consecutive patients with locally advanced rectal adenocarcinoma. All patients received preoperative radiation therapy (PRT) at doses of 45 Gy, concomitant with 5-fluorouracil at the doses of 450 mg/m2 IV bolus, days 1-5 and 28-33 of PRT; 4-8 weeks later radical surgery with a curative intent was performed. Twenty two specimens were studied by a manual technique consisting of fixation in 10% formalin. Ten specimens were studied with the modified clearing technique consisting of administration through the inferior mesenteric artery of methylene blue; fixation with 10% formalin plus 0.01% of methylene blue; clearing the fat with a sequence of 95% alcohol-100% acetone-100% xylene. In the 32 specimens, 413 lymph nodes were found. Using the manual technique 104 lymph nodes were found (average 4.7 lymph nodes per specimen); 309 lymph nodes by the modified clearing technique (average 30.9 lymph nodes per specimen), (p < 0.0001). Using the manual technique 23 out of 104 lymph nodes (22%) contained metastases. All metastatic lymph nodes measured > 5 mm; 18 out of 23 metastatic lymph nodes were located on the perirectal area (level 2); and five were located in the root of the inferior mesenteric artery (level 5). Using the modified clearing technique 278 out of 309 (89%) lymph nodes measured < 5 mm; 15 out of 309 (4.8%) lymph nodes contained metastases; 9 out of 15 (60%) measured > 5 mm and were located on levels 2 and 5; and six, located on level 5, measured < 5 mm. The modified clearing technique is a quick, easy and reproducible method for identifying lymph nodes in post-irradiated surgical specimens. In comparison to the traditional manual method of searching for lymph nodes, it improves in the detection of small lymph

  1. Post-irradiation hardness development, chemical softening, and thermal stability of bulk-fill and conventional resin-composites.

    PubMed

    Alshali, Ruwaida Z; Salim, Nesreen A; Satterthwaite, Julian D; Silikas, Nick

    2015-02-01

    To measure bottom/top hardness ratio of bulk-fill and conventional resin-composite materials, and to assess hardness changes after dry and ethanol storage. Filler content and kinetics of thermal decomposition were also tested using thermogravimetric analysis (TGA). Six bulk-fill (SureFil SDR, Venus bulk fill, X-tra base, Filtek bulk fill flowable, Sonic fill, and Tetric EvoCeram bulk-fill) and eight conventional resin-composite materials (Grandioso flow, Venus Diamond flow, X-flow, Filtek Supreme Ultra Flowable, Grandioso, Venus Diamond, TPH Spectrum, and Filtek Z250) were tested (n=5). Initial and 24h (post-cure dry storage) top and bottom microhardness values were measured. Microhardness was re-measured after the samples were stored in 75% ethanol/water solution. Thermal decomposition and filler content were assessed by TGA. Results were analysed using one-way ANOVA and paired sample t-test (α=0.05). All materials showed significant increase of microhardness after 24h of dry storage which ranged from 100.1% to 9.1%. Bottom/top microhardness ratio >0.9 was exhibited by all materials. All materials showed significant decrease of microhardness after 24h of storage in 75% ethanol/water which ranged from 14.5% to 74.2%. The extent of post-irradiation hardness development was positively correlated to the extent of ethanol softening (R(2)=0.89, p<0.001). Initial thermal decomposition temperature assessed by TGA was variable and was correlated to ethanol softening. Bulk-fill resin-composites exhibit comparable bottom/top hardness ratio to conventional materials at recommended manufacturer thickness. Hardness was affected to a variable extent by storage with variable inorganic filler content and initial thermal decomposition shown by TGA. The manufacturer recommended depth of cure of bulk-fill resin-composites can be reached based on the microhardness method. Characterization of the primary polymer network of a resin-composite material should be considered when

  2. FFTF/IEM (Fast Flux Test Facility/Interim Examination and Maintenance) cell fuel pin removal equipment

    SciTech Connect

    Greenwell, R.K.

    1987-01-01

    This paper describes a fuel pin removal device used for pin removal from irradiated fuel assemblies at the Fast Flux Test Facility (FFTF). After irradiation in the FFTF, selected fuel assemblies are remotely disassembled in the Interim Examination and Maintenance (IEM) cell. The remote disassembly, following sodium removal, consists of slitting and removing the duct and then removing the fuel pins one-at-a-time by sliding the pins from parallel attachment rails. All pins are removed from one rail before starting on the next. The new pin removal equipment has been used very successfully on the last three fuel experiments disassembled in the IEM cell, including one assembly containing residual sodium. Pin removal time has been cut in half, and this once tedious and time-consuming activity has been turned into an almost effortless evolution.

  3. Characterization of stochastic noise and post-irradiation density growth for reflective-type radiochromic film in therapeutic photon beam dosimetry.

    PubMed

    Kamomae, Takeshi; Oita, Masataka; Hayashi, Naoki; Sasaki, Motoharu; Aoyama, Hideki; Oguchi, Hiroshi; Kawamura, Mariko; Monzen, Hajime; Itoh, Yoshiyuki; Naganawa, Shinji

    2016-10-01

    The aim of this study is to investigate the dosimetric uncertainty of stochastic noise and the post-irradiation density growth for reflective-type radiochromic film to obtain the appropriate dose from the exactly controlled film density. Film pieces were irradiated with 6-MV photon beams ranging from 0 to 400cGy. The pixel values (PVs) of these films were obtained using a flatbed scanner at elapsed times of 1min to 120h between the end of irradiation and the film scan. The means and standard deviations (SDs) of the PVs were calculated. The SDs of the converted dose scale, usd, and the dose increases resulting from the PV increases per ±29min at each elapsed time, utime, were computed. The combined dose uncertainties from these two factors, uc, were then calculated. A sharp increase in the PV occurred within the first 3h after irradiation, and a slight increase continued from 3h to 120h. usd was independent of post-irradiation elapsed time. Sharp decreases in utime were obtained within 1h after irradiation, and slight decreases in utime were observed from 1 to 24h after irradiation. uc first decreased 1h after irradiation and remained constant afterward. Assuming that the post-irradiation elapsed times of all of the related measurements are synchronized within ±29min, the elapsed time should be at least 1h in our system. It is important to optimize the scanning protocol for each institution with consideration of the required measurement uncertainty and acceptable latency time.

  4. SU-E-T-222: Investigation of Pre and Post Irradiation Fading of the TLD100 Thermoluminescence Dosimetry for Photon Beams

    SciTech Connect

    Sina, S; Sadeghi, M; Faghihi, R

    2014-06-01

    Purpose: The pre-irradiation and post-irradiation fading of the Thermoluminescense dosimeter signals were investigated in this study. Methods: Two groups of TLD chips with pre-determined ECC values were used in this study. The two groups were divided into 6 series, each composing of 5 TLD chips.The first group was used for pre-irradiation fading. 5 TLDs were exposed to a known amount of radiation from Cs-137 source, and were read out the next day. After seven days, the other 5 TLDs were exposed to the same amount of radiation and were read out after a day. The other series of 5 TLDs were also exposed after 7,19,28, 59, and 90 days, and were read out a day after irradiation. The loss in TLD signal were obtained for all the above cases. The second group, was used for postirradiation fading. All the TLDs of this group were exposed to a known amount of radiation from Cs-137 source. The 6 series composed of 5 TLDs were read out after 1,7,19,28,59, and 90 days. The above-mentioned procedures for obtaining pre-irradiation, and post-irradiation fading were performed for three storage temperatures (25°C, 4°C, and −18°C). Results: According to the results obtained in this study, in case of pre-irradiation fading study, the signal losses after 90 days are 12%, 24%, and 17% for 25°C, 4°C, and −18°C respectively. In case of post-irradiation fading study, the sensitivity losses after 90 days are 25%, 216%, and 20% for 25°C, 4°C, and −18°C respectively. Conclusion: The results indicate that the optimized time between exposing and reading out, and also the optimized time between annealing and exposing is 1 day.The reduction of Storage temperature will reduce the post-irradiation fading, While temperature reduction does not have any effect on pre-irradiation fading.

  5. The Advanced Test Reactor National Scientific User Facility Advancing Nuclear Technology

    SciTech Connect

    T. R. Allen; J. B. Benson; J. A. Foster; F. M. Marshall; M. K. Meyer; M. C. Thelen

    2009-05-01

    To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team

  6. The effect of electron irradiation and post-irradiation annealing on α-Al2O3 coating prepared by MOD method

    NASA Astrophysics Data System (ADS)

    Wang, Long; Zhang, Ling Dan; Wang, Jia Heng; Feng, Yong Jin; Feng, Kai Ming; Yang, Ji Jun; Liao, Jia Li; Yang, Yuan You; Liu, Ning

    2017-09-01

    α-Al2O3 ceramic coatings were prepared by a novel metal organic decomposition (MOD) method on 316L stainless steel. Effects of electron irradiation and post-irradiation annealing process on the surface morphology, composition, phases and corrosion resistance of the coating were studied by using AFM, FESEM, EDS, XRD and electrochemical workstation. The results show that the surface of α-Al2O3 ceramic coating was roughened after irradiation and then smoothed after subsequent annealing. The oxygen content of the coating was highly decreased after electron irradiation and then increased after subsequent annealing. The FeO phase of the coating was disappeared after irradiation and re-formed with the disappearance of AlFeCr phase after subsequent annealing. Both the irradiated and post-irradiated annealed coatings behaved superior corrosion resistance and protective ability compared to the original counterpart due to microstructure modification induced by irradiation. Meanwhile, two electrical circuit models were proposed to simulate the EIS results to explain the corrosion mechanism of the coatings.

  7. Examining Inequities in Incidence of Catastrophic Health Expenditures on Different Healthcare Services and Health Facilities in Nigeria

    PubMed Central

    Onwujekwe, Obinna; Hanson, Kara; Uzochukwu, Benjamin

    2012-01-01

    Objective There is limited evidence about levels of socio-economic and other differences in catastrophic health spending in Nigeria and in many sub-Saharan African countries. The study estimated the level of catastrophic healthcare expenditures for different healthcare services and facilities and their distribution across socioeconomic status (SES) groups. Methods The study took place in four Local Government Areas in southeast Nigeria. Data were collected using interviewer-administered questionnaires administered to 4873 households. Catastrophic health expenditures (CHE) were measured using a threshold of 40% of monthly non-food expenditure. We examined both total monthly health expenditure and disaggregated expenditure by source and type of care. Results The average total household health expenditure per month was 2354 Naira ($19.6). For outpatient services, average monthly expenditure was 1809 Naira ($15.1), whilst for inpatient services it was 610 Naira ($5.1). Higher health expenditures were incurred by urban residents and the better-off SES groups. Overall, 27% of households incurred CHE, higher for poorer socioeconomic groups and for rural residents. Only 1.0% of households had a member that was enrolled in a health insurance scheme. Conclusion The worse-off households (the poorest SES and rural dwellers) experienced the highest burden of health expenditure. There was almost a complete lack of financial risk protection. Health reform mechanisms are needed to ensure universal coverage with financial risk protection mechanisms. PMID:22815828

  8. Examining inequities in incidence of catastrophic health expenditures on different healthcare services and health facilities in Nigeria.

    PubMed

    Onwujekwe, Obinna; Hanson, Kara; Uzochukwu, Benjamin

    2012-01-01

    There is limited evidence about levels of socio-economic and other differences in catastrophic health spending in Nigeria and in many sub-Saharan African countries. The study estimated the level of catastrophic healthcare expenditures for different healthcare services and facilities and their distribution across socioeconomic status (SES) groups. The study took place in four Local Government Areas in southeast Nigeria. Data were collected using interviewer-administered questionnaires administered to 4873 households. Catastrophic health expenditures (CHE) were measured using a threshold of 40% of monthly non-food expenditure. We examined both total monthly health expenditure and disaggregated expenditure by source and type of care. The average total household health expenditure per month was 2354 Naira ($19.6). For outpatient services, average monthly expenditure was 1809 Naira ($15.1), whilst for inpatient services it was 610 Naira ($5.1). Higher health expenditures were incurred by urban residents and the better-off SES groups. Overall, 27% of households incurred CHE, higher for poorer socioeconomic groups and for rural residents. Only 1.0% of households had a member that was enrolled in a health insurance scheme. The worse-off households (the poorest SES and rural dwellers) experienced the highest burden of health expenditure. There was almost a complete lack of financial risk protection. Health reform mechanisms are needed to ensure universal coverage with financial risk protection mechanisms.

  9. [Examination of the contamination aetiological agent of legionellosis in the water supply systems of medical treatment facilities].

    PubMed

    Gruzdeva, O A; Tartakovskiĭ, I S; Mar'in, G G

    2012-05-01

    This study considers the features of colonization of water distribution systems by Legionella in large multi-type health-care facilities in Moscow-city, Russia. The investigation of 16 pavilions in 5 multi-type health-care facilities had found the hith level of hot water systems contaminated by Legionella pneumophila (68%), including the risk units. Among the different species of Legionella pneumophila, circulating in hot water systems of health-care facilities, the following strains had prevailed: the serogroup 6 (44%), 5 (26%) and 1 (13%). The findings conclude that certain prevention measures should be taken for microbial control and ensuring water safety in water systems of health-care facilities to prevent the nosocomial cases of legionellosis.

  10. A National Study of Efficiency for Dialysis Centers: An Examination of Market Competition and Facility Characteristics for Production of Multiple Dialysis Outputs

    PubMed Central

    Ozgen, Hacer; A. Ozcan, Yasar

    2002-01-01

    Objective To examine market competition and facility characteristics that can be related to technical efficiency in the production of multiple dialysis outputs from the perspective of the industrial organization model. Study Setting Freestanding dialysis facilities that operated in 1997 submitted cost report forms to the Health Care Financing Administration (HCFA), and offered all three outputs—outpatient dialysis, dialysis training, and home program dialysis. Data Sources The Independent Renal Facility Cost Report Data file (IRFCRD) from HCFA was utilized to obtain information on output and input variables and market and facility features for 791 multiple-output facilities. Information regarding population characteristics was obtained from the Area Resources File. Study Design Cross-sectional data for the year 1997 were utilized to obtain facility-specific technical efficiency scores estimated through Data Envelopment Analysis (DEA). A binary variable of efficiency status was then regressed against its market and facility characteristics and control factors in a multivariate logistic regression analysis. Principal Findings The majority of the facilities in the sample are functioning technically inefficiently. Neither the intensity of market competition nor a policy of dialyzer reuse has a significant effect on the facilities' efficiency. Technical efficiency is significantly associated, however, with type of ownership, with the interaction between the market concentration of for-profits and ownership type, and with affiliations with chains of different sizes. Nonprofit and government-owned facilities are more likely than their for-profit counterparts to become inefficient producers of renal dialysis outputs. On the other hand, that relationship between ownership form and efficiency is reversed as the market concentration of for-profits in a given market increases. Facilities that are members of large chains are more likely to be technically inefficient

  11. A national study of efficiency for dialysis centers: an examination of market competition and facility characteristics for production of multiple dialysis outputs.

    PubMed

    Ozgen, Hacer; Ozcan, Yasar A

    2002-06-01

    To examine market competition and facility characteristics that can be related to technical efficiency in the production of multiple dialysis outputs from the perspective of the industrial organization model. Freestanding dialysis facilities that operated in 1997 submitted cost report fonns to the Health Care Financing Administration (HCFA), and offered all three outputs--outpatient dialysis, dialysis training, and home program dialysis. The Independent Renal Facility Cost Report Data file (IRFCRD) from HCFA was utilized to obtain information on output and input variables and market and facility features for 791 multiple-output facilities. Information regarding population characteristics was obtained from the Area Resources File. Cross-sectional data for the year 1997 were utilized to obtain facility-specific technical efficiency scores estimated through Data Envelopment Analysis (DEA). A binary variable of efficiency status was then regressed against its market and facility characteristics and control factors in a multivariate logistic regression analysis. The majority of the facilities in the sample are functioning technically inefficiently. Neither the intensity of market competition nor a policy of dialyzer reuse has a significant effect on the facilities' efficiency. Technical efficiency is significantly associated, however, with type of ownership, with the interaction between the market concentration of for-profits and ownership type, and with affiliations with chains of different sizes. Nonprofit and government-owned Facilities are more likely than their for-profit counterparts to become inefficient producers of renal dialysis outputs. On the other hand, that relationship between ownership form and efficiency is reversed as the market concentration of for-profits in a given market increases. Facilities that are members of large chains are more likely to be technically inefficient. Facilities do not appear to benefit from joint production of a variety of

  12. FY 2013 Summary Report: Post-Irradiation Examination of Zircaloy-4 Samples in Target Capsules and Initiation of Bending Fatigue Testing for Used Nuclear Fuel Vibration Integrity Investigations

    SciTech Connect

    Howard, Richard H.; Yan, Yong; Wang, Jy-An John; Ott, Larry J.; Howard, Rob L.

    2013-10-01

    This report documents ongoing work performed at Oak Ridge National Laboratory (ORNL) for the Department of Energy, Office of Fuel Cycle Technology Used Fuel Disposition Campaign (UFDC), and satisfies the deliverable for milestone M2FT-13OR0805041, “Data Report on Hydrogen Doping and Irradiation in HFIR.” This work is conducted under WBS 1.02.08.05, Work Package FT-13OR080504 ST “Storage and Transportation-Experiments – ORNL.” The objectives of work packages that make up the S&T Experiments Control Account are to conduct the separate effects tests (SET) and small-scale tests that have been identified in the Used Nuclear Fuel Storage and Transportation Data Gap Prioritization (FCRD-USED-2012-000109). In FY 2013, the R&D focused on cladding and container issues and small-scale tests as identified in Sections A-2.9 and A-2.12 of the prioritization report.

  13. Comparison of Pre-and Post-Irradiation Low-Frequency Noise Spectra of Midwave Infrared nBn Detectors With Superlattice Absorbers

    NASA Astrophysics Data System (ADS)

    Garduño, Eli A.; Cowan, Vincent M.; Jenkins, Geoffrey D.; Morath, Christian P.; Steenbergen, Elizabeth H.

    2017-04-01

    Noise spectra of type-II strained layer superlattice midwave infrared photodetectors were compared preand postirradiation by a proton fluence of 7.5 × 1011 cm-2 [total ionizing dose equivalent of 100 krad (Si)] and related to the shot noise limit at biases ranging from +200 to -800 mV and temperatures of 130 and 160 K. Pre-irradiation dark current at 130 K was 7.5X Rule '07 and increased to 59X Rule '07 after irradiation. The pre-irradiation noise spectra were within one order of magnitude of the shot noise prediction, while post-irradiation noise spectra were close to two orders higher, indicating the introduction of nonshot-like noise sources.

  14. HT-9 duct cutting - IEM (Interim Examination and Maintenance) cell and mock-up testing experience at FFTF (Fast Flux Test Facility)

    SciTech Connect

    Gibbons, P.W.; Greenwell, R.K.

    1987-01-01

    This paper describes experience gained during remote cutting of the HT-9 alloy duct from an advanced fuel assembly in the Interim Examination and Maintenance (IEM) cell at the Fast Flux Test Facility (FFTF). Also described is a test program performed on mock-up equipment to develop successful cutting parameters.

  15. FFTF (Fast Flux Test Facility) cobalt test assembly results

    SciTech Connect

    Rawlins, J.A.; Wootan, D.W.; Carter, L.L.; Brager, H.R.; Schenter, R.E.

    1987-10-01

    A cobalt test assembly containing yttrium hydride pins for neutron moderation was irradiated in the Fast Flux Test Facility during Cycle 9A for 137.7 equivalent full power days at a power level of 291 MW. The 36 test pins consisted of a batch of 32 pins containing cobalt metal to produce Co-60, and a set of 4 pins with europium oxide to produce Gd-153, a radioisotope used in detection of the bone disease Osteoporosis. Post-irradiation examination of the cobalt pins determined the Co-60 produced with an accuracy of about 5%. The measured Co-60 spatially distributed concentrations were within 20% of the calculated concentrations. The assembly average Co-60 measured activity was 4% less than the calculated value. The europium oxide pins were gamma scanned for the europium isotopes Eu-152 and Eu-154 to an absolute accuracy of about 10%. The measured europium radioisotope and Gd-153 concentrations were within 20% of calculated values. In conclusion, the hydride assembly performed well and is an excellent vehicle for many Fast Flux Test Facility isotope production applications. The results also demonstrate that the calculational methods developed by the Westinghouse Hanford Company are very accurate. 4 refs., 3 figs., 1 tab.

  16. Examining the role of information exchange in residential aged care work practices-a survey of residential aged care facilities

    PubMed Central

    2012-01-01

    Background The provision of residential aged care is underpinned by information, and is reliant upon systems that adequately capture and effectively utilise and communicate this information. The aim of this study was to explicate and quantify the volume and method by which information is collected, exchanged within facilities and with external providers, and retrieved from facility information systems and hospitals. Methods A survey of staff (n = 119), including managers, health informatics officers (HIOs), quality improvement staff, registered nurses (RNs), enrolled nurses (ENs)/endorsed enrolled nurses (EENs) and assistants in nursing (AINs) was carried out in four residential aged care facilities in New South Wales and Victoria, Australia. Sites varied in size and displayed a range of information technology (IT) capabilities. The survey investigated how and by whom information is collected, retrieved and exchanged, and the frequency and amount of time devoted to these tasks. Descriptive analysis was performed using SPSS, and open responses to questions were coded into key themes. Results Staff completed a median of six forms each, taking a median of 30 min per shift. 68.8% of staff reported transferring information from paper to a computer system, which took a median of 30 min per shift. Handover and face-to-face communication was the most frequently used form of information exchange within facilities. There was a large amount of faxing and telephone communication between facility staff and General Practitioners and community pharmacists, with staff reporting sending a median of 2 faxes to pharmacy and 1.5 faxes to General Practitioners, and initiating 2 telephone calls to pharmacies and 1.5 calls to General Practitioners per shift. Only 38.5% of respondents reported that they always had information available at the point-of-care and only 35.4% of respondents reported that they always had access to hospital stay information of residents after hospital

  17. 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.

  18. Prevention of significant deterioration permit application for the Fueled Clad Fabrication System, the Radioisotope Power Systems Facility, and the Fuel Assembly Area

    SciTech Connect

    Not Available

    1989-08-01

    This New Source Review'' has been submitted by the US Department of Energy-Richland Operations Office (PO Box 550, Richland, Washington 99352), pursuant to WAC 173-403-050 and in compliance with the Department of Ecology Guide to Processing A Prevention Of Significant Deterioration (PSD) Permit'' for three new sources of radionuclide emissions at the Hanford Site in Washington State. The three new sources, the Fueled Clad Fabrication System (FCFS), the Radioisotope Power Systems Facility (RPSF), and the Fuel Assembly Area (FAA), will be located in one facility, the Fuels and Materials Examination Facility (FMEF) of the 400 Area. The FMEF was originally designed to provide for post-irradiation examination and fabrication of breeder reactor fuels. These FMEF missions were cancelled before the introduction of any fuel materials or any irradiated material. The current plans are to use the facility to fabricate power supplies for use in space applications and to produce Fast Flux Test Facility (FFTF) fuel and target assemblies. The FCFS and the RPSF will produce materials and assemblies for application in space. The FAA project will produce FFTF fuel and target assemblies. The FCFS and the RPSF will share the same building, stack, and, in certain cases, the same floor space. Given this relationship, these systems will be dealt with separately to the extent possible. The FAA is a comparatively independent operation though it will share the FMEF complex.

  19. Supplemental information for a notice of construction for the Fueled Clad Fabrication System, the Radioisotope Power Systems Facility, and the Fuel Assembly Area

    SciTech Connect

    Not Available

    1989-08-01

    This ''Notice of Construction'' has been submitted by the US Department of Energy-Richland Operations Office (P.O. Box 550, Richland, Washington 99352), pursuant to WAC 402-80-070, for three new sources of radionuclide emissions at the Hanford Site in Washington State (Figure 1). The three new sources, the Fueled Clad Fabrication System (FCFS) the Radioisotope Power Systems Facility (RPSF) and the Fuel Assembly Area (FAA) will be located in one facility, the Fuels and materials Examination Facility (FMEF) of the 400 Area. The FMEF was originally designed to provide for post- irradiation examination and fabrication of breeder reactor fuels. These FMEF missions were cancelled before the introduction of any fuel materials or any irradiated material. The current plans are to use the facility to fabricate power supplies to be used in space applications and to produce Fast Flux Test Facility (FFTF) fuel and target assemblies. The FCFS and the RPSF will produce materials and assemblies for application in space. The FAA project will produce FFTF fuel and target assemblies. The FCFS and the RPSF will share the same building, stack, and, in certain cases, the same floor space. Given this relationship, to the extent possible, these systems will be dealt with separately. The FAA is a comparatively independent operation though it will share the FMEF complex.

  20. Application for approval for construction of the Fueled Clad Fabrication System, the Radioisotope Power Systems Facility, and the Fuel Assembly Area

    SciTech Connect

    Not Available

    1989-08-01

    The following ''Application for Approval of Construction'' is being submitted by the US Department of Energy-Richland Operations Office, pursuant to 40 CFR 61.07, for three new sources of airborne radionuclide emissions at the Hanford Site in Washington State. The three new sources, the Fueled Clad Fabrication System (FCFS), the Radioisotope Power Systems Facility (RPSF), and the Fuel Assembly Area (FAA), will be located in one facility, the Fuels and Materials Examination Facility (FMEF) of the 400 Area. The FMEF was originally designed to provide for post-irradiation examination and fabrication of breeder reactor fuels. These FMEF missions were canceled before the introduction of any fuel materials or any irradiated material. The current plans are to use the facility to fabricate power supplies to be used in space applications and to produce Fast Flux Test Facility (FFTF) fuel and target assemblies. The FCFS and the RPSF will produce materials and assemblies for application in space. The FAA project will produce FFTF fuel and target assemblies. The FCFS and the RPSF will share the same building and stack and, in certain cases, the same floor space. Given this relationship, these systems will be dealt with separately to the extent possible. The FAA is a comparatively independent operation though it will share the FMEF complex. 2 refs., 16 figs., 12 tabs.

  1. Conceptual design for a receiving station for the nondestructive assay of PuO/sub 2/ at the fuels and materials examination facility

    SciTech Connect

    Sampson, T.E.; Speir, L.G.; Ensslin, N.; Hsue, S.T.; Johnson, S.S.; Bourret, S.; Parker, J.L.

    1981-11-01

    We propose a conceptual design for a receiving station for input accountability measurements on PuO/sub 2/ received at the Fuels and Materials Examination Facility at the Hanford Engineering Development Laboratory. Nondestructive assay techniques are proposed, including neutron coincidence counting, calorimetry, and isotopic determination by gamma-ray spectroscopy, in a versatile data acquisition system to perform input accountability measurements with precisions better than 1% at throughputs of up to 2 M.T./yr of PuO/sub 2/.

  2. Gas Test Loop Facilities Alternatives Assessment Report Rev 1

    SciTech Connect

    William J. Skerjanc; William F. Skerjanc

    2005-07-01

    An important task in the Gas Test Loop (GTL) conceptual design was to determine the best facility to serve as host for this apparatus, which will allow fast-flux neutron testing in an existing nuclear facility. A survey was undertaken of domestic and foreign nuclear reactors and accelerator facilities to arrive at that determination. Two major research reactors in the U.S. were considered in detail, the Advanced Test Reactor (ATR) and the High Flux Isotope Reactor (HFIR), each with sufficient power to attain the required neutron fluxes. HFIR routinely operates near its design power limit of 100 MW. ATR has traditionally operated at less than half its design power limit of 250 MW. Both of these reactors should be available for at least the next 30 years. The other major U.S. research reactor, the Missouri University Research Reactor, does not have sufficient power to reach the required neutron flux nor do the smaller research reactors. Of the foreign reactors investigated, BOR-60 is perhaps the most attractive. Monju and BN 600 are power reactors for their respective electrical grids. Although the Joyo reactor is vigorously campaigning for customers, local laws regarding transport of radioactive material mean it would be very difficult to retrieve test articles from either Japanese reactor for post irradiation examination. PHENIX is scheduled to close in 2008 and is fully booked until then. FBTR is limited to domestic (Indian) users only. Data quality is often suspect in Russia. The only accelerator seriously considered was the Fuel and Material Test Station (FMTS) currently proposed for operation at Los Alamos National Laboratory. The neutron spectrum in FMTS is similar to that found in a fast reactor, but it has a pronounced high-energy tail that is atypical of fast fission reactor spectra. First irradiation in the FMTS is being contemplated for 2008. Detailed review of these facilities resulted in the recommendation that the ATR would be the best host for the GTL.

  3. Examining the potential role of a supervised injection facility in Saskatoon, Saskatchewan, to avert HIV among people who inject drugs

    PubMed Central

    Jozaghi, Ehsan; Jackson, Asheka

    2015-01-01

    Background: Research predicting the public health and fiscal impact of Supervised Injection Facilities (SIFs), across different cities in Canada, has reported positive results on the reduction of HIV cases among People Who Inject Drugs (PWID). Most of the existing studies have focused on the outcomes of Insite, located in the Vancouver Downtown Eastside (DTES). Previous attention has not been afforded to other affected areas of Canada. The current study seeks to address this deficiency by assessing the cost-effectiveness of opening a SIF in Saskatoon, Saskatchewan. Methods: We used two different mathematical models commonly used in the literature, including sensitivity analyses, to estimate the number of HIV infections averted due to the establishment of a SIF in the city of Saskatoon, Saskatchewan. Results: Based on cumulative cost-effectiveness results, SIF establishment is cost-effective. The benefit to cost ratio was conservatively estimated to be 1.35 for the first two potential facilities. The study relied on 34% and 14% needle sharing rates for sensitivity analyses. The result for both sensitivity analyses and the base line estimates indicated positive prospects for the establishment of a SIF in Saskatoon. Conclusion: The opening of a SIF in Saskatoon, Saskatchewan is financially prudent in the reduction of tax payers’ expenses and averting HIV infection rates among PWID PMID:26029896

  4. A Multi-stage Carcinogenesis Model to Investigate Caloric Restriction as a Potential Tool for Post-irradiation Mitigation of Cancer Risk

    PubMed Central

    Tani, Shusuke; Blyth, Benjamin John; Shang, Yi; Morioka, Takamitsu; Kakinuma, Shizuko; Shimada, Yoshiya

    2016-01-01

    The risk of radiation-induced cancer adds to anxiety in low-dose exposed populations. Safe and effective lifestyle changes which can help mitigate excess cancer risk might provide exposed individuals the opportunity to pro-actively reduce their cancer risk, and improve mental health and well-being. Here, we applied a mathematical multi-stage carcinogenesis model to the mouse lifespan data using adult-onset caloric restriction following irradiation in early life. We re-evaluated autopsy records with a veterinary pathologist to determine which tumors were the probable causes of death in order to calculate age-specific mortality. The model revealed that in both irradiated and unirradiated mice, caloric restriction reduced the age-specific mortality of all solid tumors and hepatocellular carcinomas across most of the lifespan, with the mortality rate dependent more on age owing to an increase in the number of predicted rate-limiting steps. Conversely, irradiation did not significantly alter the number of steps, but did increase the overall transition rate between the steps. We show that the extent of the protective effect of caloric restriction is independent of the induction of cancer from radiation exposure, and discuss future avenues of research to explore the utility of caloric restriction as an example of a potential post-irradiation mitigation strategy. PMID:27390741

  5. Post-irradiation lumbosacral radiculopathy associated with multiple cavernous malformations of the cauda equina: Case report and review of the literature

    PubMed Central

    Drazin, Doniel; Kappel, Ari; Withrow, Stefan; Perry, Tiffany; Chu, Ray; Phuphanich, Surasak

    2017-01-01

    Background: Multiple radiation-induced cavernous malformations of the cauda equina are extremely rare. A review of the literature suggested that the post-irradiation lumbosacral radiculopathy in our patient was most likely associated with a diagnosis of multiple radiation-induced cavernous malformations of the cauda equina. Case Description: A 76-year-old man with a remote history of abdominal radiation therapy presented with a 6-month history of progressively worsening right foot drop and balance impairment. Magnetic resonance imaging (MRI) revealed multiple enhancing areas of the cauda equina concerning for carcinomatous meningitis, however, cerebrospinal fluid (CSF) analysis was unrevealing. Intraoperative findings were consistent with multiple radiation-induced cavernous malformations of the cauda equina. Conclusions: Multiple radiation-induced cavernous malformations of the cauda equina may mimic carcinomatous or infectious meningitis. Clinicians should be suspicious of this diagnosis when CSF and MRI findings are inconsistent with metastatic disease or infectious meningitis in patients who present with radiculopathy and a history of radiation therapy. PMID:28303206

  6. Post-irradiation annealing behavior of microstructure and hardening of a reactor pressure vessel steel studied by positron annihilation and atom probe tomography

    NASA Astrophysics Data System (ADS)

    Kuramoto, A.; Toyama, T.; Takeuchi, T.; Nagai, Y.; Hasegawa, M.; Yoshiie, T.; Nishiyama, Y.

    2012-06-01

    Post-irradiation annealing (PIA) behavior of irradiation-induced microstructural changes and hardening of an A533B (0.16 wt.% Cu) steel after neutron-irradiation of 3.9 × 1019 n cm-2 (0.061 displacement per atom (dpa)) at 290 °C was studied by positron annihilation spectroscopy (PAS), atom probe tomography (APT) and Vickers microhardness measurements. Coincidence Doppler broadening and positron lifetime measurements clearly reveal two recovery stages; (i) as-irradiated state to annealing at 450 °C and (ii) annealing from 450 to 600 °C. The first stage is due to annealing out of the most of irradiation-induced vacancy-related defects, while the second stage corresponds to dissolving of irradiation-induced solute nanoclusters (SCs). APT observations reveal that the SCs are enriched with Cu, Mn, Ni and Si and that their number densities decrease with increasing annealing temperature without coarsening to give almost complete recovery at 550 °C. The experimental hardening is almost twice the SC hardening estimated by the Russell-Brown model below 350 °C, whereas it is almost the same as that estimated in the range 400-550 °C.

  7. Oral health and dental care in aged care facilities in New South Wales, Australia. Part 3 concordance between residents' perceptions and a professional dental examination.

    PubMed

    Webb, Bettine C; Whittle, Terry; Schwarz, Eli

    2016-09-01

    To determine the perceptions of dental care held by the residents in aged care facilities (ACFs) in New South Wales (NSW) and to compare these perceptions with clinical observations. No specific data exist relating to NSW residents' perceptions of dental care compared with a clinical examination. Planning for appropriate oral health programs in ACFs necessitate such data. Four Area Health Services of Sydney and 25 low care ACFs were selected from which representative residents were sampled who completed a survey and underwent a basic dental examination. Of the subjects (25 males, 96 females), 76.9% had never received a dental visit as entering the ACF; 14.1% suffered from dental pain; 69.4% wore dentures and of these 18.3% required assistance in cleaning. Dentures were cleaned twice/day in 54.9% of cases. Natural teeth were reported present in 71.9% of residents, and 85.1% did not require assistance in cleaning. Appropriate dental care facilities and dry mouth were most frequent problems highlighted. Clinical examinations showed that 69% were denture wearers; oral hygiene and denture hygiene were considered good in 15.7% of cases. A high level of concordance existed between self-reports and examination. Increased awareness about oral health across leadership, caregivers and residents with appropriate dental health education and dedicated space within facilities would provide a much needed improvement for addressing oral health issues of the ACF residents. This might be the right time to plan for the future challenges that will need to be met by the NSW care system. © 2015 John Wiley & Sons A/S and The Gerodontology Association. Published by John Wiley & Sons Ltd.

  8. Effect of antihistamines, disodium cromoglycate (DSCG) or methysergide on post-irradiation cerebral blood flow and mean systemic arterial blood pressure in primates after 25 Gy, whole-body, gamma irradiation.

    PubMed

    Cockerham, L G; Forcino, C D

    1995-06-01

    Exposure to ionizing radiation causes hypotension, cerebral ischemia and release of histamine (HA) and serotonin (5-HT). To investigate the relationship among these responses, rhesus monkeys (Macaca mulatta) received physiological saline (i.v.), disodium cromoglycate (DSCG), antihistamines (AH, mepyramine and cimetidine), or methysergide (METH), then were given 25 Gy whole-body irradiation. Monkeys receiving DSCG, AH or METH had higher post-irradiation mean arterial blood pressure (MBP) than saline-treated controls. Compared to levels in controls, post-irradiation hippocampal blood flow (rCBF) levels were higher in monkeys receiving DSCG, AH or METH. Treatment with the 5-HT2 receptor antagonist methysergide was the most effective in maintaining both rCBF and MBP after irradiation. Results support the hypothesis that the irradiation-induced cerebral ischemia and, to some extent, the hypotension is mediated by serotonin through 5-HT2 receptor sites.

  9. DNA microarray analyses reveal a post-irradiation differential time-dependent gene expression profile in yeast cells exposed to X-rays and gamma-rays.

    PubMed

    Kimura, Shinzo; Ishidou, Emi; Kurita, Sakiko; Suzuki, Yoshiteru; Shibato, Junko; Rakwal, Randeep; Iwahashi, Hitoshi

    2006-07-21

    Ionizing radiation (IR) is the most enigmatic of genotoxic stress inducers in our environment that has been around from the eons of time. IR is generally considered harmful, and has been the subject of numerous studies, mostly looking at the DNA damaging effects in cells and the repair mechanisms therein. Moreover, few studies have focused on large-scale identification of cellular responses to IR, and to this end, we describe here an initial study on the transcriptional responses of the unicellular genome model, yeast (Saccharomyces cerevisiae strain S288C), by cDNA microarray. The effect of two different IR, X-rays, and gamma (gamma)-rays, was investigated by irradiating the yeast cells cultured in YPD medium with 50 Gy doses of X- and gamma-rays, followed by resuspension of the cells in YPD for time-course experiments. The samples were collected for microarray analysis at 20, 40, and 80 min after irradiation. Microarray analysis revealed a time-course transcriptional profile of changed gene expressions. Up-regulated genes belonged to the functional categories mainly related to cell cycle and DNA processing, cell rescue defense and virulence, protein and cell fate, and metabolism (X- and gamma-rays). Similarly, for X- and gamma-rays, the down-regulated genes belonged to mostly transcription and protein synthesis, cell cycle and DNA processing, control of cellular organization, cell fate, and C-compound and carbohydrate metabolism categories, respectively. This study provides for the first time a snapshot of the genome-wide mRNA expression profiles in X- and gamma-ray post-irradiated yeast cells and comparatively interprets/discusses the changed gene functional categories as effects of these two radiations vis-à-vis their energy levels.

  10. SU-E-T-628: Predicted Risk of Post-Irradiation Cerebral Necrosis in Pediatric Brain Cancer Patients: A Treatment Planning Comparison of Proton Vs. Photon Therapy

    SciTech Connect

    Freund, D; Zhang, R; Sanders, M; Newhauser, W

    2015-06-15

    Purpose: Post-irradiation cerebral necrosis (PICN) is a severe late effect that can Result from brain cancers treatment using radiation therapy. The purpose of this study was to compare the treatment plans and predicted risk of PICN after volumetric modulated arc therapy (VMAT) to the risk after passively scattered proton therapy (PSPT) and intensity modulated proton therapy (IMPT) in a cohort of pediatric patients. Methods: Thirteen pediatric patients with varying age and sex were selected for this study. A clinical treatment volume (CTV) was constructed for 8 glioma patients and 5 ependymoma patients. Prescribed dose was 54 Gy over 30 fractions to the planning volume. Dosimetric endpoints were compared between VMAT and proton plans. The normal tissue complication probability (NTCP) following VMAT and proton therapy planning was also calculated using PICN as the biological endpoint. Sensitivity tests were performed to determine if predicted risk of PICN was sensitive to positional errors, proton range errors and selection of risk models. Results: Both PSPT and IMPT plans resulted in a significant increase in the maximum dose and reduction in the total brain volume irradiated to low doses compared with the VMAT plans. The average ratios of NTCP between PSPT and VMAT were 0.56 and 0.38 for glioma and ependymoma patients respectively and the average ratios of NTCP between IMPT and VMAT were 0.67 and 0.68 for glioma and ependymoma plans respectively. Sensitivity test revealed that predicted ratios of risk were insensitive to range and positional errors but varied with risk model selection. Conclusion: Both PSPT and IMPT plans resulted in a decrease in the predictive risk of necrosis for the pediatric plans studied in this work. Sensitivity analysis upheld the qualitative findings of the risk models used in this study, however more accurate models that take into account dose and volume are needed.

  11. DNA microarray analyses reveal a post-irradiation differential time-dependent gene expression profile in yeast cells exposed to X-rays and {gamma}-rays

    SciTech Connect

    Kimura, Shinzo; Ishidou, Emi; Kurita, Sakiko; Suzuki, Yoshiteru; Shibato, Junko; Rakwal, Randeep . E-mail: rakwal-68@aist.go.jp; Iwahashi, Hitoshi

    2006-07-21

    Ionizing radiation (IR) is the most enigmatic of genotoxic stress inducers in our environment that has been around from the eons of time. IR is generally considered harmful, and has been the subject of numerous studies, mostly looking at the DNA damaging effects in cells and the repair mechanisms therein. Moreover, few studies have focused on large-scale identification of cellular responses to IR, and to this end, we describe here an initial study on the transcriptional responses of the unicellular genome model, yeast (Saccharomyces cerevisiae strain S288C), by cDNA microarray. The effect of two different IR, X-rays, and gamma ({gamma})-rays, was investigated by irradiating the yeast cells cultured in YPD medium with 50 Gy doses of X- and {gamma}-rays, followed by resuspension of the cells in YPD for time-course experiments. The samples were collected for microarray analysis at 20, 40, and 80 min after irradiation. Microarray analysis revealed a time-course transcriptional profile of changed gene expressions. Up-regulated genes belonged to the functional categories mainly related to cell cycle and DNA processing, cell rescue defense and virulence, protein and cell fate, and metabolism (X- and {gamma}-rays). Similarly, for X- and {gamma}-rays, the down-regulated genes belonged to mostly transcription and protein synthesis, cell cycle and DNA processing, control of cellular organization, cell fate, and C-compound and carbohydrate metabolism categories, respectively. This study provides for the first time a snapshot of the genome-wide mRNA expression profiles in X- and {gamma}-ray post-irradiated yeast cells and comparatively interprets/discusses the changed gene functional categories as effects of these two radiations vis-a-vis their energy levels.

  12. Mesoscale Benchmark Demonstration Problem 1: Mesoscale Simulations of Intra-granular Fission Gas Bubbles in UO2 under Post-irradiation Thermal Annealing

    SciTech Connect

    Li, Yulan; Hu, Shenyang Y.; Montgomery, Robert; Gao, Fei; Sun, Xin; Tonks, Michael; Biner, Bullent; Millet, Paul; Tikare, Veena; Radhakrishnan, Balasubramaniam; Andersson , David

    2012-04-11

    A study was conducted to evaluate the capabilities of different numerical methods used to represent microstructure behavior at the mesoscale for irradiated material using an idealized benchmark problem. The purpose of the mesoscale benchmark problem was to provide a common basis to assess several mesoscale methods with the objective of identifying the strengths and areas of improvement in the predictive modeling of microstructure evolution. In this work, mesoscale models (phase-field, Potts, and kinetic Monte Carlo) developed by PNNL, INL, SNL, and ORNL were used to calculate the evolution kinetics of intra-granular fission gas bubbles in UO2 fuel under post-irradiation thermal annealing conditions. The benchmark problem was constructed to include important microstructural evolution mechanisms on the kinetics of intra-granular fission gas bubble behavior such as the atomic diffusion of Xe atoms, U vacancies, and O vacancies, the effect of vacancy capture and emission from defects, and the elastic interaction of non-equilibrium gas bubbles. An idealized set of assumptions was imposed on the benchmark problem to simplify the mechanisms considered. The capability and numerical efficiency of different models are compared against selected experimental and simulation results. These comparisons find that the phase-field methods, by the nature of the free energy formulation, are able to represent a larger subset of the mechanisms influencing the intra-granular bubble growth and coarsening mechanisms in the idealized benchmark problem as compared to the Potts and kinetic Monte Carlo methods. It is recognized that the mesoscale benchmark problem as formulated does not specifically highlight the strengths of the discrete particle modeling used in the Potts and kinetic Monte Carlo methods. Future efforts are recommended to construct increasingly more complex mesoscale benchmark problems to further verify and validate the predictive capabilities of the mesoscale modeling

  13. Role of isolated and clustered DNA damage and the post-irradiating repair process in the effects of heavy ion beam irradiation.

    PubMed

    Tokuyama, Yuka; Furusawa, Yoshiya; Ide, Hiroshi; Yasui, Akira; Terato, Hiroaki

    2015-05-01

    Clustered DNA damage is a specific type of DNA damage induced by ionizing radiation. Any type of ionizing radiation traverses the target DNA molecule as a beam, inducing damage along its track. Our previous study showed that clustered DNA damage yields decreased with increased linear energy transfer (LET), leading us to investigate the importance of clustered DNA damage in the biological effects of heavy ion beam radiation. In this study, we analyzed the yield of clustered base damage (comprising multiple base lesions) in cultured cells irradiated with various heavy ion beams, and investigated isolated base damage and the repair process in post-irradiation cultured cells. Chinese hamster ovary (CHO) cells were irradiated by carbon, silicon, argon and iron ion beams with LETs of 13, 55, 90 and 200 keV µm(-1), respectively. Agarose gel electrophoresis of the cells with enzymatic treatments indicated that clustered base damage yields decreased as the LET increased. The aldehyde reactive probe procedure showed that isolated base damage yields in the irradiated cells followed the same pattern. To analyze the cellular base damage process, clustered DNA damage repair was investigated using DNA repair mutant cells. DNA double-strand breaks accumulated in CHO mutant cells lacking Xrcc1 after irradiation, and the cell viability decreased. On the other hand, mouse embryonic fibroblast (Mef) cells lacking both Nth1 and Ogg1 became more resistant than the wild type Mef. Thus, clustered base damage seems to be involved in the expression of heavy ion beam biological effects via the repair process. © The Author 2015. Published by Oxford University Press on behalf of The Japan Radiation Research Society and Japanese Society for Radiation Oncology.

  14. Role of isolated and clustered DNA damage and the post-irradiating repair process in the effects of heavy ion beam irradiation

    PubMed Central

    Tokuyama, Yuka; Furusawa, Yoshiya; Ide, Hiroshi; Yasui, Akira; Terato, Hiroaki

    2015-01-01

    Clustered DNA damage is a specific type of DNA damage induced by ionizing radiation. Any type of ionizing radiation traverses the target DNA molecule as a beam, inducing damage along its track. Our previous study showed that clustered DNA damage yields decreased with increased linear energy transfer (LET), leading us to investigate the importance of clustered DNA damage in the biological effects of heavy ion beam radiation. In this study, we analyzed the yield of clustered base damage (comprising multiple base lesions) in cultured cells irradiated with various heavy ion beams, and investigated isolated base damage and the repair process in post-irradiation cultured cells. Chinese hamster ovary (CHO) cells were irradiated by carbon, silicon, argon and iron ion beams with LETs of 13, 55, 90 and 200 keV µm−1, respectively. Agarose gel electrophoresis of the cells with enzymatic treatments indicated that clustered base damage yields decreased as the LET increased. The aldehyde reactive probe procedure showed that isolated base damage yields in the irradiated cells followed the same pattern. To analyze the cellular base damage process, clustered DNA damage repair was investigated using DNA repair mutant cells. DNA double-strand breaks accumulated in CHO mutant cells lacking Xrcc1 after irradiation, and the cell viability decreased. On the other hand, mouse embryonic fibroblast (Mef) cells lacking both Nth1 and Ogg1 became more resistant than the wild type Mef. Thus, clustered base damage seems to be involved in the expression of heavy ion beam biological effects via the repair process. PMID:25717060

  15. Pre- and post-irradiation fading effect for LiF:Mg,Ti and LiF:Mg,Cu,P materials used in routine monitoring.

    PubMed

    Carinou, E; Askounis, P; Dimitropoulou, F; Kiranos, G; Kyrgiakou, H; Nirgianaki, E; Papadomarkaki, E; Kamenopoulou, V

    2011-03-01

    LiF is a well-known thermoluminescent (TL) material used in individual monitoring, and its fading characteristics have been studied for years. In the present study, the fading characteristics (for a period of 150 d) of various commercial LiF materials with different dopants have been evaluated. The materials used in the study are those used in routine procedures by the Personal Dosimetry Department of Greek Atomic Energy Commission and in particular, LiF:Mg,Ti (MTS-N, TL Poland), LiF:Mg,Cu,P (MCP-N, TL Poland), LiF:Mg,Cu,P (MCP-Ns, thin active layer detector, TL Poland) and LiF:Mg,Cu,P (TLD100H, Harshaw). The study showed that there is a sensitivity loss in signal of up to 20 % for the MTS-N material for a 150-d period in the pre-irradiation fading phase. The MCP-N has a stable behaviour in the pre-irradiation fading phase, but this also depends on the readout system. As far as the post-irradiation fading effect is concerned, a decrease of up to 20 % for the MTS-N material is observed for the same time period. On the other hand, the LiF:Mg,Cu,P material presents a stable behaviour within ± 5 %. These results show that the fading effect is different for each material and should be taken into account when estimating doses from dosemeters that are in use for >2 months.

  16. Coping with information silos: an examination of the medication management process in residential aged care facilities (RACFs).

    PubMed

    Tariq, Amina; Georgiou, Andrew; Westbrook, Johanna

    2014-01-01

    The aim of this study was to examine the actions of geographically dispersed process stakeholders (doctors, community pharmacists and RACFs) in order to cope with the information silos that exist within and across different settings. The study setting involved three metropolitan RACFs in Sydney, Australia and employed a qualitative approach using semi-structured interviews, non-participant observations and artefact analysis. Findings showed that medication information was stored in silos which required specific actions by each setting to translate this information to fit their local requirements. A salient example of this was the way in which community pharmacists used the RACF medication charts to prepare residents' pharmaceutical records. This translation of medication information across settings was often accompanied by telephone or face-to-face conversations to cross-check, validate or obtain new information. Findings highlighted that technological interventions that work in silos can negatively impact the quality of medication management processes in RACF settings. The implementation of commercial software applications like electronic medication charts need to be appropriately integrated to satisfy the collaborative information requirements of the RACF medication process.

  17. Examining the radiation drive asymmetries present in the high foot series of implosion experiments at the National Ignition Facility

    DOE PAGES

    Pak, A.; Divol, L.; Kritcher, A. L.; ...

    2017-03-24

    This paper details and examines the origins of radiation drive asymmetries present during the initial High Foot implosion experiments. Such asymmetries are expected to reduce the stagnation pressure and the resulting yield of these experiments by several times. Analysis of reemission and dual axis shock timing experiments indicates that a flux asymmetry, with a P2/P0 amplitude that varies from -10 to -5 %, is present during the first shock of the implosion. This first shock asymmetry can be corrected through adjustments to the laser cone fraction. A thin shell model and more detailed radiation hydrodynamic calculations indicate that an additionalmore » negative P2/P0 asymmetry during the second or portions of the third shock is required to reach the observed amount of asymmetry in the shape of the ablator at peak implosion velocity. In conjunction with symmetry data from the x-ray self emission produced at stagnation, these models also indicate that after the initially negative P2/P0 flux asymmetry, the capsule experiences a positive P2/P0 flux asymmetry that develops at or before ~2 ns into the peak of the laser power. Here, direct evidence for this inference, using measurements of the x-ray emission produced by the lasers irradiating the hohlraum, is presented. This data indicates that the reduction in the transmitted inner laser cone energy results from impeded propagation through the plasma associated with the ablation of the capsule target. This paper also correlates measurements of the outer cone laser deposition location with variations in the observed x-ray self emission shape from experiments conducted with nominally the same input conditions.« less

  18. Examining the radiation drive asymmetries present in the high foot series of implosion experiments at the National Ignition Facility

    NASA Astrophysics Data System (ADS)

    Pak, A.; Divol, L.; Kritcher, A. L.; Ma, T.; Ralph, J. E.; Bachmann, B.; Benedetti, L. R.; Casey, D. T.; Celliers, P. M.; Dewald, E. L.; Döppner, T.; Field, J. E.; Fratanduono, D. E.; Berzak Hopkins, L. F.; Izumi, N.; Khan, S. F.; Landen, O. L.; Kyrala, G. A.; LePape, S.; Millot, M.; Milovich, J. L.; Moore, A. S.; Nagel, S. R.; Park, H.-S.; Rygg, J. R.; Bradley, D. K.; Callahan, D. A.; Hinkel, D. E.; Hsing, W. W.; Hurricane, O. A.; Meezan, N. B.; Moody, J. D.; Patel, P.; Robey, H. F.; Schneider, M. B.; Town, R. P. J.; Edwards, M. J.

    2017-05-01

    This paper details and examines the origins of radiation drive asymmetries present during the initial High Foot implosion experiments. Such asymmetries are expected to reduce the stagnation pressure and the resulting yield of these experiments by several times. Analysis of reemission and dual axis shock timing experiments indicates that a flux asymmetry, with a P2/P0 amplitude that varies from -10% to -5%, is present during the first shock of the implosion. This first shock asymmetry can be corrected through adjustments to the laser cone fraction. A thin shell model and more detailed radiation hydrodynamic calculations indicate that an additional negative P2/P0 asymmetry during the second or portions of the third shock is required to reach the observed amount of asymmetry in the shape of the ablator at peak implosion velocity. In conjunction with symmetry data from the x-ray self emission produced at stagnation, these models also indicate that after the initially negative P2/P0 flux asymmetry, the capsule experiences a positive P2/P0 flux asymmetry that develops at or before ˜2 ns into the peak of the laser power. Here, direct evidence for this inference, using measurements of the x-ray emission produced by the lasers irradiating the hohlraum, is presented. These data indicate that the reduction in the transmitted inner laser cone energy results from impeded propagation through the plasma associated with the ablation of the capsule target. This paper also correlates measurements of the outer cone laser deposition location with variations in the observed x-ray self emission shape from experiments conducted with nominally the same input conditions.

  19. Irradiation of Argentine (U,Pu)O 2 MOX fuels. Post-irradiation results and experimental analysis with the BACO code

    NASA Astrophysics Data System (ADS)

    Marino, Armando Carlos; Pérez, Edmundo; Adelfang, Pablo

    1996-04-01

    The irradiation of the first Argentine prototypes of pressurized heavy water reactor (PHWR) (U,Pu)O 2 MOX fuels began in 1986. These experiments were carried out in the High Flux Reactor (HFR)-Petten, Holland. The rods were prepared and controlled in the CNEA's α Facility. The postirradiation examinations were performed in the Kernforschungszentrum, Karlsruhe, Germany and in the Joint Research Center (JRC), Petten. The first rod has been used for destructive pre-irradiation analysis. The second one as a pathfinder to adjust systems in the HFR. Two additional rods including iodine doped pellets were intended to simulate 15 000 MWd/T(M) burnup. The remaining two rods were irradiated until 15 000 MWd/T(M). One of them underwent a final ramp with the aim of verifying fabrication processes and studying the behaviour under power transients. BACO (BArra COmbustible) code was used to define the power histories and to analyse the experiments. This paper presents a description of the different experiments and a comparison between the results of the postirradiation examinations and the BACO outputs.

  20. Downgrading Nuclear Facilities to Radiological Facilities

    SciTech Connect

    Jarry, Jeffrey F.; Farr, Jesse Oscar; Duran, Leroy

    2015-08-01

    Based on inventory reductions and the use of alternate storage facilities, the Sandia National Laboratories (SNL) downgraded 4 SNL Hazard Category 3 (HC-3) nuclear facilities to less-than-HC-3 radiological facilities. SNL’s Waste Management and Pollution Prevention Department (WMPPD) managed the HC-3 nuclear facilities and implemented the downgrade. This paper will examine the downgrade process,

  1. An Examination of the Conditions of School Facilities Attended by 10th-Grade Students in 2002. E.D. TAB. NCES 2006-302

    ERIC Educational Resources Information Center

    Mike Planty; Jill F. DeVoe; Jeffrey A. Owings; Kathryn Chandler

    2005-01-01

    This report presents key findings from the Education Longitudinal Study of 2002 (ELS:2002) Facilities Checklist for all ELS:2002 public and private schools and students in the 10th grade. The facilities instrument was administered as a part of the ELS:2002 and focused on the conditions of school facilities, including disrepair, cleanliness,…

  2. Burnup Predictions for Metal Fuel Tests in the Fast Flux Test Facility

    SciTech Connect

    Wootan, David W.; Nelson, Joseph V.

    2012-06-01

    The Fast Flux Test Facility (FFTF) is the most recent Liquid Metal Reactor (LMR) to be designed, constructed, and operated by the U.S. Department of Energy (DOE). The FFTF operated successfully from initial startup in 1980 through the end of the last operating cycle in March, 1992. A variety of fuel tests were irradiated in FFTF to provide performance data over a range of conditions. The MFF-3 and MFF-5 tests were U10Zr metal fuel tests with HT9 cladding. The MFF-3 and MFF-5 tests were both aggressive irradiation tests of U10Zr metal fuel pins with HT9 cladding that were prototypic of full scale LMR designs. MFF-3 was irradiated for 726 Effective Full Power Days (EFPD), starting from Cycle 10C1 (from November 1988 through March 1992), and MFF-5 was irradiated for 503 EFPD starting from Cycle 11B1 (from January 1990 through March 1992). A group of fuel pins from these two tests are undergoing post irradiation examination at the Idaho National Laboratory (INL) for the Fuel Cycle Research and Development Program (FCRD). The generation of a data package of key information on the irradiation environment and current pin detailed compositions for these tests is described. This information will be used in interpreting the results of these examinations.

  3. Facility Focus: Sports and Recreation Facilities.

    ERIC Educational Resources Information Center

    College Planning & Management, 2000

    2000-01-01

    Examines projects that demonstrate three different commitments administrators make to their athletic facilities: convenience; excellence; and comfort. Projects discussed involve a fitness center, a football stadium, and a multi-sport indoor practice facility. (GR)

  4. Facility Focus: Sports and Recreation Facilities.

    ERIC Educational Resources Information Center

    College Planning & Management, 2000

    2000-01-01

    Examines projects that demonstrate three different commitments administrators make to their athletic facilities: convenience; excellence; and comfort. Projects discussed involve a fitness center, a football stadium, and a multi-sport indoor practice facility. (GR)

  5. Neutron and gamma-ray nondestructive examination of contact-handled transuranic waste at the ORNL TRU Waste Drum Assay Facility

    SciTech Connect

    Schultz, F.J.; Coffey, D.E.; Norris, L.B.; Haff, K.W.

    1985-03-01

    A nondestructive assay system, which includes the Neutron Assay System (NAS) and the Segmented Gamma Scanner (SGS), for the quantification of contact-handled (<200 mrem/h total radiation dose rate at contact with container) transuranic elements (CH-TRU) in bulk solid waste contained in 208-L and 114-L drums has been in operation at the Oak Ridge National Laboratory since April 1982. The NAS has been developed and demonstrated by Los Alamos National Laboratory (LANL) and the Oak Ridge National Laboratory (ORNL) for use by most US Department of Energy Defense Plant (DOE-DP) sites. More research and development is required, however, before the NAS can provide complete assay results for other than routine defense waste. To date, 525 ORNL waste drums have been assayed, with varying degrees of success. The isotopic complexity of the ORNL waste creates a correspondingly complex assay problem. The NAS and SGS assay data are presented and discussed. Neutron matrix effects, the destructive examination facility, and enriched uranium fuel-element assays are also discussed.

  6. Effects of post-irradiation annealing and re-irradiation on microstructure in surveillance test specimens of the Loviisa-1 reactor studied by atom probe tomography and positron annihilation

    NASA Astrophysics Data System (ADS)

    Toyama, T.; Kuramoto, A.; Nagai, Y.; Inoue, K.; Nozawa, Y.; Shimizu, Y.; Matsukawa, Y.; Hasegawa, M.; Valo, M.

    2014-06-01

    This paper presents a microstructural study of a surveillance test specimen from the Loviisa-1 reactor in Finland, which is a Russian-type pressurized water reactor (VVER-440), after initial irradiation to a neutron fluence of 2.5 × 1019 n/cm2 (E > 1 MeV), post-irradiation annealing at 475 °C for 100 h and re-irradiation to three different fluences up to 2.7 × 1019 n/cm2. Atom probe tomography (APT) and positron annihilation spectroscopy (PAS) were used to characterize the test specimens. APT results showed the formation of Cu-rich solute clusters (SCs) during the initial irradiation and their subsequent coarsening during annealing. After re-irradiation, a small number of SCs formed once again. The hardening due to the SCs was estimated using the Russell-Brown model based on the APT results, and was in good agreement with the measured hardening after the initial irradiation and post-irradiation annealing. In contrast, during the first-step of re-irradiation, the estimated hardening due to the SCs was smaller than the measured hardening. This suggested that the hardening after re-irradiation was due to some microstructure other than the observed SCs. This difference was attributed to newly-formed matrix defects during re-irradiation, which was supported by the PAS results. However in subsequent steps of re-irradiation, the hardening was almost constant.

  7. Assessment of the Idaho National Laboratory Hot Fuel Examination Facility Stack Monitoring Site for Compliance with ANSI/HPS N13.1 1999

    SciTech Connect

    Glissmeyer, John A.; Flaherty, Julia E.

    2010-08-27

    This document reports on a series of tests to determine whether the location of the air sampling probe in the Hot Fuels Examination Facility (HFEF) heating, ventilation and air conditioning (HVAC) exhaust duct meets the applicable regulatory criteria regarding the placement of an air sampling probe. Federal regulations require that a sampling probe be located in the exhaust stack according to the criteria of the ANSI/HPS N13.1-1999, Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stacks and Ducts of Nuclear Facilities. These criteria address the capability of the sampling probe to extract a sample that is representative of the effluent stream. The tests conducted by PNNL during July 2010 on the HFEF system are described in this report. The sampling probe location is approximately 20 feet from the base of the stack. The stack base is in the second floor of the HFEF, and has a building ventilation stream (limited potential radioactive effluent) as well as a process stream (potential radioactive effluent, but HEPA-filtered) that feeds into it. The tests conducted on the duct indicate that the process stream is insufficiently mixed with the building ventilation stream. As a result, the air sampling probe location does not meet the criteria of the N13.1-1999 standard. The series of tests consists of various measurements taken over a grid of points in the duct cross section at the proposed sampling-probe location. The results of the test series on the HFEF exhaust duct as it relates to the criteria from ANSI/HPS N13.1-1999 are desribed in this report. Based on these tests, the location of the air sampling probe does not meet the requirements of the ANSI/HPS N13.1-1999 standard, and modifications must be made to either the HVAC system or the air sampling probe for compliance. The recommended approaches are discussed and vary from sampling probe modifications to modifying the junction of the two air exhaust streams.

  8. Examination of the Relationship among Hearing Impairment, Linguistic Communication, Mood, and Social Engagement of Residents in Complex Continuing-Care Facilities

    ERIC Educational Resources Information Center

    Brink, Peter; Stones, Michael

    2007-01-01

    Earlier evidence was not conclusive about whether hearing loss is associated with mood (i.e., depressive symptoms and anhedonia) and social engagement (i.e., reduced psychosocial involvement and reduced activity levels) in elderly residents living in complex continuing-care facilities. If hearing impairment results in poor mood and lower levels of…

  9. Examination of the Relationship among Hearing Impairment, Linguistic Communication, Mood, and Social Engagement of Residents in Complex Continuing-Care Facilities

    ERIC Educational Resources Information Center

    Brink, Peter; Stones, Michael

    2007-01-01

    Earlier evidence was not conclusive about whether hearing loss is associated with mood (i.e., depressive symptoms and anhedonia) and social engagement (i.e., reduced psychosocial involvement and reduced activity levels) in elderly residents living in complex continuing-care facilities. If hearing impairment results in poor mood and lower levels of…

  10. Facility effluent monitoring plan determinations for the 400 Area facilities

    SciTech Connect

    Nickels, J.M.

    1991-09-01

    This Facility Effluent Monitoring Plan determination resulted from an evaluation conducted for the Westinghouse Hanford Company 400 Area facilities on the Hanford Site. The Facility Effluent Monitoring Plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans. Two major Westinghouse Hanford Company facilities in the 400 Area were evaluated: the Fast Flux Test Facility and the Fuels Manufacturing and examination Facility. The determinations were prepared by Westinghouse Hanford Company. Of these two facilities, only the Fast Flux Test Facility will require a Facility Effluent Monitoring Plan. 7 refs., 5 figs., 4 tabs.

  11. Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research

    SciTech Connect

    John Jackson; Todd Allen; Frances Marshall; Jim Cole

    2013-03-01

    The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue University’s Interaction of Materials

  12. Indoor Athletic Facilities.

    ERIC Educational Resources Information Center

    Fleming, E. Scott

    2000-01-01

    Examines the concept of shared-use facilities to help financially support and meet the demand for athletic facilities. Shared-use considerations are explored including cost sharing of ongoing operations, aesthetics, locker rooms, support facilities, parking and site access, and building access and security. (GR)

  13. Examining the Quality of Medicines at Kenyan Healthcare Facilities: A Validation of an Alternative Post-Market Surveillance Model That Uses Standardized Patients.

    PubMed

    Wafula, Francis; Dolinger, Amy; Daniels, Benjamin; Mwaura, Njeri; Bedoya, Guadalupe; Rogo, Khama; Goicoechea, Ana; Das, Jishnu; Olayo, Bernard

    2017-03-01

    Promoting access to medicines requires concurrent efforts to strengthen quality assurance for sustained impact. Although problems of substandard and falsified medicines have been documented in low- and middle-income countries, reliable information on quality is rarely available. The aim of this study was to validate an alternative post-market surveillance model to complement existing models. The study used standardized patients or mystery clients (people recruited from the local community and trained to pose as real patients) to collect medicine samples after presenting a pre-specified condition. The patients presented four standardized conditions to 42 blinded facilities in Nairobi, Kenya, resulting in 166 patient-clinician interactions and dispensing of 300 medicines at facilities or nearby retail pharmacies. The medicine samples obtained thus resemble those that would be given to real patients. Sixty samples were selected from the 300, and sent for analysis at the Kenya National Quality Control Laboratory. Of these, ten (17%) did not comply with monograph specifications (three ibuprofen, two cetirizine, two amoxicillin/clavulanic acid combinations, and one each for prednisone, salbutamol and zinc). Five of the ten samples that failed had been inappropriately prescribed to patients who had presented symptoms of unstable angina. There was no association between medicine quality and ownership, size or location of the facilities. The study shows that the standardized patient model can provide insights into multiple dimensions of care, thus helping to link primary care encounters with medicine quality. Furthermore, it makes it possible to obtain medicines from blinded sellers, thus minimizing the risk of obtaining biased samples.

  14. National Postirradiation Examination Workshop Report

    SciTech Connect

    Schulthess, Jason L

    2011-06-01

    A National Post-Irradiation-Examination (PIE) Workshop was held March 29-30, 2011, in Washington D.C., stimulated by the DOE Acting Assistant Secretary for Nuclear Energy approval on January 31, 2011 of the “Mission Need Statement for Advanced Post-Irradiation Examination Capability”. As stated in the Mission Need, “A better understanding of nuclear fuels and material performance in the nuclear environment, at the nanoscale and lower, is critical to the development of innovative fuels and materials required for tomorrow’s nuclear energy systems.” (2011) Developing an advanced post-irradiation capability is the most important thing we can do to advance nuclear energy as an option to meeting national energy goals. Understanding the behavior of fuels and materials in a nuclear reactor irradiation environment is the limiting factor in nuclear plant safety, longevity, efficiency, and economics. The National PIE Workshop is part of fulfilling or addressing Department of Energy (DOE) missions in safe and publically acceptable nuclear energy. Several presentations were given during the opening of the workshop. Generally speaking, these presentations established that we cannot continue to rely on others in the world to provide the capabilities we need to move forward with nuclear energy technology. These presentations also generally identified the need for increased microstructural understanding of fuels and materials to be coupled with modeling and simulation, and increased accessibility and infrastructure to facilitate the interaction between national laboratories and participating organizations. The overall results of the work of the presenters and panels was distilled into four primary needs 1. Understanding material changes in the extreme nuclear environment at the nanoscale. Nanoscale studies have significant importance due to the mechanisms that cause materials to degrade, which actually occur on the nanoscale. 2. Enabling additional proficiency in

  15. Preparing a Facilities Master Plan

    ERIC Educational Resources Information Center

    Kalina, David

    2006-01-01

    This article examines the steps in creating a facilities master plan. The facilities master plan is a long-range look at the development of one's facilities, combined with an implementation plan that indicates the steps, sequence and costs to get one there. There are three basic steps: (1) analyzing what one has (assessing one's facilities to…

  16. Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9

    NASA Astrophysics Data System (ADS)

    Harp, Jason M.; Porter, Douglas L.; Miller, Brandon D.; Trowbridge, Tammy L.; Carmack, William J.

    2017-10-01

    Observations from a scanning electron microscopy examination of irradiated U-10Zr fuel are presented. The sample studied had a local burnup of 5.7 atom percent and a local inner cladding temperature of 615 °C. This examination by electron microscopy has concentrated on producing data relevant to facilitating a better understanding of Zr redistribution in irradiated U-10Zr fuel and on a better understanding of the complex microstructure present in fuel cladding chemical interaction (FCCI) layers. The presented zirconium redistribution data supplements the existing literature by providing a data set at these particular local conditions. In addition to FCCI layers that are readily visible in optical microscopy, this examination has revealed lanthanide degradation of the cladding by what appears to be a grain boundary facilitated pathway. Precipitates of fission produced Pd-lanthanide compounds were observed in the fuel. Precipitated regions with elevated Mo and elevated W content were also observed in the HT-9 cladding of this sample.

  17. Combined therapy for post-irradiation infection

    SciTech Connect

    Elliott, T.B.; Madonna, G.S.; Ledney, G.D.; Brook, I.

    1989-01-01

    Increased susceptibility to bacterial infection, probably by translocation from the intestinal flora, can be a lethal complication for 2-3 weeks after exposure to ionizing radiation. Antibiotics alone do not provide adequate therapy for induced infections in neutropenic mice. Because some substances that are derived from bacterial cell walls activate macrophages and stimulate nonspecific resistance to infection, such agents might be used to prevent or treat postirradiation infections. In this study, a cell-wall glycolipid, trehalose dimycolate (TDM), was evaluated together with a third-generation cephalosporin, ceftriaxone, for their separate and combined effects on survival of B6D2F1 female mice that were exposed to the sublethal dose of 7.0 Gy Co radiation and challenged s.c. with lethal doses of Klebsiella pneumoniae. A single injection of TDM inoculated i.p. 1 hr postirradiation increased 30-day survival to 80% after a lethal challenge by K. pneumoniae 4 days later. When the challenge dose of K. pneumoniae was increased to 5000 Ld 50/30 on Day 4, all mice died.

  18. Facility Microgrids

    SciTech Connect

    Ye, Z.; Walling, R.; Miller, N.; Du, P.; Nelson, K.

    2005-05-01

    Microgrids are receiving a considerable interest from the power industry, partly because their business and technical structure shows promise as a means of taking full advantage of distributed generation. This report investigates three issues associated with facility microgrids: (1) Multiple-distributed generation facility microgrids' unintentional islanding protection, (2) Facility microgrids' response to bulk grid disturbances, and (3) Facility microgrids' intentional islanding.

  19. Advanced Test Reactor National Scientific User Facility Progress

    SciTech Connect

    Frances M. Marshall; Todd R. Allen; James I. Cole; Jeff B. Benson; Mary Catherine Thelen

    2012-10-01

    cannot be met using the INL facilities. The ATR NSUF program includes a robust education program enabling students to participate in their research at INL and the partner facilities, attend the ATR NSUF annual User Week, and compete for prizes at sponsored conferences. Development of additional research capabilities is also a key component of the ATR NSUF Program; researchers are encouraged to propose research projects leading to these enhanced capabilities. Some ATR irradiation experiment projects irradiate more specimens than are tested, resulting in irradiated materials available for post irradiation examination by other researchers. These “extra” specimens comprise the ATR NSUF Sample Library. This presentation will highlight the ATR NSUF Sample Library and the process open to researchers who want to access these materials and how to propose research projects using them. This presentation will provide the current status of all the ATR NSUF Program elements. Many of these were not envisioned in 2007, when DOE established the ATR NSUF.

  20. Shaping Campus Facilities.

    ERIC Educational Resources Information Center

    Calcara, James R.

    1999-01-01

    Explains how colleges and universities, faced with emerging trends and increased competition, can utilize their facilities as strategic resources. Examines technology changes in the classroom and the effects on user needs, the trend toward real-world learning environments, and facility design planning that responds to social interaction and…

  1. Shaping Campus Facilities.

    ERIC Educational Resources Information Center

    Calcara, James R.

    1999-01-01

    Explains how colleges and universities, faced with emerging trends and increased competition, can utilize their facilities as strategic resources. Examines technology changes in the classroom and the effects on user needs, the trend toward real-world learning environments, and facility design planning that responds to social interaction and…

  2. Facility Focus: Food Service.

    ERIC Educational Resources Information Center

    College Planning & Management, 2000

    2000-01-01

    Examines three renovated college facilities that offer student-friendly dining space. Renovation problems in the areas of food and entertainment, service and choice, and image versus architectural history preservation are addressed. (GR)

  3. Rendezvous facilities

    SciTech Connect

    Gehani, N.H.; Roome, W.D.

    1988-11-01

    The concurrent programming facilities in both Concurrent C and the Ada language are based on the rendezvous concept. Although these facilities are similar, there are substantial differences. Facilities in Concurrent C were designed keeping in perspective the concurrent programming facilities in the Ada language and their limitations. Concurrent C facilities have also been modified as a result of experience with its initial implementations. In this paper, the authors compare the concurrent programming facilities in Concurrent C and Ada, and show that it is easier to write a variety of concurrent programs in Concurrent C than in Ada.

  4. Preservation Impacts on Educational Facilities Planning.

    ERIC Educational Resources Information Center

    Shultz, James A.

    This paper examines the significance of facilities preservation for educational facilities planning and identifies various forms of facilities preservation applicable to educational facilities. It analyzes why educational facilities planners need to be aware of preservation considerations, reviews the relevant literature for preservation…

  5. Skylab Dental Examination

    NASA Technical Reports Server (NTRS)

    1973-01-01

    Skylab 2 Commander Charles Conrad is seen undergoing a dental examination by the Medical Officer, Joseph Kerwin in the Skylab Medical Facility. In the absence of an examination chair, Conrad simply rotated his body to an upside down position to facilitate the procedure.

  6. Examining appropriate diagnosis and treatment of malaria: availability and use of rapid diagnostic tests and artemisinin-based combination therapy in public and private health facilities in south east Nigeria

    PubMed Central

    2010-01-01

    Background Rapid diagnostic tests (RDTs) and Artemisinin-based combination therapy (ACT) have been widely advocated by government and the international community as cost-effective tools for diagnosis and treatment of malaria. ACTs are now the first line treatment drug for malaria in Nigeria and RDTs have been introduced by the government to bridge the existing gaps in proper diagnosis. However, it is not known how readily available these RDTs and ACTs are in public and private health facilities and whether health workers are actually using them. Hence, this study investigated the levels of availability and use of RDTs and ACTs in these facilities. Methods The study was undertaken in Enugu state, southeast Nigeria in March 2009. Data was collected from heads of 74 public and private health facilities on the availability and use of RDTs and ACTs. Also, the availability of RDTs and the types of ACTs that were available in the facilities were documented. Results Only 31.1% of the health facilities used RDTs to diagnose malaria. The majority used the syndromic approach. However, 61.1% of healthcare providers were aware of RDTs. RDTs were available in 53.3% of the facilities. Public health facilities and health facilities in the urban areas were using RDTs more and these were mainly bought from pharmacy shops and supplied by NGOs. The main reasons given for non use are unreliability of RDTs, supply issues, costs, preference for other methods of diagnosis and providers' ignorance. ACTs were the drug of choice for most public health facilities and the drugs were readily available in these facilities. Conclusion Although many providers were knowledgeable about RDTs, not many facilities used it. ACTS were readily available and used in public but not private health facilities. However, the reported use of ACTs with limited proper diagnosis implies that there could be high incidence of inappropriate case management of malaria which can also increase the economic burden of

  7. Arcjet Facility

    DTIC Science & Technology

    1991-09-01

    PL-TR--91-3085 PL-TR-- ________AD-A243 948 1-8 ARCJET FACILITY Captain Salvador Castillo October 1991 OVa99 Final Report - - A P P R O V...REPORT DATE 3. REPORT TYPE AND DATES COVERED September 1991 Final Aug 86 to Aug 91 4. TITLE AND SUBTITLE 5. FUNDING NUMBERS ARCJET FACILITY PE- 62302F...Electric Propulsion Laboratory has designed and begun installation of an arcjet research facility. A 5 foot by 10 foot long chamber with eight 12 inch

  8. Health Facilities

    MedlinePlus

    Health facilities are places that provide health care. They include hospitals, clinics, outpatient care centers, and specialized care centers, such as birthing centers and psychiatric care centers. When you ...

  9. Facility Planning.

    ERIC Educational Resources Information Center

    Graves, Ben E.

    1984-01-01

    This article reviews recommendations on policies for leasing surplus school space made during the Council of Educational Facility Planners/International conference. A case study presentation of a Seattle district's use of lease agreements is summarized. (MJL)

  10. QF monitoring. [Qualifying Facilities

    SciTech Connect

    Greenwald, S. ); Hoffman, B. )

    1991-10-01

    This article examines the effects on project financing of independent power projects of the California Public Utilities Commission decision to grant authority to California utilities to monitor and enforce compliance with the Federal Energy Regulatory Commission Qualifying Facility standards. The topics of the article include monitoring proposals, monitoring guidelines, the effects of monitoring, minimizing status loss and monitoring requirements.

  11. Educational Facilities in Korea.

    ERIC Educational Resources Information Center

    PEB Exchange, 1999

    1999-01-01

    Describes a Korean program to modernize school buildings and equipment to better meet current teaching needs.Examines Korea's education and administrative systems, and the Ministry of Education's involvement in schooling trends, facilities for higher education, and developments in information and technology. (GR)

  12. State School Facility Programs Overview.

    ERIC Educational Resources Information Center

    California State Dept. of General Services, Sacramento. Office of Public School Construction.

    This overview examines California's various State Allocation Board's funding programs for the construction, modernization, and maintenance of local school facilities. Funding information is provided for each program as are explanations of the school facility program construction process and the lease purchase program. The organizational chart for…

  13. Facility rehabilitation

    Treesearch

    Edwin H. Ketchledge

    1971-01-01

    Restoration of vegetation on damaged sites is the most perplexing challenge in facility rehabilitation. In the Adirondack Mountains, the ecological impact of recreationists on the natural environment has become critical in two high-quality interior areas: on the steep higher slopes where trails soon become eroding stream channels, washing away the thin mountain soils;...

  14. Facilities Management.

    ERIC Educational Resources Information Center

    Bete, Tim, Ed.

    1998-01-01

    Presents responses from Matt McGovern, "School Planning and Management's" Maintenance and Operations columnist, on the issue of school facility maintenance. McGovern does not believe schools will ever likely meet acceptable levels of maintenance, nor use infrared thermography for assessing roofs, outsource all maintenance work, nor find…

  15. Asian Facilities

    NASA Astrophysics Data System (ADS)

    Nakahata, M.

    2011-04-01

    Asian underground facilities are reviewed. The YangYang underground Laboratory in Korea and the Kamioka observatory in Japan are operational and several astrophysical experiments are running. Indian Neutrino Observatory(INO) and China JinPing Underground Laboratory (CJPL) are under construction and underground experiments are being prepared. Current activities and future prospects at those underground sites are described.

  16. Life science payloads planning study integration facility survey results

    NASA Technical Reports Server (NTRS)

    Wells, G. W.; Brown, N. E.; Nelson, W. G.

    1976-01-01

    The integration facility survey effort described is structured to examine the facility resources needed to conduct life science payload (LSP) integration checkout activities at NASA-JSC. The LSP integration facility operations and functions are defined along with the LSP requirements for facility design. A description of available JSC life science facilities is presented and a comparison of accommodations versus requirements is reported.

  17. 7 CFR 800.26 - Access to records and facilities.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 7 2010-01-01 2010-01-01 false Access to records and facilities. 800.26 Section 800... Recordkeeping and Access to Facilities § 800.26 Access to records and facilities. (a) Inspection of records and facilities. Prior to the examination of records or inspection of facilities by an authorized...

  18. Ear examination

    MedlinePlus

    ... page: //medlineplus.gov/ency/article/003340.htm Ear examination To use the sharing features on this page, ... ear References King EF, Couch ME. History, physical examination, and the preoperative evaluation. In: Flint PW, Haughey ...

  19. Mission analysis report - deactivation facilities at Hanford

    SciTech Connect

    Lund, D.P.

    1996-09-27

    This document examines the portion of the Hanford Site Cleanup Mission that deals with facility deactivation. How facilities get identified for deactivation, how they enter EM-60 for deactivation, programmatic alternatives to perform facility deactivation, the deactivation process itself, key requirements and objectives associated with the deactivation process, and deactivation planning are discussed.

  20. Challenges for proteomics core facilities.

    PubMed

    Lilley, Kathryn S; Deery, Michael J; Gatto, Laurent

    2011-03-01

    Many analytical techniques have been executed by core facilities established within academic, pharmaceutical and other industrial institutions. The centralization of such facilities ensures a level of expertise and hardware which often cannot be supported by individual laboratories. The establishment of a core facility thus makes the technology available for multiple researchers in the same institution. Often, the services within the core facility are also opened out to researchers from other institutions, frequently with a fee being levied for the service provided. In the 1990s, with the onset of the age of genomics, there was an abundance of DNA analysis facilities, many of which have since disappeared from institutions and are now available through commercial sources. Ten years on, as proteomics was beginning to be utilized by many researchers, this technology found itself an ideal candidate for being placed within a core facility. We discuss what in our view are the daily challenges of proteomics core facilities. We also examine the potential unmet needs of the proteomics core facility that may also be applicable to proteomics laboratories which do not function as core facilities. Copyright © 2011 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  1. Advanced analytical facilities report of the planetary materials and geochemistry working group

    NASA Technical Reports Server (NTRS)

    1988-01-01

    The role of advanced analytical facilities; upgrading/replacement of the existing facilities; the relationship of advanced facilities to the present program; and possible facilities are examined. Major conclusions and recommendations are presented.

  2. National Postirradiation Examination Workshop Needs Assessment

    SciTech Connect

    Not listed

    2011-09-01

    The development of nuclear fuels and materials requires a clear understanding of irradiation effects on the materials performance. Development of this understanding at present relies on irradiation experiments ranging from tests aimed at targeted phenomenology to integral effects under both prototypic and off-normal conditions. Within the new DOE paradigm of a science-based approach aimed at more fundamental understanding of fuel performance, more specialized experiments and measurements are needed. To support the development of such fuels and materials, especially under a science-based development strategy, the nation needs a consolidated, state-of-the-art, post-irradiation examination (PIE) capability that can reliably extract the needed data from the experimental programs. In some cases, new capabilities beyond the current state-of-the art need to be developed and implemented to perform measurements that were not needed in the more empirically based approaches used in earlier fuel development and qualification programs. A national PIE workshop was held in March 2011 which solicited the PIE needs that are necessary to support both DOE and U.S. goals for nuclear energy. These needs recognize that significant capability already exists that must be maintained, upgraded and continued while bringing online new capabilities that support research on highly irradiated fuels and materials. Further, these needs mostly focus on the reducing the time and length scales in which materials can be examined and coupling these measurements with a robust modeling capability within an infrastructure that can meet the needs of higher demand and a variety of customers. A consolidated capability where a comprehensive set of measurements can be simultaneously performed is essential for efficiently implementing fuel and materials development programs in a cost effective manner. This document captures the national PIE needs necessary to support current and future research, and where

  3. Interactive Astronomical Data Analysis Facility

    NASA Technical Reports Server (NTRS)

    Klinglesmith, D. A., III

    1980-01-01

    A description is given of the Interactive Astronomical Data Analysis Facility (IADAF) which performs interactive analysis of astronomical data for resident and visiting scientists. The facilities include a Grant measuring engine, a PDS 1010A microdensitometer, a COMTAL image display system and a PDP 11/40 computer system. Both hardware and software systems are examined, including a description of thirteen overlay programs. Some uses of the IADAF are indicated.

  4. Universal Test Facility

    NASA Astrophysics Data System (ADS)

    Laughery, Mike

    A universal test facility (UTF) for Space Station Freedom is developed. In this context, universal means that the experimental rack design must be: automated, highly marketable, and able to perform diverse microgravity experiments according to NASA space station requirements. In order to fulfill these broad objectives, the facility's customers, and their respective requirements, are first defined. From these definitions, specific design goals and the scope of the first phase of this project are determined. An examination is first made into what types of research are most likely to make the UTF marketable. Based on our findings, the experiments for which the UTF would most likely be used included: protein crystal growth, hydroponics food growth, gas combustion, gallium arsenide crystal growth, microorganism development, and cell encapsulation. Therefore, the UTF is designed to fulfill all of the major requirements for the experiments listed above. The versatility of the design is achieved by taking advantage of the many overlapping requirements presented by these experiments.

  5. Universal Test Facility

    NASA Technical Reports Server (NTRS)

    Laughery, Mike

    1994-01-01

    A universal test facility (UTF) for Space Station Freedom is developed. In this context, universal means that the experimental rack design must be: automated, highly marketable, and able to perform diverse microgravity experiments according to NASA space station requirements. In order to fulfill these broad objectives, the facility's customers, and their respective requirements, are first defined. From these definitions, specific design goals and the scope of the first phase of this project are determined. An examination is first made into what types of research are most likely to make the UTF marketable. Based on our findings, the experiments for which the UTF would most likely be used included: protein crystal growth, hydroponics food growth, gas combustion, gallium arsenide crystal growth, microorganism development, and cell encapsulation. Therefore, the UTF is designed to fulfill all of the major requirements for the experiments listed above. The versatility of the design is achieved by taking advantage of the many overlapping requirements presented by these experiments.

  6. Breadboard Facility

    NASA Technical Reports Server (NTRS)

    1977-01-01

    In the sixties, Chrysler was NASA's prime contractor for the Saturn I and IB test launch vehicles. The company installed and operated at Huntsville what was known as the Saturn I/IB Development Breadboard Facility. "Breadboard," means an array of electrical and electronic equipment for performing a variety of development and test functions. This work gave Chrysler a broad capability in computerized testing to assure quality control in development of solid-state electronic systems. Today that division is manufacturing many products not destined for NASA, most of them being associated with the company's automotive line. A major project is production and quality-control testing of the "lean-burn" engine, one that has a built-in Computer to control emission timing, and allow the engine to run on a leaner mixture of fuel and air. Other environment-related products include vehicle emission analyzers. The newest of the line is an accurate, portable solid state instrument for testing auto exhaust gases. The exhaust analyzers, now being produced for company dealers and for service

  7. Mechanical properties and TEM examination of RAFM steels irradiated up to 70 dpa in BOR-60

    NASA Astrophysics Data System (ADS)

    Gaganidze, E.; Petersen, C.; Materna-Morris, E.; Dethloff, C.; Weiß, O. J.; Aktaa, J.; Povstyanko, A.; Fedoseev, A.; Makarov, O.; Prokhorov, V.

    2011-10-01

    Mechanical properties of Reduced Activation Ferritic/Martensitic (RAFM) steels were studied after irradiation in BOR-60 reactor to a neutron displacement damage of 70 dpa at 330-340 °C. Yield stress and Ductile-to-Brittle-Transition-Temperature of EUROFER97 indicate saturation of hardening and embrittlement. The phenomenological models for description of microstructure evolution and resulting irradiation hardening and embrittlement are discussed. The evolution of yield stress with dose is qualitatively understood within a Whapham and Makin model. Dislocation loops examined in TEM are considered a main source for low-temperature irradiation hardening. The analysis of the fatigue data in terms of the inelastic strain reveals comparable fatigue behaviour both for unirradiated and irradiated conditions, which can be described by a common Manson-Coffin relation. The study of helium effects in B-doped model steels indicated progressive material embrittlement with helium content. Post-irradiation annealing of RAFM steels yielded substantial recovery of mechanical properties.

  8. National facilities study. Volume 2: Task group on aeronautical research and development facilities report

    NASA Technical Reports Server (NTRS)

    1994-01-01

    The Task Group on Aeronautics R&D Facilities examined the status and requirements for aeronautics facilities against the competitive need. Emphasis was placed on ground-based facilities for subsonic, supersonic and hypersonic aerodynamics, and propulsion. Subsonic and transonic wind tunnels were judged to be most critical and of highest priority. Results of the study are presented.

  9. The Right to Own Quality Head Start Facilities. Facilities Focus.

    ERIC Educational Resources Information Center

    Pinckney, Shawna

    1995-01-01

    Notes that previously, Head Start programs were restricted to leasing space, which created renovation and rent difficulties. Examines critical issues confronted by programs since 1992 as they searched for suitable facilities to purchase, and efforts of NHSA to foster collaboration between local programs and community organizations that would…

  10. Guide to research facilities

    SciTech Connect

    Not Available

    1993-06-01

    This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

  11. Alaska SAR Facility mass storage, current system

    NASA Technical Reports Server (NTRS)

    Cuddy, David; Chu, Eugene; Bicknell, Tom

    1993-01-01

    This paper examines the mass storage systems that are currently in place at the Alaska SAR Facility (SAF). The architecture of the facility will be presented including specifications of the mass storage media that are currently used and the performances that we have realized from the various media. The distribution formats and media are also discussed. Because the facility is expected to service future sensors, the new requirements and possible solutions to these requirements are also discussed.

  12. Planning School Library Media Facilities.

    ERIC Educational Resources Information Center

    Anderson, Pauline H.

    This manual examines the planning process for building or renovating new library media facilities. It is concerned with building programs, local building and fire codes, design, working with architects, reading blueprints, engineering and mechanical plans, budgets, bids, and change orders. It offers help with such sensitive issues as the politics…

  13. Post-irradiation identification of papaya ( Carica papaya L.) fruit

    NASA Astrophysics Data System (ADS)

    Chatterjee, Suchandra; Variyar, Prasad S.; Sharma, Arun

    2012-03-01

    Impact of radiation processing on the volatile essential oil profile of papaya ( Carica papaya) was investigated. Gamma-radiation processing resulted in the appearance of a new peak in the GLC profile that was identified as phenol. The observed dose dependent increase in phenol content suggested possible use of this compound as a marker for radiation processed papaya.

  14. Antimicrobials in the Management of Post-Irradiation Infection

    DTIC Science & Technology

    2005-01-01

    infection due to Gram-negative bacteria in the immunocompromised host generally in- volves the use of an aminoglycoside in combination with a beta ...pefloxacin in irradiated C3H/HeN mice: Correction with glucan therapy. Antimicrob Agents Chemother; 37:1882–9, 1993. [Rozenberg-Arska 1985] Rozenberg

  15. Post-irradiation angiosarcoma of the greater omentum.

    PubMed

    Westenberg, A H; Wiggers, T; Henzen-Logmans, S C; Verweij, J; Meerwaldt, J A; van Geel, A N

    1989-04-01

    A case of angiosarcoma of the greater omentum is reported. This angiosarcoma developed 8 years after irradiation for cervical carcinoma and presented with an intra-abdominal hemorrhage. We describe her clinical course, treatment and follow-up. Although several other locations of irradiation-induced sarcomas have been published, this is the first report in literature of a postirradiation angiosarcoma in the greater omentum.

  16. Plum Brook facilities

    NASA Technical Reports Server (NTRS)

    Kozar, Robert

    1993-01-01

    The topics are presented in viewgraph form and include the following: the Spacecraft Propulsion Research Research Facility (B-2); the Hydrogen Heat Transfer Facility (HHTF); the Rocket Dynamics and Control Facility (B-3); the Cryogenic Propellant Tank Site (K-Site); and the Space Power Facility (SPF).

  17. Future Fixed Target Facilities

    SciTech Connect

    Melnitchouk, Wolodymyr

    2009-01-01

    We review plans for future fixed target lepton- and hadron-scattering facilities, including the 12 GeV upgraded CEBAF accelerator at Jefferson Lab, neutrino beam facilities at Fermilab, and the antiproton PANDA facility at FAIR. We also briefly review recent theoretical developments which will aid in the interpretation of the data expected from these facilities.

  18. Sports Facility Management.

    ERIC Educational Resources Information Center

    Walker, Marcia L., Ed.; Stotlar, David K., Ed.

    The numbers of both sports facility management college courses and sport and exercise facilities are increasing, along with the need for an understanding of the trends and management concepts of these facilities. This book focuses exclusively on managing facilities where sporting events occur and includes examples in physical education, athletics,…

  19. Sports Facility Management.

    ERIC Educational Resources Information Center

    Walker, Marcia L., Ed.; Stotlar, David K., Ed.

    The numbers of both sports facility management college courses and sport and exercise facilities are increasing, along with the need for an understanding of the trends and management concepts of these facilities. This book focuses exclusively on managing facilities where sporting events occur and includes examples in physical education, athletics,…

  20. Reliable Facility Location Problem with Facility Protection

    PubMed Central

    Tang, Luohao; Zhu, Cheng; Lin, Zaili; Shi, Jianmai; Zhang, Weiming

    2016-01-01

    This paper studies a reliable facility location problem with facility protection that aims to hedge against random facility disruptions by both strategically protecting some facilities and using backup facilities for the demands. An Integer Programming model is proposed for this problem, in which the failure probabilities of facilities are site-specific. A solution approach combining Lagrangian Relaxation and local search is proposed and is demonstrated to be both effective and efficient based on computational experiments on random numerical examples with 49, 88, 150 and 263 nodes in the network. A real case study for a 100-city network in Hunan province, China, is presented, based on which the properties of the model are discussed and some managerial insights are analyzed. PMID:27583542

  1. Reliable Facility Location Problem with Facility Protection.

    PubMed

    Tang, Luohao; Zhu, Cheng; Lin, Zaili; Shi, Jianmai; Zhang, Weiming

    2016-01-01

    This paper studies a reliable facility location problem with facility protection that aims to hedge against random facility disruptions by both strategically protecting some facilities and using backup facilities for the demands. An Integer Programming model is proposed for this problem, in which the failure probabilities of facilities are site-specific. A solution approach combining Lagrangian Relaxation and local search is proposed and is demonstrated to be both effective and efficient based on computational experiments on random numerical examples with 49, 88, 150 and 263 nodes in the network. A real case study for a 100-city network in Hunan province, China, is presented, based on which the properties of the model are discussed and some managerial insights are analyzed.

  2. Do School Facilities Affect Academic Outcomes?

    ERIC Educational Resources Information Center

    Schneider, Mark

    This review explores which facility attributes affect academic outcomes the most and in what manner and degree. The research is examined in six categories: indoor air quality, ventilation, and thermal comfort; lighting; acoustics; building age and quality; school size; and class size. The review concludes that school facilities affect learning.…

  3. NREL's Concentrated Solar Radiation User Facility

    SciTech Connect

    Lewandowski, A.

    1999-09-01

    Declared a national user facility in 1993, NREL's Concentrated Solar Radiation User Facility (CSR) allows industry, government, and university researchers to examine the effects and applications of as much as 50,000 suns of concentrated solar radiation using a High-Flux Solar Furnace and long-term exposure using an ultraviolet (UV) concentrator.

  4. Facility Condition Assessment from A to Z

    ERIC Educational Resources Information Center

    Kaleba, Frank

    2013-01-01

    This article will provide an overview of the options for performing facility condition assessments. Quite often, the facility manager will choose a condition assessment method without deliberate examination of what type of assessment is best suited to the needs of the organization. In addition, the needs of diverse audiences usually differ--for…

  5. Facility Condition Assessment from A to Z

    ERIC Educational Resources Information Center

    Kaleba, Frank

    2013-01-01

    This article will provide an overview of the options for performing facility condition assessments. Quite often, the facility manager will choose a condition assessment method without deliberate examination of what type of assessment is best suited to the needs of the organization. In addition, the needs of diverse audiences usually differ--for…

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

    SciTech Connect

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

    2016-05-01

    Abstract The Mechanistic Fuel Failure (MFF) series of metal fuel irradiations conducted in the Fast Flux Test Facility (FFTF) provides an important potential comparison between data generated in the Experimental Breeder Reactor (EBR-II) and that expected in a larger-scale fast reactor. The irradiations were the beginning tests to qualify U-10wt%Zr as a driver fuel for FFTF. The FFTF core, with a 91.4 cm tall fuel column and a chopped cosine neutron flux profile, 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 previous EBR-II experiments that had a 32-cm height core. The MFF-3 and MFF-5 qualification assemblies operated in FFTF to >10 at% burnup, and performed very well with no cladding breaches. The MFF-3 assembly operated to 13.8 at% burnup with a peak inner cladding temperature of 643°C, and the MFF-5 assembly operated to 10.1 at% burnup with a peak inner cladding temperature of 651°C. Because of the very high operating temperatures for both the fuel and the cladding, data from the MFF assemblies are most comparable to the data obtained from the EBR-II X447 experiment, which experienced two pin breaches. The X447 breaches were strongly influenced by a large amount of fuel/cladding chemical interaction (FCCI). The MFF pins benefitted from different axial locations of high burnup and peak cladding temperature, which helped to reduce interdiffusion between rare earth fission products and stainless steel cladding. Post-irradiation examination evidence illustrates this advantage. Comparing other performance data of the long MFF pins to prior EBR-II test data, the MFF fuel inside the cladding grew less axially, and the gas release data did not reveal a definitive difference.

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

    DOE PAGES

    Carmack, W. Jon; Chichester, Heather M.; Porter, Douglas L.; ...

    2016-02-27

    The Mechanistic Fuel Failure (MFF) series of metal fuel irradiations conducted in the Fast Flux Test Facility (FFTF) provides an important potential comparison between data generated in the Experimental Breeder Reactor (EBR-II) and that expected in a larger-scale fast reactor. The irradiations were the beginning tests to qualify U-10wt%Zr as a driver fuel for FFTF. The FFTF core, with a 91.4 cm tall fuel column and a chopped cosine neutron flux profile, operated with a peak cladding temperature at the top of the fuel column, but developed peak burnup at the centerline of the core. This then places the peakmore » fuel temperature midway between the core center and the top of fuel, lower in the fuel column than in previous EBR-II experiments that had a 32-cm height core. The MFF-3 and MFF-5 qualification assemblies operated in FFTF to >10 at% burnup, and performed very well with no cladding breaches. The MFF-3 assembly operated to 13.8 at% burnup with a peak inner cladding temperature of 643°C, and the MFF-5 assembly operated to 10.1 at% burnup with a peak inner cladding temperature of 651°C. Because of the very high operating temperatures for both the fuel and the cladding, data from the MFF assemblies are most comparable to the data obtained from the EBR-II X447 experiment, which experienced two pin breaches. The X447 breaches were strongly influenced by a large amount of fuel/cladding chemical interaction (FCCI). The MFF pins benefitted from different axial locations of high burnup and peak cladding temperature, which helped to reduce interdiffusion between rare earth fission products and stainless steel cladding. Post-irradiation examination evidence illustrates this advantage. After comparing other performance data of the long MFF pins to prior EBR-II test data, the MFF fuel inside the cladding grew less axially, and the gas release data did not reveal a definitive difference.« less

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

    SciTech Connect

    Carmack, W. Jon; Chichester, Heather M.; Porter, Douglas L.; Wootan, David W.

    2016-02-27

    The Mechanistic Fuel Failure (MFF) series of metal fuel irradiations conducted in the Fast Flux Test Facility (FFTF) provides an important potential comparison between data generated in the Experimental Breeder Reactor (EBR-II) and that expected in a larger-scale fast reactor. The irradiations were the beginning tests to qualify U-10wt%Zr as a driver fuel for FFTF. The FFTF core, with a 91.4 cm tall fuel column and a chopped cosine neutron flux profile, operated with a peak cladding temperature at the top of the fuel column, but developed peak burnup at the centerline of the core. This then places the peak fuel temperature midway between the core center and the top of fuel, lower in the fuel column than in previous EBR-II experiments that had a 32-cm height core. The MFF-3 and MFF-5 qualification assemblies operated in FFTF to >10 at% burnup, and performed very well with no cladding breaches. The MFF-3 assembly operated to 13.8 at% burnup with a peak inner cladding temperature of 643°C, and the MFF-5 assembly operated to 10.1 at% burnup with a peak inner cladding temperature of 651°C. Because of the very high operating temperatures for both the fuel and the cladding, data from the MFF assemblies are most comparable to the data obtained from the EBR-II X447 experiment, which experienced two pin breaches. The X447 breaches were strongly influenced by a large amount of fuel/cladding chemical interaction (FCCI). The MFF pins benefitted from different axial locations of high burnup and peak cladding temperature, which helped to reduce interdiffusion between rare earth fission products and stainless steel cladding. Post-irradiation examination evidence illustrates this advantage. After comparing other performance data of the long MFF pins to prior EBR-II test data, the MFF fuel inside the cladding grew less axially, and the gas release data did not reveal a definitive difference.

  9. Design considerations of the national transonic facility

    NASA Technical Reports Server (NTRS)

    Baals, D. D.

    1976-01-01

    The inability of existing wind tunnels to provide aerodynamic test data at transonic speeds and flight Reynolds numbers was examined. The proposed transonic facility is a high Reynolds number transonic wind tunnel designed to meet the research and development needs of industry, and the scientific community. The facility employs the cryogenic approach to achieve high transonic Reynolds numbers at acceptable model loads and tunnel power. By using temperature as a test variable, a unique capability to separate scale effects from model aeroelastic effects is provided. The performance envelope of the facility is shown to provide a ten fold increase in transonic Reynolds number capability compared to currently available facilities.

  10. Materials and Fuels Complex Tour

    SciTech Connect

    Miley, Don

    2011-01-01

    The Materials and Fuels Complex at Idaho National Laboratory is home to several facilities used for the research and development of nuclear fuels. Stops include the Fuel Conditioning Facility, the Hot Fuel Examination Facility (post-irradiation examination), and the Space and Security Power System Facility, where radioisotope thermoelectric generators (RTGs) are assembled for deep space missions. You can learn more about INL research programs at http://www.facebook.com/idahonationallaboratory.

  11. Materials and Fuels Complex Tour

    ScienceCinema

    Miley, Don

    2016-07-12

    The Materials and Fuels Complex at Idaho National Laboratory is home to several facilities used for the research and development of nuclear fuels. Stops include the Fuel Conditioning Facility, the Hot Fuel Examination Facility (post-irradiation examination), and the Space and Security Power System Facility, where radioisotope thermoelectric generators (RTGs) are assembled for deep space missions. You can learn more about INL research programs at http://www.facebook.com/idahonationallaboratory.

  12. Research and test facilities

    NASA Technical Reports Server (NTRS)

    1993-01-01

    A description is given of each of the following Langley research and test facilities: 0.3-Meter Transonic Cryogenic Tunnel, 7-by 10-Foot High Speed Tunnel, 8-Foot Transonic Pressure Tunnel, 13-Inch Magnetic Suspension & Balance System, 14-by 22-Foot Subsonic Tunnel, 16-Foot Transonic Tunnel, 16-by 24-Inch Water Tunnel, 20-Foot Vertical Spin Tunnel, 30-by 60-Foot Wind Tunnel, Advanced Civil Transport Simulator (ACTS), Advanced Technology Research Laboratory, Aerospace Controls Research Laboratory (ACRL), Aerothermal Loads Complex, Aircraft Landing Dynamics Facility (ALDF), Avionics Integration Research Laboratory, Basic Aerodynamics Research Tunnel (BART), Compact Range Test Facility, Differential Maneuvering Simulator (DMS), Enhanced/Synthetic Vision & Spatial Displays Laboratory, Experimental Test Range (ETR) Flight Research Facility, General Aviation Simulator (GAS), High Intensity Radiated Fields Facility, Human Engineering Methods Laboratory, Hypersonic Facilities Complex, Impact Dynamics Research Facility, Jet Noise Laboratory & Anechoic Jet Facility, Light Alloy Laboratory, Low Frequency Antenna Test Facility, Low Turbulence Pressure Tunnel, Mechanics of Metals Laboratory, National Transonic Facility (NTF), NDE Research Laboratory, Polymers & Composites Laboratory, Pyrotechnic Test Facility, Quiet Flow Facility, Robotics Facilities, Scientific Visualization System, Scramjet Test Complex, Space Materials Research Laboratory, Space Simulation & Environmental Test Complex, Structural Dynamics Research Laboratory, Structural Dynamics Test Beds, Structures & Materials Research Laboratory, Supersonic Low Disturbance Pilot Tunnel, Thermal Acoustic Fatigue Apparatus (TAFA), Transonic Dynamics Tunnel (TDT), Transport Systems Research Vehicle, Unitary Plan Wind Tunnel, and the Visual Motion Simulator (VMS).

  13. Facilities for US Radioastronomy.

    ERIC Educational Resources Information Center

    Thaddeus, Patrick

    1982-01-01

    Discusses major developments in radioastronomy since 1945. Topics include proposed facilities, very-long-baseline interferometric array, millimeter-wave telescope, submillimeter-wave telescope, and funding for radioastronomy facilities and projects. (JN)

  14. 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.

  15. FDA Certified Mammography Facilities

    MedlinePlus

    ... Program Consumer Information (MQSA) Search for a Certified Facility Share Tweet Linkedin Pin it More sharing options ... Email Print This list of FDA Certified Mammography Facilities is updated weekly. If you click on Search ...

  16. Spacelab Data Processing Facility

    NASA Technical Reports Server (NTRS)

    1983-01-01

    The capabilities of the Spacelab Data Processing Facility (SPDPF) are highlighted. The capturing, quality monitoring, processing, accounting, and forwarding of vital Spacelab data to various user facilities around the world are described.

  17. 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

  18. Science Facilities. An Interpretive Bibliography.

    ERIC Educational Resources Information Center

    Wisconsin Univ., Madison. ERIC Clearinghouse on Educational Facilities.

    References pertaining to science facilities are organized and presented in the following categories--(1) biology facilities, (2) chemistry facilities, (3) physics facilities, (4) astronomy facilities, (5) elementary and secondary school science facilities, (6) college and university science facilities, and (7) planning and science laboratory. (FS)

  19. Japanese and Eastern Facilities

    NASA Astrophysics Data System (ADS)

    Nakahata, M.

    2005-09-01

    The underground facilities in Japan and Korea are reviewed. Those facilities are Kamioka Observatory, Oto Cosmo Observatory, Ogoya Underground Laboratory, and Kashiwa Underground Laboratory in Japan and YangYang Underground Laboratory in Korea. Features of those facilities and radon reduction systems at Kamioka Observatory are presented.

  20. Facilities Engineering in NASA

    NASA Technical Reports Server (NTRS)

    Pagluiso, M. A.

    1970-01-01

    An overview of NASA facilities is given outlining some of the more interesting and unique aspects of engineering and facilities associated with the space program. Outlined are some of the policies under which the Office of Facilities conducts its business. Included are environmental quality control measures.

  1. Considerations on Facilities Planning

    ERIC Educational Resources Information Center

    Baule, Steven

    2007-01-01

    Most facilities renovation projects occur because someone at the executive or board level has lobbied successfully for them. Often in public schools, the voters have agreed to the project as well via a building referendum. Therefore, facilities projects are highly visible to the community. Unlike many other issues in schools, facilities projects…

  2. Facilities Engineering in NASA

    NASA Technical Reports Server (NTRS)

    Pagluiso, M. A.

    1970-01-01

    An overview of NASA facilities is given outlining some of the more interesting and unique aspects of engineering and facilities associated with the space program. Outlined are some of the policies under which the Office of Facilities conducts its business. Included are environmental quality control measures.

  3. Considerations on Facilities Planning

    ERIC Educational Resources Information Center

    Baule, Steven

    2007-01-01

    Most facilities renovation projects occur because someone at the executive or board level has lobbied successfully for them. Often in public schools, the voters have agreed to the project as well via a building referendum. Therefore, facilities projects are highly visible to the community. Unlike many other issues in schools, facilities projects…

  4. Aeronautical facilities assessment

    NASA Technical Reports Server (NTRS)

    Penaranda, F. E. (Compiler)

    1985-01-01

    A survey of the free world's aeronautical facilities was undertaken and an evaluation made on where the relative strengths and weaknesses exist. Special emphasis is given to NASA's own capabilities and needs. The types of facilities surveyed are: Wind Tunnels; Airbreathing Propulsion Facilities; and Flight Simulators

  5. Rental of School Facilities.

    ERIC Educational Resources Information Center

    San Antonio Independent School District, TX.

    Regulations governing rental of facilities owned by the San Antonio School District (Texas) are documented as found in Section Eight of the school district's rules code ("Public Use of All School District Facilities"). Eight divisions of the code are as follows: (1) administration; (2) use of school facilities by pupils, employees, and…

  6. Designs for Learning: 55 Exemplary Educational Facilities. Education and Skills.

    ERIC Educational Resources Information Center

    Organisation for Economic Cooperation and Development, Paris (France). Programme on Educational Building.

    This document examines 55 educational facilities throughout the world whose quality designs were deemed instrumental in providing an environment for a quality educational process to emerge. Each entry provides facility statistics such as number of students, the facility's age and type, and name of the architectural firm responsible for its design.…

  7. Associations between Moderate-to-Vigorous Physical Activity and Neighbourhood Recreational Facilities: The Features of the Facilities Matter

    PubMed Central

    Lee, Ka Yiu; Lee, Paul H.; Macfarlane, Duncan

    2014-01-01

    Objectives: To examine the associations between objectively-assessed moderate-to-vigorous physical activity (MVPA) and perceived/objective measures of neighbourhood recreational facilities categorized into indoor or outdoor, public, residential or commercial facilities. The associations between facility perceptions and objectively-assessed numbers of recreational facilities were also examined. Method: A questionnaire was used on 480 adults to measure local facility perceptions, with 154 participants wearing ActiGraph accelerometers for ≥4 days. The objectively-assessed number of neighbourhood recreational facilities were examined using direct observations and Geographical Information System data. Results: Both positive and negative associations were found between MVPA and perceived/objective measures of recreational facilities. Some associations depended on whether the recreational facilities were indoor or outdoor, public or residential facilities. The objectively-assessed number of most public recreational facilities was associated with the corresponding facility perceptions, but the size of effect was generally lower than for residential recreational facilities. Conclusions: The objectively-assessed number of residential outdoor table tennis courts and public indoor swimming pools, the objectively-assessed presence of tennis courts and swimming pools, and the perceived presence of bike lanes and swimming pools were positive determinants of MVPA. It is suggested to categorize the recreational facilities into smaller divisions in order to identify unique associations with MVPA. PMID:25485980

  8. Post-Service Examination of PWR Baffle Bolts, Part I. Examination and Test Plan

    SciTech Connect

    Leonard, Keith J.; Sokolov, Mikhail A.; Gussev, Maxim N.

    2015-04-30

    In support of extended service and current operations of the US nuclear reactor plants, the Oak Ridge National Laboratory (ORNL), through the Department of Energy (DOE), Light Water Reactor Sustainability (LWRS) Program, is coordinating with Ginna Nuclear Power Plant, The Westinghouse Electric Company, LLC, and ATI Consulting, the selective procurement of baffle bolts that were withdrawn from service in 2011 and currently stored on site at Ginna. The goal of this program is to perform detailed microstructural and mechanical property characterization of baffle former bolts following in-service exposures. This report outlines the selection criteria of the bolts and the techniques to be used in this study. The bolts available are the original alloy 347 steel fasteners used in holding the baffle plates to the baffle former structures within the lower portion of the pressurized water reactor vessel. Of the eleven possible bolts made available for this work, none were identified to have specific damage. The bolts, however, did show varying levels of breakaway torque required in their removal. The bolts available for this study varied in peak fluence (highest dose within the head of the bolt) between 9.9 and 27.8x1021 n/cm2 (E>1MeV). As no evidence for crack initiation was determined for the available bolts from preliminary visual examination, two bolts with the higher fluence values were selected for further post-irradiation examination. The two bolts showed different breakaway torque levels necessary in their removal. The information from these bolts will be integral to the LWRS program initiatives in evaluating end of life microstructure and properties. Furthermore, valuable data will be obtained that can be incorporated into model predictions of long-term irradiation behavior and compared to results obtained in high flux experimental reactor conditions. The two bolts selected for the ORNL study will be shipped to Westinghouse with bolts of

  9. Facility requirements for hypersonic propulsion system testing

    NASA Astrophysics Data System (ADS)

    Dunn, M. G.; Lordi, J. A.; Wittliff, C. E.; Holden, M. S.

    Facility requirements and capabilities for hypersonic propulsion system testing are reviewed with emphasis on short-duration test facilities. Past and current hypersonic facility studies are reviewed, and some of the many problems currently associated with wing-body hypersonic aircraft and several currently operational ground-based facilities or facilities in the development stage are described. Limitations on the short-duration shock tunnel are examined, including problem areas where this device can make significant contributions to the type of unified computational, ground-test, and flight-experiment program that will be necessary to resolve complex issues associated with the development of either a SSTO vehicle or an air-breathing/rocket-assist-to-orbit vehicle.

  10. Evaluation of existing United States` facilities for use as a mixed-oxide (MOX) fuel fabrication facility for plutonium disposition

    SciTech Connect

    Beard, C.A.; Buksa, J.J.; Chidester, K.; Eaton, S.L.; Motley, F.E.; Siebe, D.A.

    1995-12-31

    A number of existing US facilities were evaluated for use as a mixed-oxide fuel fabrication facility for plutonium disposition. These facilities include the Fuels Material Examination Facility (FMEF) at Hanford, the Washington Power Supply Unit 1 (WNP-1) facility at Hanford, the Barnwell Nuclear Fuel Plant (BNFP) at Barnwell, SC, the Fuel Processing Facility (FPF) at Idaho National Engineering Laboratory (INEL), the Device Assembly Facility (DAF) at the Nevada Test Site (NTS), and the P-reactor at the Savannah River Site (SRS). The study consisted of evaluating each facility in terms of available process space, available building support systems (i.e., HVAC, security systems, existing process equipment, etc.), available regional infrastructure (i.e., emergency response teams, protective force teams, available transportation routes, etc.), and ability to integrate the MOX fabrication process into the facility in an operationally-sound manner that requires a minimum amount of structural modifications.

  11. 340 Facility compliance assessment

    SciTech Connect

    English, S.L.

    1993-10-01

    This study provides an environmental compliance evaluation of the RLWS and the RPS systems of the 340 Facility. The emphasis of the evaluation centers on compliance with WAC requirements for hazardous and mixed waste facilities, federal regulations, and Westinghouse Hanford Company (WHC) requirements pertinent to the operation of the 340 Facility. The 340 Facility is not covered under either an interim status Part A permit or a RCRA Part B permit. The detailed discussion of compliance deficiencies are summarized in Section 2.0. This includes items of significance that require action to ensure facility compliance with WAC, federal regulations, and WHC requirements. Outstanding issues exist for radioactive airborne effluent sampling and monitoring, radioactive liquid effluent sampling and monitoring, non-radioactive liquid effluent sampling and monitoring, less than 90 day waste storage tanks, and requirements for a permitted facility.

  12. Mir training Facility view

    NASA Image and Video Library

    1995-02-22

    S95-04319 (22 Feb 1995) --- The neutral buoyancy facility at the Gagarin Cosmonaut Training Center in Star City, Russia, is used for underwater training for missions aboard the Russian Mir Space Station. The facility is similar to NASA's Weightless Environment Training Facility (WET-F) at the Johnson Space Center (JSC) in Houston, Texas, and the Neutral Buoyancy Simulator (NBS) at the Marshall Space Flight Center (MSFC) in Huntsville, Alabama.

  13. Facility Measures Magnetic Fields

    NASA Technical Reports Server (NTRS)

    Honess, Shawn B.; Narvaez, Pablo; Mcauley, James M.

    1991-01-01

    Partly automated facility measures and computes steady near magnetic field produced by object. Designed to determine magnetic fields of equipment to be installed on spacecraft including sensitive magnetometers, with view toward application of compensating fields to reduce interfernece with spacecraft-magnetometer readings. Because of its convenient operating features and sensitivity of its measurements, facility serves as prototype for similar facilities devoted to magnetic characterization of medical equipment, magnets for high-energy particle accelerators, and magnetic materials.

  14. Developing a facility strategy.

    PubMed

    Capps, D M

    1994-05-01

    Successful planning for capital investment relies upon the ability of the management team to establish a cogent and comprehensive direction for facility development. The selection of an appropriate strategy integrates multiple issues: mission, service needs of the community, the external environment, the organization's ethos, current physical resources, operational systems, and vision. This paper will identify and discuss key components and data integral to formulating a facility strategy that outlines the basic direction for developing a facility master plan. The process itself will be presented as a working methodology that can be applied to the organization's resources and vision to generate a coherent facility strategy.

  15. Perimeter security for Minnesota correctional facilities

    SciTech Connect

    Crist, D.; Spencer, D.D.

    1996-12-31

    For the past few years, the Minnesota Department of Corrections, assisted by Sandia National Laboratories, has developed a set of standards for perimeter security at medium, close, and maximum custody correctional facilities in the state. During this process, the threat to perimeter security was examined and concepts about correctional perimeter security were developed. This presentation and paper will review the outcomes of this effort, some of the lessons learned, and the concepts developed during this process and in the course of working with architects, engineers and construction firms as the state upgraded perimeter security at some facilities and planned new construction at other facilities.

  16. Meteorological Sensor Calibration Facility

    NASA Technical Reports Server (NTRS)

    Schmidlin, F. J.

    1988-01-01

    The meteorological sensor calibration facility is designed to test and assess radiosonde measurement quality through actual flights in the atmosphere. United States radiosonde temperature measurements are deficient in that they require correction for errors introduced by long- and short-wave radiation. The effect of not applying corrections results in a large bias between day time and night time measurements. This day/night bias has serious implications for users of radiosonde data, of which NASA is one. The derivation of corrections for the U.S. radiosonde is quite important. Determination of corrections depends on solving the heat transfer equation of the thermistor using laboratory measurements of the emissivity and absorptivity of the thermistor coating. The U.S. radiosonde observations from the World Meteorological Organization International Radiosonde Intercomparison were used as the data base to test whether the day/night height bias can be removed. Twenty-five noon time and 26 night time observations were used. Corrected temperatures were used to calculate new geopotentials. Day/night bias in the geopotentials decreased significantly when corrections were introduced. Some testing of thermal lag attendant with the standard carbon hygristor took place. Two radiosondes with small bead thermistors imbedded in the hygristor were flown. Detailed analysis was not accomplished; however, cursory examination of the data showed that the hygristor is at a higher temperature than the external thermistor indicates.

  17. Environmental protection facilities safety study: Portsmouth Gaseous Diffusion Plant

    SciTech Connect

    Not Available

    1982-05-01

    The purpose of this Safety Study is to examine the existing facilities at the Portsmouth Gaseous Diffusion Plant that are dedicated to environmental protection. Seven separate, numbered facilities and five unnumbered continuous air sampling stations are identified as the fixed facilities to protect the environment. Each is examined from the standpoint of hazardous materials, monitoring and protection systems, confinement systems, ventilation systems, criticality control systems, fire protection systems, waste disposal systems, and safety systems.

  18. SSPA Equipment Engineering Feasibility Report

    SciTech Connect

    N.E. Woolstenhulme; C.R. Clark

    2011-09-01

    In response to a demanding reactor conversion schedule, construction of the Shielded Sample Preparation Area (SSPA) was initiated in 2010 to augment the existing capabilities of the Hot Fuel Examination Facility (HFEF). While HFEF is and will remain the workhorse for post irradiation sample preparation, there is currently a large backlog of Post-Irradiation Examination (PIE) experiments caused by numerous competing projects (this backlog is expected to continue for the foreseeable future). HFEF, in its present configuration also lacks the ability to prepare samples suitable for several of the tests that have been identified for the successful conclusion of the RERTR program; these samples require fine detail machining of irradiated fuel plates.

  19. State Capital Spending on PK-12 School Facilities

    ERIC Educational Resources Information Center

    Filardo, Mary; Bar, Michelle; Cheng, Stephanie; Ulsoy, Jessie; Allen, Marni

    2010-01-01

    In this study, the 21st Century School Fund (21CSF), with support from the National Clearinghouse for Educational Facilities, examined the state capital outlay funding for elementary and secondary public education facility construction and modernization. The authors examined how much capital outlay has been expended by states from 2005-2008 as…

  20. Future User Facilities

    NASA Astrophysics Data System (ADS)

    Riedinger, Lee

    2002-10-01

    The southeastern part of the U.S. is blessed with an array of national user facilities that are accessible to scientists in the region. The Oak Ridge National Laboratory (ORNL) operates 17 officially designated user facilities for the Department of Energy, the Jefferson Lab operates the Continuous Electron Beam Accelerator Facility (CEBAF), and a number of universities have forefront experimental facilities that are widely accessible. The long lead time necessary to originate and construct new user facilities makes it imperative to consider the needs of the physical sciences 10 to 20 years in the future. The construction of the Spallation Neutron Source at ORNL positions the southeast to lead in neutron science. Upgrades are desired for CEBAF and the Holifield Radioactive Ion Beam Facility (ORNL). The more future possibilities are less clear, but are becoming a focus of strategic planning among the national laboratories. Possibilities may arise in the U.S. for next-generation light sources, large computational centers, advanced fusion devices, nanotechnology centers, and perhaps facilities that are not yet contemplated. A regional discussion of the needs for large-scale user facilities in the southeast is important.

  1. Wake Shield Facility (WSF)

    NASA Technical Reports Server (NTRS)

    2004-01-01

    The Wake Shield Facility (WSF) is a free-flying research and development facility that is designed to use the pure vacuum of space to conduct scientific research in the development of new materials. The thin film materials technology developed by the WSF could some day lead to applications such as faster electronics components for computers.

  2. Relocatale Learning Facilities.

    ERIC Educational Resources Information Center

    Ontario Dept. of Education, Toronto. School Planning and Building Research Section.

    This document supplies guidelines for the future design of structures within one category of relocatable learning facilities--divisible facilities. The current use and average cost of portables; and teacher, student, and community reactions are discussed. Four types of relocatable structures are described: portable, mobile, divisible, and…

  3. Florida Educational Facilities, 1999.

    ERIC Educational Resources Information Center

    Florida State Dept. of Education, Tallahassee. Office of Educational Facilities.

    This publication describes Florida school and community college facilities completed in 1999, including photographs and floor plans. The facilities profiled are: Buchholz High School (Alachua County); Gator Run Elementary School (Broward); Corkscrew Elementary School (Collier); The 500 Role Models Academy of Excellence (Miami-Dade); Caribbean…

  4. BIBLIOGRAPHY OF FACILITIES INFORMATION.

    ERIC Educational Resources Information Center

    American Association of Junior Colleges, Washington, DC.

    PERSONNEL OF THE FACILITIES INFORMATION SERVICE OF THE AMERICAN ASSOCIATION OF JUNIOR COLLEGES COMPILED THIS LISTING OF BOOKS, ARTICLES, MONOGRAPHS, AND OTHER PRINTED MATERIALS RELEVANT TO JUNIOR COLLEGE FACILITIES PLANNING, DESIGN, AND CONSTRUCTION. IN ADDITION TO A "GENERAL" CATEGORY, REFERENCES ARE GROUPED UNDER HEADINGS OF AUDITORIUMS, COLLEGE…

  5. INCINERATION RESEARCH FACILITY

    EPA Science Inventory

    The Cincinnati-based Risk Reduction Engineering Laboratory, ORD, U.S. EPA operates the Incineration Research Facility *IRF) in Jefferson, Arkansas. This facility's pilot-scale experimental incineration systems include a Rotary Kiln System and a Liquid Injection System. Each syste...

  6. Florida Educational Facilities, 2000.

    ERIC Educational Resources Information Center

    Florida State Dept. of Education, Tallahassee. Office of Educational Facilities.

    This publication describes Florida school and community college facilities completed in 2000, including photographs and floor plans. The facilities profiled are:J. R. Arnold High School (Bay County); Falcon Cove Middle School (Broward); Floranada Elementary School (Broward); Lyons Creek Middle School (Broward); Parkside Elementary School…

  7. Facility Focus: Food Service.

    ERIC Educational Resources Information Center

    College Planning & Management, 2001

    2001-01-01

    Details the design goals, materials, and finish choices of a 38,400 square-foot dining facility and the delineation and organization of multiple spaces that comprise a 21,000 square-foot food service facility. This later design utilized market studies of student tastes and buying patterns to ensure student satisfaction. Includes seven photographs.…

  8. Science Facilities Bibliography.

    ERIC Educational Resources Information Center

    National Science Foundation, Washington, DC.

    A bibliographic collection on science buildings and facilities is cited with many different reference sources for those concerned with the design, planning, and layout of science facilities. References are given covering a broad scope of information on--(1) physical plant planning, (2) management and safety, (3) building type studies, (4) design…

  9. INCINERATION RESEARCH FACILITY

    EPA Science Inventory

    The Cincinnati-based Risk Reduction Engineering Laboratory, ORD, U.S. EPA operates the Incineration Research Facility *IRF) in Jefferson, Arkansas. This facility's pilot-scale experimental incineration systems include a Rotary Kiln System and a Liquid Injection System. Each syste...

  10. Long Range Facilities Planning

    DTIC Science & Technology

    1982-04-01

    Richard Muther range facilities Many alterna- analysis indi- cated that if NASSCO ever expected to surpass its output of the last several years, current...Marine Engineers (SNAME) SP-1 Panel Meeting. The Maritime Administration had Richard Muther (an authority on long range facility planning) address a

  11. Irradiation performance of FFTF drivers using the D9 alloy

    SciTech Connect

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

    1994-12-31

    Five test assemblies similar in design to the Fast Flux Test Facility driver fuel assembly , but employing the alloy D9 in place of stainless steel 316 for duct, cladding, and wire wrap compnents were irradiated to demonstrate the improved performance of the new design. Results of post-irradiation examinations are discussed.

  12. METC Combustion Research Facility

    SciTech Connect

    Halow, J.S.; Maloney, D.J.; Richards, G.A.

    1994-12-31

    The objective of the Morgantown Energy Technology Center (METC) high pressure combustion facility is to provide a mid-scale facility for combustion and cleanup research to support DOE`s advanced gas turbine, pressurized, fluidized-bed combustion, and hot gas cleanup programs. The facility is intended to fill a gap between lab scale facilities typical of universities and large scale combustion/turbine test facilities typical of turbine manufacturers. The facility is now available to industry and university partners through cooperative programs with METC. Currently two combustion rigs are operating and one additional project is under construction for the facility. Space is available in the test cells for at least one additional test rig. A pressurized pulsed combustor began operating in July of 1993. The combustor will carry out pulsed combustion of natural gas at pressures up to 10 atmospheres. A high pressure steady flow rig is currently completely fabricated. The objective of this rig is to test novel, steady-flow, pressurized combustors that produce very low NO{sub x} and other emissions. An evaporation rig currently is in startup. This rig will test the concept of water injection in an externally fired cycle. The specific technical issue that the unit will address is evaporation rates of water droplets in high pressure flows.

  13. 17. Topside facility, interior of facility manager's room, view towards ...

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

    17. Topside facility, interior of facility manager's room, view towards south. Lyon - Whiteman Air Force Base, Oscar O-1 Minuteman Missile Alert Facility, Southeast corner of Twelfth & Vendenberg Avenues, Knob Noster, Johnson County, MO

  14. 18. Topside facility, interior of facility manager's room, view towards ...

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

    18. Topside facility, interior of facility manager's room, view towards west. Lyon - Whiteman Air Force Base, Oscar O-1 Minuteman Missile Alert Facility, Southeast corner of Twelfth & Vendenberg Avenues, Knob Noster, Johnson County, MO

  15. Association of U.S. Dialysis Facility Neighborhood Characteristics with Facility-Level Kidney Transplantation

    PubMed Central

    Plantinga, Laura; Pastan, Stephen; Kramer, Michael; McClellan, Ann; Krisher, Jenna; Patzer, Rachel E.

    2014-01-01

    Background Improving access to optimal healthcare may depend on attributes of neighborhoods where patients receive healthcare services. We investigated whether characteristics of dialysis facility neighborhoods—where most patients with end-stage renal disease are treated—were associated with facility-level kidney transplantation. Methods We examined the association between census tract (neighborhood)-level sociodemographic factors and facility-level kidney transplantation rate in 3,983 U.S. dialysis facilities with reported kidney transplantation rates. Number of kidney transplants and total person-years contributed at the facility level in 2007-2010 were obtained from the Dialysis Facility Report and linked to census tract data on sociodemographic characteristics from the American Community Survey 2006-2010 by dialysis facility location. We used multivariable Poisson models with generalized estimating equations to estimate associations between neighborhood characteristics and transplant incidence. Results U.S. dialysis facilities were located in neighborhoods with substantially greater proportions of black and poor residents, relative to the national average. Most facility neighborhood characteristics were associated with transplant, with incidence rate ratios (95% CI) for standardized increments (in percentage) of neighborhood exposures of: living in poverty, 0.88 (0.84-0.92), black race, 0.83 (0.78-0.89); high school graduates, 1.22 (1.17-1.26); and unemployed, 0.90 (0.85-0.95). Conclusion Dialysis facility neighborhood characteristics may be modestly associated with facility rates of kidney transplantation. The success of dialysis facility interventions to improve access to kidney transplantation may partially depend on reducing neighborhood-level barriers. PMID:25196018

  16. Association of U.S. Dialysis facility neighborhood characteristics with facility-level kidney transplantation.

    PubMed

    Plantinga, Laura; Pastan, Stephen; Kramer, Michael; McClellan, Ann; Krisher, Jenna; Patzer, Rachel E

    2014-01-01

    Improving access to optimal healthcare may depend on the attributes of neighborhoods where patients receive healthcare services. We investigated whether the characteristics of dialysis facility neighborhoods--where most patients with end-stage renal disease are treated--were associated with facility-level kidney transplantation. We examined the association between census tract (neighborhood)-level sociodemographic factors and facility-level kidney transplantation rate in 3,983 U.S. dialysis facilities where kidney transplantation rates were high. Number of kidney transplants and total person-years contributed at the facility level in 2007-2010 were obtained from the Dialysis Facility Report and linked to the census tract data on sociodemographic characteristics from the American Community Survey 2006-2010 by dialysis facility location. We used multivariable Poisson models with generalized estimating equations to estimate the link between the neighborhood characteristics and transplant incidence. Dialysis facilities in the United States were located in neighborhoods with substantially greater proportions of black and poor residents, relative to the national average. Most facility neighborhood characteristics were associated with transplant, with incidence rate ratios (95% CI) for standardized increments (in percentage) of neighborhood exposures of: living in poverty, 0.88 (0.84-0.92), black race, 0.83 (0.78-0.89); high school graduates, 1.22 (1.17-1.26); and unemployed, 0.90 (0.85-0.95). Dialysis facility neighborhood characteristics may be modestly associated with facility rates of kidney transplantation. The success of dialysis facility interventions to improve access to kidney transplantation may partially depend on reducing neighborhood-level barriers. © 2014 S. Karger AG, Basel.

  17. Biotechnology Facility: An ISS Microgravity Research Facility

    NASA Technical Reports Server (NTRS)

    Gonda, Steve R.; Tsao, Yow-Min

    2000-01-01

    The International Space Station (ISS) will support several facilities dedicated to scientific research. One such facility, the Biotechnology Facility (BTF), is sponsored by the Microgravity Sciences and Applications Division (MSAD) and developed at NASA's Johnson Space Center. The BTF is scheduled for delivery to the ISS via Space Shuttle in April 2005. The purpose of the BTF is to provide: (1) the support structure and integration capabilities for the individual modules in which biotechnology experiments will be performed, (2) the capability for human-tended, repetitive, long-duration biotechnology experiments, and (3) opportunities to perform repetitive experiments in a short period by allowing continuous access to microgravity. The MSAD has identified cell culture and tissue engineering, protein crystal growth, and fundamentals of biotechnology as areas that contain promising opportunities for significant advancements through low-gravity experiments. The focus of this coordinated ground- and space-based research program is the use of the low-gravity environment of space to conduct fundamental investigations leading to major advances in the understanding of basic and applied biotechnology. Results from planned investigations can be used in applications ranging from rational drug design and testing, cancer diagnosis and treatments and tissue engineering leading to replacement tissues.

  18. The Association between Suicide Screening Practices and Attempts Requiring Emergency Care in Juvenile Justice Facilities.

    ERIC Educational Resources Information Center

    Gallagher, Catherine A.; Dobrin, Adam

    2005-01-01

    Objective: To provide a national description of suicide screening practices in juvenile residential facilities and to examine their association with whether facilities experience a suicide attempt. Method: Multivariate modeling with data from the 2000 Juvenile Residential Facility Census (n = 3690 facilities). Results: Controlling for facility…

  19. The Association between Suicide Screening Practices and Attempts Requiring Emergency Care in Juvenile Justice Facilities.

    ERIC Educational Resources Information Center

    Gallagher, Catherine A.; Dobrin, Adam

    2005-01-01

    Objective: To provide a national description of suicide screening practices in juvenile residential facilities and to examine their association with whether facilities experience a suicide attempt. Method: Multivariate modeling with data from the 2000 Juvenile Residential Facility Census (n = 3690 facilities). Results: Controlling for facility…

  20. 33 CFR 127.1301 - Persons in charge of transfers for the facility: Qualifications and certification.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... FACILITIES HANDLING LIQUEFIED NATURAL GAS AND LIQUEFIED HAZARDOUS GAS Waterfront Facilities Handling... Operations Manual and the examined Emergency Manual. (b) Before a person in charge of transfers for a waterfront facility handling LHG supervises a transfer of LHG, the operator of the facility shall certify in...

  1. The Impact of Special Focus Facility Nursing Homes on Market Quality

    ERIC Educational Resources Information Center

    Castle, Nicholas G.; Sonon, Kristen; Antonova, Jenya

    2010-01-01

    Purpose: Special Focus Facilities (SFFs) are nursing facilities designated by the Centers for Medicare & Medicaid Services to be of chronic poor quality. Relatively few nursing facilities are included in this initiative. The purpose of this research was to examine whether nursing facilities included in the 2007 SFF initiative subsequently…

  2. GRC Ground Support Facilities

    NASA Technical Reports Server (NTRS)

    SaintOnge, Thomas H.

    2010-01-01

    The ISS Program is conducting an "ISS Research Academy' at JSC the first week of August 2010. This Academy will be a tutorial for new Users of the International Space Station, focused primarily on the new ISS National Laboratory and its members including Non-Profit Organizations, other government agencies and commercial users. Presentations on the on-orbit research facilities accommodations and capabilities will be made, as well as ground based hardware development, integration and test facilities and capabilities. This presentation describes the GRC Hardware development, test and laboratory facilities.

  3. National Facilities study

    NASA Technical Reports Server (NTRS)

    1994-01-01

    This study provides a set of recommendations for improving the effectiveness of our nation's aeronautics and space facilities. The study plan considers current and future government and commercial needs as well as DOD and NASA mission requirements through the year 2023. It addresses shortfalls in existing capabilities, new facility requirements, upgrades, consolidations, and phase-out of existing facilities. If the recommendations are implemented, they will provide world-class capability where it is vital to our country's needs and make us more efficient in meeting future needs.

  4. TRITIUM EXTRACTION FACILITY ALARA

    SciTech Connect

    Joye, BROTHERTON

    2005-04-19

    The primary mission of the Tritium Extraction Facility (TEF) is to extract tritium from tritium producing burnable absorber rods (TPBARs) that have been irradiated in a commercial light water reactor and to deliver tritium-containing gas to the Savannah River Site Facility 233-H. The tritium extraction segment provides the capability to deliver three (3) kilograms per year to the nation's nuclear weapons stockpile. The TEF includes processes, equipment and facilities capable of production-scale extraction of tritium while minimizing personnel radiation exposure, environmental releases, and waste generation.

  5. Engineering the National Ignition Facility

    SciTech Connect

    Bowers, J; Hackel, R; Larson, D; Manes, K; Murray, J; Sawicki, R

    1998-08-19

    The engineering team of the National Ignition Facility (NIF) has developed a highly optimized hardware design that satisfies stringent cost, performance and schedule requirements. After a 3-year effort, the design will culminate at the end of FY98 with the completion of major Title II design reviews. Every element of the facility from optic configuration, facility layout and hardware specifications to material selection, fabrication techniques and part tolerancing has been examined to assure the minimum cost per joule of laser energy delivered on target. In this paper, the design of the major subsystems will be discussed from the perspective of this optimization emphasis. Focus will be placed on the special equipment hardware which includes laser, beam transport, opto-mechanical , system control and target area systems. Some of the unique features in each of these areas will be discussed to highlight how significant cost savings have been achieved while maintaining reasonable and acceptable performance risk. Key to the success has also been a vigorous development program that commenced nearly 4 years ago and has been highly responsive to the specific needs of the NIF project. Supporting analyses and prototyping work that evolved from these parallel activities will also be discussed.

  6. Facility characteristics associated with the use of electronic health records in residential care facilities.

    PubMed

    Holup, Amanda A; Dobbs, Debra; Meng, Hongdao; Hyer, Kathryn

    2013-01-01

    The integration of electronic health records (EHRs) across care settings including residential care facilities (RCFs) promises to reduce medical errors and improve coordination of services. Using data from the 2010 National Survey of Residential Care Facilities (n=2302), this study examines the association between facility structural characteristics and the use of EHRs in RCFs. Findings indicate that in 2010, only 3% of RCFs nationwide were using an EHR. However, 55% of RCFs reported using a computerized system for one or more (but not all) of the functionalities defined by a basic EHR. Ownership, chain membership, staffing levels, and facility size were significantly associated with the use of one or more core EHR functionalities. These findings suggest that facility characteristics may play an important role in the adoption of EHRs in RCFs.

  7. 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 ...

  8. NETL - Fuel Reforming Facilities

    SciTech Connect

    2013-06-12

    Research using NETL's Fuel Reforming Facilities explores catalytic issues inherent in fossil-energy related applications, including catalyst synthesis and characterization, reaction kinetics, catalyst activity and selectivity, catalyst deactivation, and stability.

  9. A cryogenic test facility

    NASA Astrophysics Data System (ADS)

    Veenendaal, Ian

    The next generation, space-borne instruments for far infrared spectroscopy will utilize large diameter, cryogenically cooled telescopes in order to achieve unprecedented sensitivities. Low background, ground-based cryogenic facilities are required for the cryogenic testing of materials, components and subsystems. The Test Facility Cryostat (TFC) at the University of Lethbridge is a large volume, closed cycle, 4K cryogenic facility, developed for this purpose. This thesis discusses the design and performance of the facility and associated external instrumentation. An apparatus for measuring the thermal properties of materials is presented, and measurements of the thermal expansion and conductivity of carbon fibre reinforced polymers (CFRPs) at cryogenic temperatures are reported. Finally, I discuss the progress towards the design and fabrication of a demonstrator cryogenic, far infrared Fourier transform spectrometer.

  10. Planning Home Economics Facilities.

    ERIC Educational Resources Information Center

    Arcy, Thomas H.; Schultz, Jerelyn B.

    1980-01-01

    Discusses modernizing, remodeling, or developing new home economic facilities. Equipment considerations, curriculum objectives, the making of a master plan, and planning reminders are provided along with a basic sketch to review prior to planning home economics laboratories. (Author)

  11. Shuttle Landing Facility

    NASA Image and Video Library

    The Shuttle Landing Facility at NASA's Kennedy Space Center in Florida marked the finish line for space shuttle missions since 1984. It is also staffed by a group of air traffic controllers who wor...

  12. Ames Hybrid Combustion Facility

    NASA Technical Reports Server (NTRS)

    Zilliac, Greg; Karabeyoglu, Mustafa A.; Cantwell, Brian; Hunt, Rusty; DeZilwa, Shane; Shoffstall, Mike; Soderman, Paul T.; Bencze, Daniel P. (Technical Monitor)

    2003-01-01

    The report summarizes the design, fabrication, safety features, environmental impact, and operation of the Ames Hybrid-Fuel Combustion Facility (HCF). The facility is used in conducting research into the scalability and combustion processes of advanced paraffin-based hybrid fuels for the purpose of assessing their applicability to practical rocket systems. The facility was designed to deliver gaseous oxygen at rates between 0.5 and 16.0 kg/sec to a combustion chamber operating at pressures ranging from 300 to 900. The required run times were of the order of 10 to 20 sec. The facility proved to be robust and reliable and has been used to generate a database of regression-rate measurements of paraffin at oxygen mass flux levels comparable to those of moderate-sized hybrid rocket motors.

  13. Special Feature: Facilities.

    ERIC Educational Resources Information Center

    Storm, George; And Others

    1993-01-01

    Includes "Planning Laboratory Design" (Storm); "Perkins Money for Automotive Programs" (Cash); "Stretching a Budget" (Warren); "Video Teleconferencing--Powerful Communication for Occupational Educators" (Major); "Danger: Hazardous Materials" (Brown); and "Keeping Facilities Safe--Electrical…

  14. NETL - Fuel Reforming Facilities

    ScienceCinema

    None

    2016-07-12

    Research using NETL's Fuel Reforming Facilities explores catalytic issues inherent in fossil-energy related applications, including catalyst synthesis and characterization, reaction kinetics, catalyst activity and selectivity, catalyst deactivation, and stability.

  15. Facility Modernization Report

    SciTech Connect

    Robinson, D; Ackley, R

    2007-05-10

    Modern and technologically up-to-date facilities and systems infrastructure are necessary to accommodate today's research environment. In response, Lawrence Livermore National Laboratory (LLNL) has a continuing commitment to develop and apply effective management models and processes to maintain, modernize, and upgrade its facilities to meet the science and technology mission. The Facility Modernization Pilot Study identifies major subsystems of facilities that are either technically or functionally obsolete, lack adequate capacity and/or capability, or need to be modernized or upgraded to sustain current operations and program mission. This study highlights areas that need improvement, system interdependencies, and how these systems/subsystems operate and function as a total productive unit. Although buildings are 'grandfathered' in and are not required to meet current codes unless there are major upgrades, this study also evaluates compliance with 'current' building, electrical, and other codes. This study also provides an evaluation of the condition and overall general appearance of the structure.

  16. Special Feature: Facilities.

    ERIC Educational Resources Information Center

    Storm, George; And Others

    1993-01-01

    Includes "Planning Laboratory Design" (Storm); "Perkins Money for Automotive Programs" (Cash); "Stretching a Budget" (Warren); "Video Teleconferencing--Powerful Communication for Occupational Educators" (Major); "Danger: Hazardous Materials" (Brown); and "Keeping Facilities Safe--Electrical…

  17. 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.

  18. Facilities | ECHO | US EPA

    EPA Pesticide Factsheets

    ECHO, Enforcement and Compliance History Online, provides compliance and enforcement information for approximately 800,000 EPA-regulated facilities nationwide. ECHO includes permit, inspection, violation, enforcement action, and penalty information about facilities regulated under the Clean Air Act (CAA) Stationary Source Program, Clean Water Act (CWA) National Pollutant Elimination Discharge System (NPDES), and/or Resource Conservation and Recovery Act (RCRA). Information also is provided on surrounding demographics when available.

  19. Hanford Facility contingency plan

    SciTech Connect

    Sutton, L.N.; Miskho, A.G.; Brunke, R.C.

    1993-10-01

    The Hanford Facility Contingency Plan, together with each TSD unit-specific contingency plan, meets the WAC 173-303 requirements for a contingency plan. This plan includes descriptions of responses to a nonradiological hazardous materials spill or release at Hanford Facility locations not covered by TSD unit-specific contingency plans or building emergency plans. This plan includes descriptions of responses for spills or releases as a result of transportation activities, movement of materials, packaging, and storage of hazardous materials.

  20. Business Planning Core Facilities

    PubMed Central

    Itzkowitz, G.N.

    2014-01-01

    Thoughtful business planning is pivotal to the success of any business/operational venture. When planned in a thoughtful and detailed manner there are very few operational or financial surprises for an institution or facility (service center) to contend with. At Stony Brook Medicine we include SWOT analysis and a detailed Market Analysis as part of the process. This is bolstered by an initiative to ensure institutional policies are met so that facilities remain in compliance throughout their lifecycle. As we operate 14 facilities we have had the opportunity to become creative in our approach to coordinate activities, virtualize services, integrate new software business-to-business partners, and finally coordinate plans for phased consolidation instead of outright termination of services when required. As the Associate Dean for Scientific Operations and Research Facilities, the shared research facilities (cores) of the Medical School are in my direct line of sight. We understand their value to the meeting our overall research mission. We have found that an active process of monitoring to predict trouble as much as possible is the best approach for facilities. Some case analysis of this type of interaction will be presented as well.

  1. Engineering directorate technical facilities catalog

    NASA Technical Reports Server (NTRS)

    Maloy, Joseph E.

    1993-01-01

    The Engineering Directorate Technical Facilities Catalog is designed to provide an overview of the technical facilities available within the Engineering Directorate at the National Aeronautics and Space Administration (NASA), Lyndon B. Johnson Space Center (JSC) in Houston, Texas. The combined capabilities of these engineering facilities are essential elements of overall JSC capabilities required to manage and perform major NASA engineering programs. The facilities are grouped in the text by chapter according to the JSC division responsible for operation of the facility. This catalog updates the facility descriptions for the JSC Engineering Directorate Technical Facilities Catalog, JSC 19295 (August 1989), and supersedes the Engineering Directorate, Principle test and Development Facilities, JSC, 19962 (November 1984).

  2. Neutron-irradiation effects on high heat flux components ? examination of plasma-facing materials and their joints

    NASA Astrophysics Data System (ADS)

    Rödig, M.; Conrad, R.; Derz, H.; Duwe, R.; Linke, J.; Lodato, A.; Merola, M.; Pott, G.; Vieider, G.; Wiechers, B.

    2000-12-01

    The neutron-irradiation experiments PARIDE 1 and PARIDE 2 have been performed at 350°C and 700°C with fluences of 0.35 dpa. The major part of the post-irradiation tests are high heat flux simulation experiments carried out in the electron beam facility JUDITH. These tests cover thermal fatigue experiments with small-scale high heat flux components, and on the other hand, thermal shock tests on the plasma-facing materials. Actively cooled samples were made from CFC, or beryllium as plasma-facing materials and copper alloys as heat sink materials. Different designs (flat tile, monoblock) and joining techniques (brazing, welding) were used. Best performance was found for CFC/Cu monoblock mock-ups, but also the brazed Be/Cu flat tile mock-ups fulfill the operational requirements for first wall components. Thermal shock experiments show a higher erosion after neutron irradiation. This degradation is either due to a reduced thermal conductivity (carbon) or to a decreased ductility after irradiation (beryllium).

  3. Patient Care Staffing Levels and Facility Characteristics in U.S. Hemodialysis Facilities

    PubMed Central

    Yoder, Laura A. G.; Xin, Wenjun; Norris, Keith C.; Yan, Guofen

    2013-01-01

    Background Higher numbers of registered nurses per patient have been associated with improved patient outcomes in acute care facilities. Variation and associations of patient-care staffing levels and hemodialysis facility characteristics have not been previously examined. Study Design Cross-sectional study using Poisson regression to examine associations betwee patient-care staffing levels and hemodialysis facility characteristics. Setting & Participants 4,800 U.S. hemodialysis facilities in the 2009 CMS ESRD Annual Facility Survey (CMS-2744), USRDS. Predictors Facility characteristics, including profit status, freestanding status, chain affiliatio and geographic region, adjusted for facility size, capacity, functional type, and urbanicity. Outcomes Patient care staffing levels, including ratios of Registered Nurses (RN), Licensed Practical Nurses (LPN), Patient Care Technicians (PCT), composite staff (RN+LPN+PCT), Social Workers, and Dietitians to in-center hemodialysis patients. Results After adjusting for background facility characteristics, the ratios of RNs and LPNs to patients were 35% (p<0.001) and 42% (p<0.001) lower, but the PCT-to-patient ratio was 16% (p<0.001) higher in for-profit facilities than those in nonprofit facilities (Rate ratio, 0.65, 95%CI, 0.63–0.68; 0.58, 0.51–0.65; 1.16, 1.12–1.19; respectively). Regionally, compared to the Northeast, the adjusted RN-to-patient ratio was 14% (p< 0.001) lower in the Midwest, 25% (p< 0.001) lower in the South, and 18% (p< 0.001) lower in the West. Even after additional adjustments, the large for-profit chains had significantly lower RN and LPN ratios than the largest nonprofit chain, but a significantly higher PCT-to-patient ratio. The overall composite staffing levels were also lower in for-profit and chain-affiliated facilities. The patterns hold when the hospital-based units were excluded. Limitations Nursing hours were not available. Conclusions The significant variation in patient-care staffing

  4. Facility Environmental Vulnerability Assessment

    SciTech Connect

    Van Hoesen, S.D.

    2001-07-09

    From mid-April through the end of June 2001, a Facility Environmental Vulnerability Assessment (FEVA) was performed at Oak Ridge National Laboratory (ORNL). The primary goal of this FEVA was to establish an environmental vulnerability baseline at ORNL that could be used to support the Laboratory planning process and place environmental vulnerabilities in perspective. The information developed during the FEVA was intended to provide the basis for management to initiate immediate, near-term, and long-term actions to respond to the identified vulnerabilities. It was expected that further evaluation of the vulnerabilities identified during the FEVA could be carried out to support a more quantitative characterization of the sources, evaluation of contaminant pathways, and definition of risks. The FEVA was modeled after the Battelle-supported response to the problems identified at the High Flux Beam Reactor at Brookhaven National Laboratory. This FEVA report satisfies Corrective Action 3A1 contained in the Corrective Action Plan in Response to Independent Review of the High Flux Isotope Reactor Tritium Leak at the Oak Ridge National Laboratory, submitted to the Department of Energy (DOE) ORNL Site Office Manager on April 16, 2001. This assessment successfully achieved its primary goal as defined by Laboratory management. The assessment team was able to develop information about sources and pathway analyses although the following factors impacted the team's ability to provide additional quantitative information: the complexity and scope of the facilities, infrastructure, and programs; the significantly degraded physical condition of the facilities and infrastructure; the large number of known environmental vulnerabilities; the scope of legacy contamination issues [not currently addressed in the Environmental Management (EM) Program]; the lack of facility process and environmental pathway analysis performed by the accountable line management or facility owner; and poor

  5. View of east end of Facility 222, with Facility 223 ...

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

    View of east end of Facility 222, with Facility 223 attached on left. Facility 273 at left edge and Facility 221 at right edge of photo. - U.S. Naval Base, Pearl Harbor, Gymnasium & Theater, Neville Way, Pearl City, Honolulu County, HI

  6. Fundraising Basics for Private School Facilities.

    ERIC Educational Resources Information Center

    Roach, Arthur H.

    This report examines the process behind setting up and implementing a "capital campaign," a program for raising money for new or renovated facilities at private K-12 schools. The report briefly covers tax information regarding gifts to institutions, then offers advice for setting up a comprehensive development program, including…

  7. Financing Academic Research Facilities: A National Need.

    ERIC Educational Resources Information Center

    Norris, Julie T.

    1990-01-01

    This article examines possible changes to provide increased federal funding for university-based research facilities. The difficulties of converting between depreciation and use allowances are discussed, as is the possibility of using current market value versus acquisition cost as a basis for costing calculations and splitting the indirect cost…

  8. Fundraising Basics for Private School Facilities

    ERIC Educational Resources Information Center

    Roach, Arthur H.

    2009-01-01

    This report examines the process behind setting up and implementing a "capital campaign": a program for raising money for new or renovated facilities at private K-12 schools. The report covers tax information regarding gifts to institutions then offers advice for setting up a comprehensive development program, including fundraising software and…

  9. Facilities Guidelines for Fine Arts Programs.

    ERIC Educational Resources Information Center

    Maryland State Dept. of Education, Baltimore.

    This manual of facility guidelines examines the planning process and design features and considerations for public school fine arts programs in Maryland. Planning concepts and trends are highlighted followed by planning guidelines for dance, music, theater, visual arts, general education, and performance spaces. General design considerations…

  10. Moon Park: A research and educational facility

    NASA Technical Reports Server (NTRS)

    Kuriki, Kyoichi; Saito, Takao; Ogawa, Yukimasa

    1992-01-01

    Moon Park has been proposed as an International Space Year (ISY) event for international cooperative efforts. Moon Park will serve as a terrestrial demonstration of a prototype lunar base and provide research and educational opportunities. The kind of data that can be obtained in the Moon Park facilities is examined taking the minimum number of lunar base residents as an example.

  11. Short-term Accommodation and Relocatable Facilities.

    ERIC Educational Resources Information Center

    Metropolitan Toronto School Board (Ontario). Study of Educational Facilities.

    This SEF study examines the entire problem of temporary space needs; evaluates present solutions such as portables, busing, and space rental; and makes recommendations for a system of relocatables. The proposed system, which could be used to handle all space needs of a nonpermanent nature, would provide facilities with an internal environment…

  12. Perspectives on Leadership in Facilities Management.

    ERIC Educational Resources Information Center

    Jenkins, Charles W. Ed.

    This collection of papers examines issues concerning leadership in facilities management in higher education. Chapters include: (1) "Catch the Spirit of Leadership" (Jack Hug); (2) "Visionary Leadership: Creating a New Tomorrow" (Burt Nanus); (3) "Some Thoughts on Leadership" (Charles W. Jenkins); (4) "Educational Leadership: The Role of…

  13. Facilities Guidelines for Fine Arts Programs.

    ERIC Educational Resources Information Center

    Maryland State Dept. of Education, Baltimore.

    This manual of facility guidelines examines the planning process and design features and considerations for public school fine arts programs in Maryland. Planning concepts and trends are highlighted followed by planning guidelines for dance, music, theater, visual arts, general education, and performance spaces. General design considerations…

  14. Berkeley Low Background Facility

    NASA Astrophysics Data System (ADS)

    Thomas, K. J.; Smith, A. R.; Poon, A. W. P.; Chan, Y. D.; Norman, E. B.; Lesko, K. T.

    2015-08-01

    The Berkeley Low Background Facility (BLBF) at Lawrence Berkeley National Laboratory (LBNL) in Berkeley, California provides low background gamma spectroscopy services to a wide array of experiments and projects. The analysis of samples takes place within two unique facilities; locally within a carefully-constructed, low background laboratory on the surface at LBNL and at the Sanford Underground Research Facility (SURF) in Lead, SD. These facilities provide a variety of gamma spectroscopy services to low background experiments primarily in the form of passive material screening for primordial radioisotopes (U, Th, K) or common cosmogenic/anthropogenic products; active screening via neutron activation analysis for U,Th, and K as well as a variety of stable isotopes; and neutron flux/beam characterization measurements through the use of monitors. A general overview of the facilities, services, and sensitivities will be presented. Recent activities and upgrades will also be described including an overview of the recently installed counting system at SURF (recently relocated from Oroville, CA in 2014), the installation of a second underground counting station at SURF in 2015, and future plans. The BLBF is open to any users for counting services or collaboration on a wide variety of experiments and projects.

  15. Comprehensive facilities plan

    SciTech Connect

    1997-09-01

    The Ernest Orlando Lawrence Berkeley National Laboratory`s Comprehensive Facilities Plan (CFP) document provides analysis and policy guidance for the effective use and orderly future development of land and capital assets at the Berkeley Lab site. The CFP directly supports Berkeley Lab`s role as a multiprogram national laboratory operated by the University of California (UC) for the Department of Energy (DOE). The CFP is revised annually on Berkeley Lab`s Facilities Planning Website. Major revisions are consistent with DOE policy and review guidance. Facilities planing is motivated by the need to develop facilities for DOE programmatic needs; to maintain, replace and rehabilitate existing obsolete facilities; to identify sites for anticipated programmatic growth; and to establish a planning framework in recognition of site amenities and the surrounding community. The CFP presents a concise expression of the policy for the future physical development of the Laboratory, based upon anticipated operational needs of research programs and the environmental setting. It is a product of the ongoing planning processes and is a dynamic information source.

  16. Berkeley Low Background Facility

    SciTech Connect

    Thomas, K. J.; Norman, E. B.; Smith, A. R.; Poon, A. W. P.; Chan, Y. D.; Lesko, K. T.

    2015-08-17

    The Berkeley Low Background Facility (BLBF) at Lawrence Berkeley National Laboratory (LBNL) in Berkeley, California provides low background gamma spectroscopy services to a wide array of experiments and projects. The analysis of samples takes place within two unique facilities; locally within a carefully-constructed, low background laboratory on the surface at LBNL and at the Sanford Underground Research Facility (SURF) in Lead, SD. These facilities provide a variety of gamma spectroscopy services to low background experiments primarily in the form of passive material screening for primordial radioisotopes (U, Th, K) or common cosmogenic/anthropogenic products; active screening via neutron activation analysis for U,Th, and K as well as a variety of stable isotopes; and neutron flux/beam characterization measurements through the use of monitors. A general overview of the facilities, services, and sensitivities will be presented. Recent activities and upgrades will also be described including an overview of the recently installed counting system at SURF (recently relocated from Oroville, CA in 2014), the installation of a second underground counting station at SURF in 2015, and future plans. The BLBF is open to any users for counting services or collaboration on a wide variety of experiments and projects.

  17. Employee influenza vaccination in residential care facilities.

    PubMed

    Apenteng, Bettye A; Opoku, Samuel T

    2014-03-01

    The organizational literature on infection control in residential care facilities is limited. Using a nationally representative dataset, we examined the organizational factors associated with implementing at least 1 influenza-related employee vaccination policy/program, as well as the effect of vaccination policies on health care worker (HCW) influenza vaccine uptake in residential care facilities. The study was a cross-sectional study using data from the 2010 National Survey of Residential Care Facilities. Multivariate logistic regression analysis was used to address the study's objectives. Facility size, director's educational attainment, and having a written influenza pandemic preparedness plan were significantly associated with the implementation of at least 1 influenza-related employee vaccination policy/program, after controlling for other facility-level factors. Recommending vaccination to employees, providing vaccination on site, providing vaccinations to employees at no cost, and requiring vaccination as a condition of employment were associated with higher employee influenza vaccination rates. Residential care facilities can improve vaccination rates among employees by adopting effective employee vaccination policies. Copyright © 2014 Association for Professionals in Infection Control and Epidemiology, Inc. Published by Mosby, Inc. All rights reserved.

  18. Modernizing sports facilities

    SciTech Connect

    Dustin, R.

    1996-09-01

    Modernization and renovation of sports facilities challenge the design team to balance a number of requirements: spectator and owner expectations, existing building and site conditions, architectural layouts, code and legislation issues, time constraints and budget issues. System alternatives are evaluated and selected based on the relative priorities of these requirements. These priorities are unique to each project. At Alexander Memorial Coliseum, project schedules, construction funds and facility usage became the priorities. The ACC basketball schedule and arrival of the Centennial Olympics dictated the construction schedule. Initiation and success of the project depended on the commitment of the design team to meet coliseum funding levels established three years ago. Analysis of facility usage and system alternative capabilities drove the design team to select a system that met the project requirements and will maximize the benefits to the owner and spectators for many years to come.

  19. A Materials Exposure Facility

    NASA Technical Reports Server (NTRS)

    Slemp, Wayne S.; Avery, Don E.

    1995-01-01

    The objective of the Materials Exposure Facility (MEF) is to provide a test bed in space for conducting long-term (greater than one year) materials experiments which require exposure to the low Earth orbit (LEO) space environment. The proposed MEF is planned to be an integral part of the agency's Space Environments and Effects Research Program. The facility will provide experiment trays similar to the Long Duration Exposure Facility (LDEF). Each tray location is planned to have a power and data interface and robotic installation and removal provisions. Space environmental monitoring for each side of the MEF will also be provided. Since routine access to MEF for specimen retrieval is extremely important to the materials research, Space Station Freedom has been chosen as the preferred MEF carrier.

  20. Mars ultraviolet simulation facility.

    PubMed

    Zill, L P; Mack, R; DeVincenzi, D L

    1979-12-01

    A facility was established for long-duration ultraviolet (UV) radiation exposure of natural and synthetic materials in order to test hypotheses concerning Martian soil chemistry observed by the Viking Mars landers. The system utilized a 2500 watt xenon lamp as the radiation source, with the beam passing through a heat-dissipating water filter before impinging upon an exposure chamber containing the samples to be irradiated. The chamber was designed to allow for continuous tumbling of the samples, maintenance of temperatures below 0 degrees C during exposure, and monitoring of beam intensity. The facility also provided for sample preparation under a variety of atmospheric conditions, in addition to the Mars nominal. As many as 33 sealed sample ampules have been irradiated in a single exposure. Over 100 samples have been irradiated for approximately 100 to 700 h. The facility has performed well in providing continuous UV irradiation of multiple samples for long periods of time under simulated Mars atmospheric and thermal conditions.

  1. Facility capability assessment.

    PubMed

    McCandless, J

    1994-06-01

    An inspection and evaluation procedure has been developed to assess the capabilities of contract toxicology laboratories. This procedure has been used for the inspection of 18 different contract toxicology laboratories. There are 10 areas inspected: 1. Facility 2. Personnel 3. Operations 4. Animals/Animal Care 5. Standard Operating Procedures 6. Quality Assurance 7. Equipment 8. Test Article 9. Data 10. Archives. Each of these areas is divided into categories with each category divided further into specific topics. Points are assigned to each topic. The points earned by the laboratory reflect the inspector's assessment of the laboratory's quality in each area. Area scores are added and a percentage score for the facility is calculated. This approach provides a clear distinction among the laboratories evaluated. The facility inspection and rating system played an important role in screening laboratories when the author worked for the Atlantic Richfield Company (ARCO) corporate toxicology department. It highlighted strengths and weaknesses of individual laboratories.

  2. Examination Management and Examination Malpractice: The Nexus

    ERIC Educational Resources Information Center

    Ogunji, James A.

    2011-01-01

    Examination malpractice or cheating has become a global phenomenon. In different countries of the world today, developed and developing, academic dishonesty especially cheating in examinations has heightened and taken frightening dimension. In many countries of the world this phenomenon has become a serious matter of concern that has left many…

  3. Examination Management and Examination Malpractice: The Nexus

    ERIC Educational Resources Information Center

    Ogunji, James A.

    2011-01-01

    Examination malpractice or cheating has become a global phenomenon. In different countries of the world today, developed and developing, academic dishonesty especially cheating in examinations has heightened and taken frightening dimension. In many countries of the world this phenomenon has become a serious matter of concern that has left many…

  4. Characterizing User Communities of Large Multi-Disciplinary Research Facilities

    NASA Astrophysics Data System (ADS)

    Ludwig, K. A.

    2012-12-01

    Large-scale multi-user research facilities are a critical component of the federal science and engineering research enterprise. Developing infrastructure for multidisciplinary research requires large investments over long periods of time and typically involves partnerships across many institutions. Consequently, multiple policy questions surround federal investments in large research facilities including what is the best way to maximize scientific productivity? How should investments in infrastructure be balanced with support for individual or small group research? For many facilities, the answers to these questions become focused on the activities of the users: the individuals who are interacting with the facility for furthering scientific research and/or education. This independent study provides the first known analysis of facility utilization. Four facilities supported by the National Science Foundation (NSF) are used as case studies to create a conceptual framework for characterizing facility utilization, to examine changes in facility use over time, and to define how lessons learned can be applied to facility management and planning. Results show that there is a broad spectrum of users who interact with each facility in different ways and that for some facilities, unanticipated users are driving new areas of research. This work also shows that cyberinfrastructure-enabled facilities are experiencing rapid increases in data use and in some cases, the next generation of facility users appears to be developing new skills for working in an increasingly data-intensive research environment. Characterizing and quantifying large facility use will likely become increasingly important as the federal government continues to focus on developing metrics and evaluation tools for its investments in science and engineering research. This work establishes a foundation for assessing facility utilization and shows that this area is ripe for future work that may include portfolio

  5. National Facilities Study. Volume 1: Facilities Inventory

    NASA Technical Reports Server (NTRS)

    1994-01-01

    The inventory activity was initiated to solve the critical need for a single source of site specific descriptive and parametric data on major public and privately held aeronautics and aerospace related facilities. This a challenging undertaking due to the scope of the effort and the short lead time in which to assemble the inventory and have it available to support the task group study needs. The inventory remains dynamic as sites are being added and the data is accessed and refined as the study progresses. The inventory activity also included the design and implementation of a computer database and analytical tools to simplify access to the data. This volume describes the steps which were taken to define the data requirements, select sites, and solicit and acquire data from them. A discussion of the inventory structure and analytical tools is also provided.

  6. Practice Experiences at a Single Institutional Practice Site to Improve Advanced Pharmacy Practice Examination Performance

    PubMed Central

    Britton, Mark L.; Wheeler, Richard E.; Carter, Sandra M.

    2014-01-01

    Objective. To determine whether sequential assignment of students to the same facility for institutional practice experiences improves their advanced pharmacy practice experience (APPE) examination scores. Design. Student volunteers were assigned to the same healthcare facility for all institutional introductory pharmacy practice experiences (IPPEs) and advanced pharmacy practice experiences (APPEs). Other students completed institutional IPPEs and APPEs at separate healthcare facilities, ranging from 2 to 4 different facilities per student. APPE examination scores of students assigned to the same facility for all institutional learning experiences were compared with those of students assigned to more than 1 institutional practice site. Assessment. Holding grade point average constant, students assigned to the same facility for institutional IPPEs and APPEs scored 3 percentage points higher on the APPE institutional examination compared with students assigned to separate facilities for these experiences. Conclusion. Assigning students to the same facility for both institutional IPPEs and APPEs positively influenced knowledge-based APPE examination performance. PMID:24761021

  7. Modular space station facilities.

    NASA Technical Reports Server (NTRS)

    Parker, P. J.

    1973-01-01

    The modular space station will operate as a general purpose laboratory (GPL). In addition, the space station will be able to support many attached or free-flying research and application modules that would be dedicated to specific projects like astronomy or earth observations. The GPL primary functions have been organized into functional laboratories including an electrical/electronics laboratory, a mechanical sciences laboratory, an experiment and test isolation laboratory, a hard data process facility, a data evaluation facility, an optical sciences laboratory, a biomedical and biosciences laboratory, and an experiment/secondary command and control center.

  8. Electromagnetic propulsion test facility

    NASA Technical Reports Server (NTRS)

    Gooder, S. T.

    1984-01-01

    A test facility for the exploration of electromagnetic propulsion concept is described. The facility is designed to accommodate electromagnetic rail accelerators of various lengths (1 to 10 meters) and to provide accelerating energies of up to 240 kiloJoules. This accelerating energy is supplied as a current pulse of hundreds of kiloAmps lasting as long as 1 millisecond. The design, installation, and operating characteristics of the pulsed energy system are discussed. The test chamber and its operation at pressures down to 1300 Pascals (10 mm of mercury) are described. Some aspects of safety (interlocking, personnel protection, and operating procedures) are included.

  9. Space Station life science research facility - The vivarium/laboratory

    NASA Technical Reports Server (NTRS)

    Hilchey, J. D.; Arno, R. D.

    1985-01-01

    Research opportunities possible with the Space Station are discussed. The objective of the research program will be study gravity relationships for animal and plant species. The equipment necessary for space experiments including vivarium facilities are described. The cost of the development of research facilities such as the vivarium/laboratory and a bioresearch centrifuge is examined.

  10. 19 CFR 151.24 - Unlading facilities for bulk sugar.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 19 Customs Duties 2 2014-04-01 2014-04-01 false Unlading facilities for bulk sugar. 151.24 Section... OF THE TREASURY (CONTINUED) EXAMINATION, SAMPLING, AND TESTING OF MERCHANDISE Sugars, Sirups, and Molasses § 151.24 Unlading facilities for bulk sugar. When dutiable sugar is to be imported in bulk, a full...

  11. 19 CFR 151.24 - Unlading facilities for bulk sugar.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 19 Customs Duties 2 2013-04-01 2013-04-01 false Unlading facilities for bulk sugar. 151.24 Section... OF THE TREASURY (CONTINUED) EXAMINATION, SAMPLING, AND TESTING OF MERCHANDISE Sugars, Sirups, and Molasses § 151.24 Unlading facilities for bulk sugar. When dutiable sugar is to be imported in bulk, a full...

  12. 19 CFR 151.24 - Unlading facilities for bulk sugar.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 19 Customs Duties 2 2010-04-01 2010-04-01 false Unlading facilities for bulk sugar. 151.24 Section... OF THE TREASURY (CONTINUED) EXAMINATION, SAMPLING, AND TESTING OF MERCHANDISE Sugars, Sirups, and Molasses § 151.24 Unlading facilities for bulk sugar. When dutiable sugar is to be imported in bulk, a full...

  13. 19 CFR 151.24 - Unlading facilities for bulk sugar.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 19 Customs Duties 2 2012-04-01 2012-04-01 false Unlading facilities for bulk sugar. 151.24 Section... OF THE TREASURY (CONTINUED) EXAMINATION, SAMPLING, AND TESTING OF MERCHANDISE Sugars, Sirups, and Molasses § 151.24 Unlading facilities for bulk sugar. When dutiable sugar is to be imported in bulk, a full...

  14. 19 CFR 151.24 - Unlading facilities for bulk sugar.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 19 Customs Duties 2 2011-04-01 2011-04-01 false Unlading facilities for bulk sugar. 151.24 Section... OF THE TREASURY (CONTINUED) EXAMINATION, SAMPLING, AND TESTING OF MERCHANDISE Sugars, Sirups, and Molasses § 151.24 Unlading facilities for bulk sugar. When dutiable sugar is to be imported in bulk, a full...

  15. Alaska School Facilities Preventive Maintenance Handbook. 1997 Edition.

    ERIC Educational Resources Information Center

    Mearig, Tim; Crittenden, Edwin; Morgan, Michael

    The State of Alaska has issued preventive maintenance guidelines for educational facilities designed to prevent premature failure, or to maximize or extend the useful life of a facility and its components, including roofing inspections, repainting, and door hardware adjustments. The handbook examines preventive maintenance state legislation, and…

  16. The Impact of School Facilities on the Learning Environment

    ERIC Educational Resources Information Center

    Vandiver, Bert

    2011-01-01

    The purpose of this mixed methods study was to examine the impact of the quality of facilities on the educational environment in high schools located in northeast Texas. The intent of this research study was to determine the relationship between school facilities and the school-learning environment. This study was a mixed method research that used…

  17. Leasing Public Facilities to Private Concerns: Some Legal Checkpoints.

    ERIC Educational Resources Information Center

    Kozlowski, James

    1982-01-01

    Court cases are reviewed to show factors that courts are most likely to examine in determining the legality of leasing public recreational facilities to private operators. A checklist for developing defensible leasing arrangements of public recreational facilities to private operators is provided. (CJ)

  18. The Impact of School Facilities on the Learning Environment

    ERIC Educational Resources Information Center

    Vandiver, Bert

    2011-01-01

    The purpose of this mixed methods study was to examine the impact of the quality of facilities on the educational environment in high schools located in northeast Texas. The intent of this research study was to determine the relationship between school facilities and the school-learning environment. This study was a mixed method research that used…

  19. 9 CFR 88.5 - Requirements at a slaughtering facility.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... COMMERCIAL TRANSPORTATION OF EQUINES FOR SLAUGHTER § 88.5 Requirements at a slaughtering facility. (a) Upon arrival at a slaughtering facility, the owner/shipper must: (1) Ensure that each equine has access to... representative; (3) Allow a USDA representative access to the equines for the purpose of examination; and (4...

  20. 9 CFR 88.5 - Requirements at a slaughtering facility.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... COMMERCIAL TRANSPORTATION OF EQUINES FOR SLAUGHTER § 88.5 Requirements at a slaughtering facility. (a) Upon arrival at a slaughtering facility, the owner/shipper must: (1) Ensure that each equine has access to... representative; (3) Allow a USDA representative access to the equines for the purpose of examination; and (4...

  1. Lunar base launch and landing facility conceptual design, 2nd edition

    NASA Technical Reports Server (NTRS)

    1988-01-01

    This report documents the Lunar Base Launch and Landing Facility Conceptual Design study. The purpose of this study was to examine the requirements for launch and landing facilities for early lunar bases and to prepare conceptual designs for some of these facilities. The emphasis of this study is on the facilities needed from the first manned landing until permanent occupancy. Surface characteristics and flight vehicle interactions are described, and various facility operations are related. Specific recommendations for equipment, facilities, and evolutionary planning are made, and effects of different aspects of lunar development scenarios on facilities and operations are detailed. Finally, for a given scenario, a specific conceptual design is developed and presented.

  2. National facilities study. Volume 4: Space operations facilities task group

    NASA Technical Reports Server (NTRS)

    1994-01-01

    The principal objectives of the National Facilities Study (NFS) were to: (1) determine where U.S. facilities do not meet national aerospace needs; (2) define new facilities required to make U.S. capabilities 'world class' where such improvements are in the national interest; (3) define where consolidation and phase-out of existing facilities is appropriate; and (4) develop a long-term national plan for world-class facility acquisition and shared usage. The Space Operations Facilities Task Group defined discrete tasks to accomplish the above objectives within the scope of the study. An assessment of national space operations facilities was conducted to determine the nation's capability to meet the requirements of space operations during the next 30 years. The mission model used in the study to define facility requirements is described in Volume 3. Based on this model, the major focus of the Task Group was to identify any substantive overlap or underutilization of space operations facilities and to identify any facility shortfalls that would necessitate facility upgrades or new facilities. The focus of this initial study was directed toward facility recommendations related to consolidations, closures, enhancements, and upgrades considered necessary to efficiently and effectively support the baseline requirements model. Activities related to identifying facility needs or recommendations for enhancing U.S. international competitiveness and achieving world-class capability, where appropriate, were deferred to a subsequent study phase.

  3. Issues in providing a reliable multicast facility

    NASA Technical Reports Server (NTRS)

    Dempsey, Bert J.; Strayer, W. Timothy; Weaver, Alfred C.

    1990-01-01

    Issues involved in point-to-multipoint communication are presented and the literature for proposed solutions and approaches surveyed. Particular attention is focused on the ideas and implementations that align with the requirements of the environment of interest. The attributes of multicast receiver groups that might lead to useful classifications, what the functionality of a management scheme should be, and how the group management module can be implemented are examined. The services that multicasting facilities can offer are presented, followed by mechanisms within the communications protocol that implements these services. The metrics of interest when evaluating a reliable multicast facility are identified and applied to four transport layer protocols that incorporate reliable multicast.

  4. Pandemic Influenza and Jail Facilities and Populations

    PubMed Central

    Maruschak, Laura M.; Sabol, William J.; Potter, R. H.; Cramer, Emily W.

    2009-01-01

    Persons processed into and through jail facilities in the United States may be particularly vulnerable during an influenza pandemic. Among other concerns, public health and corrections officials need to consider flow issues, the high turnover and transitions between jails and the community, and the decentralized organization of jails. In this article, we examine some of the unique challenges jail facilities may face during an influenza pandemic and discuss issues that should be addressed to reduce the spread of illness and lessen the impact of an influenza pandemic on the jail population and their surrounding communities. PMID:19797746

  5. PFP Wastewater Sampling Facility

    SciTech Connect

    Hirzel, D.R.

    1995-05-11

    This test report documents the results obtained while conducting operational testing of the sampling equipment in the 225-WC building, the PFP Wastewater Sampling Facility. The Wastewater Sampling Facility houses equipment to sample and monitor the PFP`s liquid effluents before discharging the stream to the 200 Area Treated Effluent Disposal Facility (TEDF). The majority of the streams are not radioactive and discharges from the PFP Heating, Ventilation, and Air Conditioning (HVAC). The streams that might be contaminated are processed through the Low Level Waste Treatment Facility (LLWTF) before discharging to TEDF. The sampling equipment consists of two flow-proportional composite samplers, an ultrasonic flowmeter, pH and conductivity monitors, chart recorder, and associated relays and current isolators to interconnect the equipment to allow proper operation. Data signals from the monitors are received in the 234-5Z Shift Office which contains a chart recorder and alarm annunciator panel. The data signals are also duplicated and sent to the TEDF control room through the Local Control Unit (LCU). Performing the OTP has verified the operability of the PFP wastewater sampling system. This Operability Test Report documents the acceptance of the sampling system for use.

  6. Facility Focus: Science Buildings.

    ERIC Educational Resources Information Center

    College Planning & Management, 1998

    1998-01-01

    Provides an overview of five custom designs used in university science buildings. Descriptions include renovation to a mechanical engineering lab, construction of a new building for molecular biology, the reconstruction of chemistry labs, the renovation of a vision lab, and a new research and education facility. Includes photos. (RJM)

  7. High energy forming facility

    NASA Technical Reports Server (NTRS)

    Ciurlionis, B.

    1967-01-01

    Watertight, high-explosive forming facility, 25 feet in diameter and 15 feet deep, withstands repeated explosions of 10 pounds of TNT equivalent. The shell is fabricated of high strength steel and allows various structural elements to deform or move elastically and independently while retaining structural integrity.

  8. Administering the Preschool Facility.

    ERIC Educational Resources Information Center

    Coonrod, Debbie

    Securing the right environment for a preschool program requires planning and research. Administrators or searching parties are advised to study zoning codes to become acquainted with state sanitation and safety regulations and laws, to involve teachers in cooperative planning, to design facilities which discourage vandalism, facilitate…

  9. Mineral facilities of Europe

    USGS Publications Warehouse

    Almanzar, Francisco; Baker, Michael S.; Elias, Nurudeen; Guzman, Eric

    2010-01-01

    This map displays over 1,700 records of mineral facilities within the countries of Europe and western Eurasia. Each record represents one commodity and one facility type at a single geographic location. Facility types include mines, oil and gas fields, and plants, such as refineries, smelters, and mills. Common commodities of interest include aluminum, cement, coal, copper, gold, iron and steel, lead, nickel, petroleum, salt, silver, and zinc. Records include attributes, such as commodity, country, location, company name, facility type and capacity (if applicable), and latitude and longitude geographical coordinates (in both degrees-minutes-seconds and decimal degrees). The data shown on this map and in table 1 were compiled from multiple sources, including (1) the most recently available data from the U.S. Geological Survey (USGS) Minerals Yearbook (Europe and Central Eurasia volume), (2) mineral statistics and information from the USGS Minerals Information Web site (http://minerals.usgs.gov/minerals/pubs/country/europe.html), and (3) data collected by the USGS minerals information country specialists from sources, such as statistical publications of individual countries, annual reports and press releases of operating companies, and trade journals. Data reflect the most recently published table of industry structure for each country at the time of this publication. Additional information is available from the country specialists listed in table 2.

  10. Facilities of Environmental Distinction

    ERIC Educational Resources Information Center

    Pascopella, Angela

    2011-01-01

    Three of nine school buildings that have won the latest Educational Facility Design Awards from the American Institute of Architects (AIA) Committee on Architecture for Education stand out from the crowd of other school buildings because they are sustainable and are connected to the nature that surrounds them. They are: (1) Thurston Elementary…

  11. Science and Technology Facilities

    ERIC Educational Resources Information Center

    Moonen, Jean-Marie; Buono, Nicolas; Handfield, Suzanne

    2004-01-01

    These four articles relate to science and technology infrastructure for secondary and tertiary institutions. The first article presents a view on approaches to teaching science in school and illustrates ideal science facilities for secondary education. The second piece reports on work underway to improve the Science Complex at the "Universite…

  12. Facility effluent monitoring

    SciTech Connect

    Gleckler, B.P.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the facility effluent monitoring programs and provides an evaluation of effluent monitoring data. These evaluations are useful in assessing the effectiveness of effluent treatment and control systems, as well as management practices.

  13. Financing School Facilities.

    ERIC Educational Resources Information Center

    Honeyman, David S., Ed.

    Millions of students are attending classes in substandard schools, a condition that is becoming a major concern for many public school parents, teachers, students, and administrators. This report is the result of research investigating school facility issues, assessing the scope of the problem, and making recommendations to the membership of the…

  14. PLANNING VOCATIONAL AGRICULTURAL FACILITIES.

    ERIC Educational Resources Information Center

    Oregon State Dept. of Education, Salem.

    INFORMATION ON PLANNING AND DEVELOPING ADEQUATE AND ECONOMICAL VOCATIONAL AGRICULTURE FACILITIES IS PRESENTED FOR ADMINISTRATORS, ARCHITECTS, AND OTHERS. IT INCLUDES (1) GENERAL CONSIDERATIONS, (2) RECOMMENDATIONS FOR CLASSROOM, LABORATORY, AND LIBRARY, (3) RECOMMENDATIONS FOR FARM MECHANICS SHOP, SHOP STORAGE, AND SAFETY DEVICES, (4) EXAMPLES OF…

  15. Industrial Education Facilities.

    ERIC Educational Resources Information Center

    Michigan State Dept. of Public Instruction, Lansing.

    Factors for consideration by an industrial education planning committee are discussed. Selection, purchasing, and storage of new types of equipment and supplies, in addition to students' project storage, are noted as worthy of consideration in planning the shop facility. Planning factors for the various types of industrial arts laboratories are…

  16. Aid for Facilities

    ERIC Educational Resources Information Center

    Kennedy, Mike

    2009-01-01

    Even before the state fire marshal ordered the Somersworth (N.H.) School District in 2007 to abandon the top two floors of Hilltop Elementary School because of safety concerns, folks in the city of 12,000 had been debating whether the aging facility should be replaced--and how to pay for it. Finally, in February 2009, the city council approved…

  17. Variable gravity research facility

    NASA Technical Reports Server (NTRS)

    Allan, Sean; Ancheta, Stan; Beine, Donna; Cink, Brian; Eagon, Mark; Eckstein, Brett; Luhman, Dan; Mccowan, Daniel; Nations, James; Nordtvedt, Todd

    1988-01-01

    Spin and despin requirements; sequence of activities required to assemble the Variable Gravity Research Facility (VGRF); power systems technology; life support; thermal control systems; emergencies; communication systems; space station applications; experimental activities; computer modeling and simulation of tether vibration; cost analysis; configuration of the crew compartments; and tether lengths and rotation speeds are discussed.

  18. Revitalization of School Facilities.

    ERIC Educational Resources Information Center

    Coffey, Andrea Barlow

    This study analyzed current practices in the revitalization of school buildings and assimilates data that can be used by school administrators when deciding on revitalization issues. Data from nine revitalized schools since 1985 and a literature review of the elements for planning the revitalization of school facilities indicate that structural…

  19. Facilities of the Future

    ERIC Educational Resources Information Center

    Grayson, Jennifer

    2009-01-01

    The bricks-and-mortar infrastructure of community colleges has not nearly kept pace with increases in student enrollments. Not only are colleges bursting at the proverbial seams, but, according to the American Graduation Initiative, many two-year institutions "face large needs due to deferred maintenance or lack the modern facilities and…

  20. Facility Focus: Science Buildings.

    ERIC Educational Resources Information Center

    College Planning & Management, 1998

    1998-01-01

    Provides an overview of five custom designs used in university science buildings. Descriptions include renovation to a mechanical engineering lab, construction of a new building for molecular biology, the reconstruction of chemistry labs, the renovation of a vision lab, and a new research and education facility. Includes photos. (RJM)

  1. Excellent Writers, Facile Thinkers

    ERIC Educational Resources Information Center

    Jacoby, Russell

    2007-01-01

    In this article, the author discusses the writing style of conservative writers. Here, the author describes conservatism and conservative writers as excellent and facile thinkers. He added that conservatives are best at puncturing liberal, especially academic, balderdash. Apart from that, they uphold a minimal government but maximum government…

  2. Facilities Data System Manual.

    ERIC Educational Resources Information Center

    Acridge, Charles W.; Ford, Tim M.

    The purposes of this manual are to set forth the scope and procedures for the maintenance and operation of the University of California facilities Data System (FDX) and to serve as a reference document for users of the system. FDX is an information system providing planning and management data about the existing physical plant. That is, it…

  3. 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.

  4. Book Processing Facility Design.

    ERIC Educational Resources Information Center

    Sheahan (Drake)-Stewart Dougall, Marketing and Physical Distribution Consultants, New York, NY.

    The Association of New York Libraries for Technical Services (ANYLTS) is established to develop and run a centralized book processing facility for the public library systems in New York State. ANYLTS plans to receive book orders from the 22 library systems, transmit orders to publishers, receive the volumes from the publishers, print and attach…

  5. Administering the Preschool Facility.

    ERIC Educational Resources Information Center

    Coonrod, Debbie

    Securing the right environment for a preschool program requires planning and research. Administrators or searching parties are advised to study zoning codes to become acquainted with state sanitation and safety regulations and laws, to involve teachers in cooperative planning, to design facilities which discourage vandalism, facilitate…

  6. Aid for Facilities

    ERIC Educational Resources Information Center

    Kennedy, Mike

    2009-01-01

    Even before the state fire marshal ordered the Somersworth (N.H.) School District in 2007 to abandon the top two floors of Hilltop Elementary School because of safety concerns, folks in the city of 12,000 had been debating whether the aging facility should be replaced--and how to pay for it. Finally, in February 2009, the city council approved…

  7. Optimal Facility-Location.

    PubMed

    Goldman, A J

    2006-01-01

    Dr. Christoph Witzgall, the honoree of this Symposium, can count among his many contributions to applied mathematics and mathematical operations research a body of widely-recognized work on the optimal location of facilities. The present paper offers to non-specialists a sketch of that field and its evolution, with emphasis on areas most closely related to Witzgall's research at NBS/NIST.

  8. Facilities of Environmental Distinction

    ERIC Educational Resources Information Center

    Pascopella, Angela

    2011-01-01

    Three of nine school buildings that have won the latest Educational Facility Design Awards from the American Institute of Architects (AIA) Committee on Architecture for Education stand out from the crowd of other school buildings because they are sustainable and are connected to the nature that surrounds them. They are: (1) Thurston Elementary…

  9. Food Service Facilities.

    ERIC Educational Resources Information Center

    Rifenbark, Ray

    This annotated bibliography included summaries of 14 articles and one report dealing with the topic of school and college food service programs. A brief introduction discusses the current trend toward more diversified use of food service facilities and describes recent innovations in the preparation and distribution of students' meals. Many of the…

  10. Science and Technology Facilities

    ERIC Educational Resources Information Center

    Moonen, Jean-Marie; Buono, Nicolas; Handfield, Suzanne

    2004-01-01

    These four articles relate to science and technology infrastructure for secondary and tertiary institutions. The first article presents a view on approaches to teaching science in school and illustrates ideal science facilities for secondary education. The second piece reports on work underway to improve the Science Complex at the "Universite…

  11. Surveying School Facilities Needs.

    ERIC Educational Resources Information Center

    Weichel, Harry J.; Dennell, James

    1990-01-01

    Ralston (Nebraska) Public School District's communitywide survey helped set school facilities priorities while keeping the district's finite resources firmly in mind. With an outline of maintenance costs for the next 10 years, the district can develop a strategic construction schedule. The board also has the option of financing projects through a…

  12. NRL Tropical Exposure Facilities

    DTIC Science & Technology

    1947-04-01

    canal. To the east, on the opposite side of Limon Bay, lies Cristobal , Coco Solo, and Colon . Travel between Fort Sherman and Cristobal is accomplished...precision equipment. I 4 NRL TROPICAL EXPOSURE FACILITIES 5 Accessibility Proximity of the station to the port of Cristobal and to the Naval Air Station

  13. Test facilities for VINCI®

    NASA Astrophysics Data System (ADS)

    Greuel, Dirk; Schäfer, Klaus; Schlechtriem, Stefan

    2013-09-01

    With the replacement of the current upper-stage ESC-A of the Ariane 5 launcher by an enhanced cryogenic upper-stage, ESA's Ariane 5 Midterm Evolution (A5-ME) program aims to raise the launcher's payload capacity in geostationary transfer orbit from 10 to 12 tons, an increase of 20 %. Increasing the in-orbit delivery capability of the A5-ME launcher requires a versatile, high-performance, evolved cryogenic upper-stage engine suitable for delivering multiple payloads to all kinds of orbits, ranging from low earth orbit to geostationary transfer orbit with increased perigee. In order to meet these requirements the re-ignitable liquid oxygen/liquid hydrogen expander cycle engine VINCI® currently under development is designated to power the future upper stage, featuring a design performance of 180 kN of thrust and 464 s of specific impulse. Since 2010 development tests for the VINCI® engine have been conducted at the test benches P3.2 and P4.1 at DLR test site in Lampoldshausen under the ESA A5-ME program. For the VINCI® combustion chamber development the P3.2 test facility is used, which is the only European thrust chamber test facility. Originally erected for the development of the thrust chamber of the Vulcain engine, in 2003 the test facility was modified that today it is able to simulate vacuum conditions for the ignition and startup of the VINCI® combustion chamber. To maintain the test operations under vacuum conditions over an entire mission life of the VINCI® engine, including re-ignition following long and short coasting phases, between 2000 and 2005 the test facility P4.1 was completely rebuilt into a new high-altitude simulation facility. During the past two P4.1 test campaigns in 2010 and 2011 a series of important milestones were reached in the development of the VINCI® engine. In preparation for future activities within the frame of ESA's A5-ME program DLR has already started the engineering of a stage test facility for the prospective upper stage

  14. The Multistage Compressor Facility

    NASA Technical Reports Server (NTRS)

    Flegel, Ashlie

    2004-01-01

    Research and developments of new aerospace technologies is one of Glenn Research Center's specialties. One facility that deals with the research of aerospace technologies is the High-speed Multistage Compressor Facility. This facility will be testing the performance and efficiency of an Ultra Efficient Engine Technology (UEET) two-stage compressor. There is a lot of preparation involved with testing something of this caliber. Before the test article can be installed into the test rig, the facility must be fully operational and ready to run. Meaning all the necessary instrumentation must be calibrated and installed in the facility. The test rig should also be in safe operating condition, and the proper safety permits obtained. In preparation for the test, the Multistage Compressor Facility went through a few changes. For instance the facility will now be utilizing slip rings, the gearbox went through some maintenance, new lubrications systems replaced the old ones, and special instrumentation needs to be fine tuned to achieve the maximum amount of accurate data. Slips rings help gather information off of a rotating device - in this case from a shaft - onto stationary contacts. The contacts (or brushes) need to be cooled to reduce the amount of frictional heat produced between the slip ring and brushes. The coolant being run through the slip ring is AK-225, a material hazardous to the ozone. To abide by the safety regulations the coolant must be run through a closed chiller system. A new chiller system was purchased but the reservoir that holds the coolant was ventilated which doesn t make the system truly closed and sealed. My task was to design and have a new reservoir built for the chiller system that complies with the safety guidelines. The gearbox had some safety issues also. Located in the back of the gearbox an inching drive was set up. When the inching drive is in use the gears and chain are bare and someone can easily get caught up in it. So to prevent

  15. Caring for juveniles with mental disorders in adult corrections facilities.

    PubMed

    Wills, Cheryl D

    2017-02-01

    Although juveniles have developmental, educational, healthcare, and rehabilitation needs that differ from adults, thousands of them have been confined in adult corrections facilities in the past 30 years. This manuscript will review how and why juveniles end up in adult corrections facilities, who they are, their rehabilitative needs, and how they differ from adults in corrections facilities and youths in the juvenile justice system. The importance of providing developmentally-informed mental health services to youths in adult corrections facilities is examined, along with barriers to traditional adolescent psychiatric practice. Recommendations for future directions in adolescent psychiatric care are presented.

  16. DOE handbook: Guide to good practices for oral examinations

    SciTech Connect

    1997-09-01

    The purpose of this handbook is to provide DOE nuclear facilities (and others) with guidance that can be used to incorporate oral examination techniques and processes into their training programs. The handbook was developed on the basis of experience in the nuclear industry and incorporates information from civilian, military, commercial, and DOE nuclear sources. Different types of oral examinations are addressed and discussed, including informal, formal, checkouts, facility walkthroughs, operational examinations, and performance demonstrations. Guidelines for administering and grading oral examinations are provided for conducting consistent and reliable oral examinations. 1 tab.

  17. 27 CFR 19.12 - Furnishing facilities and assistance.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... with the necessary facilities and assistance in order to gauge spirits in any container, or to examine... locations (that is, buildings, rooms, or areas) where spirits in cases are stored. (26 U.S.C. 5202, 5203) ...

  18. Psychiatric and Medical Health Care Policies in Juvenile Detention Facilities

    ERIC Educational Resources Information Center

    Pajer, Kathleen A.; Kelleher, Kelly; Gupta, Ravindra A.; Rolls, Jennifer; Gardner, William

    2007-01-01

    A study aims to examine the existing health care policies in U.S. juvenile detention centres. The results conclude that juvenile detention facilities have many shortfalls in providing care for adolescents, particularly mental health care.

  19. Psychiatric and Medical Health Care Policies in Juvenile Detention Facilities

    ERIC Educational Resources Information Center

    Pajer, Kathleen A.; Kelleher, Kelly; Gupta, Ravindra A.; Rolls, Jennifer; Gardner, William

    2007-01-01

    A study aims to examine the existing health care policies in U.S. juvenile detention centres. The results conclude that juvenile detention facilities have many shortfalls in providing care for adolescents, particularly mental health care.

  20. On-orbit technology experiment facility definition

    NASA Technical Reports Server (NTRS)

    Russell, Richard A.; Buchan, Robert W.; Gates, Richard M.

    1988-01-01

    A study was conducted to identify on-orbit integrated facility needs to support in-space technology experiments on the Space Station and associated free flyers. In particular, the first task was to examine the proposed technology development missions (TDMX's) from the model mission set and other proposed experimental facilities, both individually and by theme, to determine how and if the experiments might be combined, what equipment might be shared, what equipment might be used as generic equipment for continued experimentation, and what experiments will conflict with the conduct of other experiments or Space Station operations. Then using these results, to determine on-orbit facility needs to optimize the implementation of technology payloads. Finally, to develop one or more scenarios, design concepts, and outfitting requirements for implementation of onboard technology experiments.

  1. Facilities for music education and their acoustical design.

    PubMed

    Koskinen, Heli; Toppila, Esko; Olkinuora, Pekka

    2010-01-01

    Good rehearsal facilities for musicians are essential. Directive 2003/10/EC necessitates that musicians are protected from noise exposure. A code of conduct gives the guidelines how this should be done. This study examines room acoustics recommendations provided by the Finnish code of conduct, and discusses whether they are adequate. Small teaching facilities were measured after renovation and compared to earlier measurements. Teachers' opinions were inquired about the facilities before and after. The renovation did not decrease the noise exposure of the teachers. However, the majority preferred the facilities after the renovation. The Finnish code of conduct is not sufficient for facilities where loud instruments are played, or band practise. Good facilities can be designed but they must be specified at the designing stage for their intended use.

  2. View of Facility 222 (on right) and Facility 221 through ...

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

    View of Facility 222 (on right) and Facility 221 through trees (parapet of latter above trees) from the parade ground. - U.S. Naval Base, Pearl Harbor, Gymnasium & Theater, Neville Way, Pearl City, Honolulu County, HI

  3. VIEW TO NORTHWEST, SHOWING FACILITY NO. 525 AND HOSPITAL (FACILITY ...

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

    VIEW TO NORTHWEST, SHOWING FACILITY NO. 525 AND HOSPITAL (FACILITY No. 515) BEYOND. See CA-2398-CP-8 for detail of the stairway in the distance - Hamilton Field, Amphitheater, North Oakland Drive near East Hospital Drive, Novato, Marin County, CA

  4. 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.

  5. Sixth Form Examining Methods.

    ERIC Educational Resources Information Center

    Schools Council, London (England).

    The methods of examining in the sixth form of secondary education in England and Wales is the basis for discussion by subject committees of the Schools Council. Special reference is made to internal examinations, oral assessments, teacher's assessments, the relaxing of the time limits for examination, and the use of aids during examinations. The…

  6. 49 CFR 109.9 - Transportation for examination and analysis.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 2 2013-10-01 2013-10-01 false Transportation for examination and analysis. 109.9... ORDERS, AND EMERGENCY RECALLS § 109.9 Transportation for examination and analysis. (a) An agent may direct a package to be transported to a facility for examination and analysis when the agent...

  7. FACILITY 846, SOUTHEAST END ON LEFT, WITH FACILITY 845 ON ...

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

    FACILITY 846, SOUTHEAST END ON LEFT, WITH FACILITY 845 ON RIGHT AND FACILITY 847 IN CENTER BACKGROUND, QUADRANGLE J, VIEW FACING NORTH. - Schofield Barracks Military Reservation, Quadrangles I & J Barracks Type, Between Wright-Smith & Capron Avenues near Williston Avenue, Wahiawa, Honolulu County, HI

  8. Spacelab Data Processing Facility

    NASA Technical Reports Server (NTRS)

    1983-01-01

    The Spacelab Data Processing Facility (SDPF) processes, monitors, and accounts for the payload data from Spacelab and other Shuttle missions and forwards relevant data to various user facilities worldwide. The SLDPF is divided into the Spacelab Input Processing System (SIPS) and the Spacelab Output Processing System (SOPS). The SIPS division demultiplexes, synchronizes, time tags, quality checks, accounts for the data, and formats the data onto tapes. The SOPS division further edits, blocks, formats, and records the data on tape for shipment to users. User experiments must conform to the Spacelab's onboard High Rate Multiplexer (HRM) format for maximum process ability. Audio, analog, instrumentation, high density, experiment data, input/output data, quality control and accounting, and experimental channel tapes along with a variety of spacelab ancillary tapes are provided to the user by SLDPF.

  9. Facilities evaluation report

    SciTech Connect

    Sloan, P.A.; Edinborough, C.R.

    1992-04-01

    The Buried Waste Integrated Demonstration (BWID) is a program of the Department of Energy (DOE) Office of Technology Development whose mission is to evaluate different new and existing technologies and determine how well they address DOE community waste remediation problems. Twenty-three Technical Task Plans (TTPs) have been identified to support this mission during FY-92; 10 of these have identified some support requirements when demonstrations take place. Section 1 of this report describes the tasks supported by BWID, determines if a technical demonstration is proposed, and if so, identifies the support requirements requested by the TTP Principal Investigators. Section 2 of this report is an evaluation identifying facility characteristics of existing Idaho National Engineering Laboratory (INEL) facilities that may be considered for use in BWID technology demonstration activities.

  10. RCRA Facility Information

    EPA Pesticide Factsheets

    This asset includes hazardous waste information, which is mostly contained in the Resource Conservation and Recovery Act Information (RCRAInfo) System, a national program management and inventory system addressing hazardous waste handlers. In general, all entities that generate, transport, treat, store, and dispose of hazardous waste are required to provide information about their activities to state environmental agencies. These agencies pass on that information to regional and national EPA offices. This regulation is governed by the Resource Conservation and Recovery Act (RCRA), as amended by the Hazardous and Solid Waste Amendments of 1984. RCRAInfo Search can be used to determine identification and location data for specific hazardous waste handlers and to find a wide range of information on treatment, storage, and disposal facilities regarding permit/closure status, compliance with Federal and State regulations, and cleanup activities. Categories of information in this asset include:-- Handlers-- Permit Information-- GIS information on facility location-- Financial Assurance-- Corrective Action-- Compliance Monitoring and Enforcement (CM&E)

  11. The ISOLDE facility

    NASA Astrophysics Data System (ADS)

    Catherall, R.; Andreazza, W.; Breitenfeldt, M.; Dorsival, A.; Focker, G. J.; Gharsa, T. P.; J, Giles T.; Grenard, J.-L.; Locci, F.; Martins, P.; Marzari, S.; Schipper, J.; Shornikov, A.; Stora, T.

    2017-09-01

    The ISOLDE facility has undergone numerous changes over the last 17 years driven by both the physics and technical community with a common goal to improve on beam variety, beam quality and safety. Improvements have been made in civil engineering and operational equipment while continuing developments aim to ensure operations following a potential increase in primary beam intensity and energy. This paper outlines the principal technical changes incurred at ISOLDE by building on a similar publication of the facility upgrades by Kugler (2000 Hyperfine Interact. 129 23-42). It also provides an insight into future perspectives through a brief summary issues addressed in the HIE-ISOLDE design study Catherall et al (2013 Nucl. Instrum. Methods Phys. Res. B 317 204-207).

  12. Space Station Furnace Facility

    SciTech Connect

    Cobb, S.D.; Lehoczky, S.L.

    1996-12-31

    The Space Station Furnace Facility (SSFF) is the modular, multi-user scientific instrumentation for conducting materials research in the reduced gravity ({approximately}10{sup {minus}6} g) environment of the International Space Station (ISS). The facility is divided into the Core System and two Instrument Racks (IRs). The Core System provides the common electrical and mechanical support equipment required to operate Experiment Modules (EMs). The EMs are investigator unique furnaces or apparatus designed to accomplish specific science investigations. Investigations are peer selected every two years from proposals submitted in response to National Aeronautics and Space Administration (NASA) Research Announcements. The SSFF Core systems are designed to accommodate an envelope of eight types of experiment modules. The first two modules to be developed for the first Instrument Rack include a High Temperature Gradient Furnace with Quench (HGFQ), and a Low Temperature Gradient Furnace (LGF). A new EM is planned to be developed every two years.

  13. Examination Involving Students as Peer Examiners

    ERIC Educational Resources Information Center

    Ljungman, Anders G.; Silen, Charlotte

    2008-01-01

    The main interest in this article is students' involvement in assessment as a part of growth towards self-directedness in learning. In order to enhance students' development of autonomy in learning, a project involving "older" students as peer examiners for "younger" students was designed and carried out. Students in the sixth semester in a…

  14. Microgravity Simulation Facility (MSF)

    NASA Technical Reports Server (NTRS)

    Richards, Stephanie E. (Compiler); Levine, Howard G.; Zhang, Ye

    2016-01-01

    The Microgravity Simulator Facility (MSF) at Kennedy Space Center (KSC) was established to support visiting scientists for short duration studies utilizing a variety of microgravity simulator devices that negate the directional influence of the "g" vector (providing simulated conditions of micro or partial gravity). KSC gravity simulators can be accommodated within controlled environment chambers allowing investigators to customize and monitor environmental conditions such as temperature, humidity, CO2, and light exposure.

  15. TACS Central Control Facility.

    DTIC Science & Technology

    1981-02-12

    Central Control Facility 6 3. System Management Data Flow 7 B. Hardware Operating Environment 9 1. Computer 9 2. TACS Interfaces 9 3. Other Central...TERMINATION TIMING 131 Appendix C SYSTEM MANAGEMENT DATA FORMATS 135 Appendix D FIVE- AND NINE-SLOT SYSTEM IMPLEMENTATION DIFFERENCES 147 Appendix E...control burst management ) 26 2-7 Call Progress Messages 29 2-8 Flowchart of Assignment/Blockage Decision Process for All-Member Net Requests 30 2-9

  16. Facility Response Plan

    DTIC Science & Technology

    1992-10-06

    otherwise described in specialized publications. Identifying and delineating these ESAU will require professional judgment. Categories of...consistent with these broader plans. Also, ensure that the ESAU identified in the ACP are considered in the FRP. Place emphasis on ensuring that the following...section 4.1 requires the identification of Environmentally Sensitive Areas (ESAs). If ESAU are located near the facility, more stringent protective

  17. The Astrometric Telescope Facility

    NASA Technical Reports Server (NTRS)

    Black, David; Dyer, John; Nishioka, Kenji; Scargle, Jeffrey; Sobeck, Charlie

    1991-01-01

    The evolution of the Astrometric Telescope Facility (ATF) proposed for use on NASA's Space Station is traced and its design characteristics are presented. With a focal plane scale of 12.7 arcsec/mm, the strawman design has a field size of 10 sq arcmin and a limiting visual magnitude fainter than 16. Output from an observation includes the X and Y coordinates of each star and its relative brightness.

  18. ORNL calibrations facility

    SciTech Connect

    Berger, C.D.; Gupton, E.D.; Lane, B.H.; Miller, J.H.; Nichols, S.W.

    1982-08-01

    The ORNL Calibrations Facility is operated by the Instrumentation Group of the Industrial Safety and Applied Health Physics Division. Its primary purpose is to maintain radiation calibration standards for calibration of ORNL health physics instruments and personnel dosimeters. This report includes a discussion of the radioactive sources and ancillary equipment in use and a step-by-step procedure for calibration of those survey instruments and personnel dosimeters in routine use at ORNL.

  19. UNISOR Nuclear Orientation Facility

    SciTech Connect

    Girit, I.C.

    1988-01-01

    The combination of an on-line isotope separator and a dilution refrigerator has increased the applicability of the nuclear orientation technique to a wide range of nuclei, especially those very far from stability. The UNISOR Nuclear Orientation Facility (UNISOR/NOF) is among the two (the other being NICOLE at CERN) that have recently become operational. The following is an overall view of the UNISOR system and recent results. 24 refs., 3 figs.

  20. A Multiprocessor Emulation Facility.

    DTIC Science & Technology

    1983-09-01

    make the facility usable. We considered three classes of machines: 1. Commercially available Motorola M68000 -based single board computers. 2. Our own...One of the most interesting multiprocessor systems built to date is the BBN Butterfly machine [17]. It currently consists of 10 M68000 boards connected...by a circuit switched network of butterfly (ie., FFT or shuffle exchange) topology. The machine can be extended to several hundred M68000s because the

  1. Proton beam therapy facility

    SciTech Connect

    Not Available

    1984-10-09

    It is proposed to build a regional outpatient medical clinic at the Fermi National Accelerator Laboratory (Fermilab), Batavia, Illinois, to exploit the unique therapeutic characteristics of high energy proton beams. The Fermilab location for a proton therapy facility (PTF) is being chosen for reasons ranging from lower total construction and operating costs and the availability of sophisticated technical support to a location with good access to patients from the Chicago area and from the entire nation. 9 refs., 4 figs., 26 tabs.

  2. 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)

  3. Optimal Facility-Location

    PubMed Central

    Goldman, A. J.

    2006-01-01

    Dr. Christoph Witzgall, the honoree of this Symposium, can count among his many contributions to applied mathematics and mathematical operations research a body of widely-recognized work on the optimal location of facilities. The present paper offers to non-specialists a sketch of that field and its evolution, with emphasis on areas most closely related to Witzgall’s research at NBS/NIST. PMID:27274920

  4. Future Facilities Summary

    SciTech Connect

    Albert De Roeck, Rolf Ent

    2009-10-01

    For the session on future facilities at DIS09 discussions were organized on DIS related measurements that can be expected in the near and medium –or perhaps far– future, including plans from JLab, CERN and FNAL fixed target experiments, possible measurements and detector upgrades at RHIC, as well as the plans for possible future electron proton/ion colliders such as the EIC and the LHeC project.

  5. Engineering test facility

    SciTech Connect

    Steiner, D.; Becraft, W.R.; Sager, P.H.

    1981-01-01

    The vehicle by which the fusion program would move into the engineering testing phase of fusion power development is designated the Engineering Test Facility (ETF). The ETF would provide a test-bed for reactor components in the fusion environment. In order to initiate preliminary planning for the ETF decision, the Office of Fusion Energy established the ETF Design Center activity to prepare the design of the ETF. This paper described the design status of the ETF.

  6. Test Track Facilities

    DTIC Science & Technology

    1979-12-01

    the surface, together with the effect of flying flintstones results in severe wear to the tyres , brake pipes and all other fittings found underneath a...as engine ignition systems and toe evaluation of waterproof clothing. *1 TechnicaZ Specifi’cation Range of rainfall: 10 - 6705.6 mm per hour (.4 -264...The building also contains the following test facilities. A 15 m square flat floor used for vehicle measurement accuracy checks, tyre deflections, and

  7. Facility decontamination technology workshop

    SciTech Connect

    1980-10-01

    Purpose of the meeting was to provide a record of experience at nuclear facilities, other than TMI-2, of events and incidents which have required decontamination and dose reduction activities, and to furnish GPU and others involved in the TMI-2 cleanup with the results of that decontamination and dose reduction technology. Separate abstracts were prepared for 24 of the 25 papers; the remaining paper had been previously abstracted. (DLC)

  8. Hot Hydrogen Test Facility

    SciTech Connect

    W. David Swank

    2007-02-01

    The core in a nuclear thermal rocket will operate at high temperatures and in hydrogen. One of the important parameters in evaluating the performance of a nuclear thermal rocket is specific impulse, ISp. This quantity is proportional to the square root of the propellant’s absolute temperature and inversely proportional to square root of its molecular weight. Therefore, high temperature hydrogen is a favored propellant of nuclear thermal rocket designers. Previous work has shown that one of the life-limiting phenomena for thermal rocket nuclear cores is mass loss of fuel to flowing hydrogen at high temperatures. The hot hydrogen test facility located at the Idaho National Lab (INL) is designed to test suitability of different core materials in 2500°C hydrogen flowing at 1500 liters per minute. The facility is intended to test non-uranium containing materials and therefore is particularly suited for testing potential cladding and coating materials. In this first installment the facility is described. Automated Data acquisition, flow and temperature control, vessel compatibility with various core geometries and overall capabilities are discussed.

  9. Hot Hydrogen Test Facility

    SciTech Connect

    Swank, W. David; Carmack, Jon; Werner, James E.; Pink, Robert J.; Haggard, DeLon C.; Johnson, Ryan

    2007-01-30

    The core in a nuclear thermal rocket will operate at high temperatures and in hydrogen. One of the important parameters in evaluating the performance of a nuclear thermal rocket is specific impulse, ISP. This quantity is proportional to the square root of the propellant's absolute temperature and inversely proportional to square root of its molecular weight. Therefore, high temperature hydrogen is a favored propellant of nuclear thermal rocket designers. Previous work has shown that one of the life-limiting phenomena for thermal rocket nuclear cores is mass loss of fuel to flowing hydrogen at high temperatures. The hot hydrogen test facility located at the Idaho National Lab (INL) is designed to test suitability of different core materials in 2500 deg. C hydrogen flowing at 1500 liters per minute. The facility is intended to test low activity uranium containing materials but is also suited for testing cladding and coating materials. In this first installment the facility is described. Automated data acquisition, flow and temperature control, vessel compatibility with various core geometries and overall capabilities are discussed.

  10. The National Ignition Facility

    SciTech Connect

    Miller, G H; Moses, E I; Wuest, C R

    2004-02-06

    The National Ignition Facility (NIF) at Lawrence Livermore National Laboratory is a stadium-sized facility containing a 192-beam, 1.8-Megajoule, 500-Terawatt, ultraviolet laser system together with a 10-meter-diameter target chamber and room for 100 diagnostics. NIF is the world's largest and most energetic laser experimental system, providing a scientific center to study inertial confinement fusion and matter at extreme energy densities and pressures. NIF's energetic laser beams will compress fusion targets to conditions required for thermonuclear burn, liberating more energy than required to initiate the fusion reactions. Other NIF experiments will study physical processes at temperatures approaching 10{sup 8} K and 10{sup 11} bar; conditions that exist naturally only in the interior of stars and planets. NIF has completed the first phases of its laser commissioning program. The first four beams of NIF have generated 106 kilojoules in 23-ns pulses of infrared light and over 16 kJ in 3.5-ns pulses at the third harmonic (351 nm). NIF's target experimental systems are being commissioned and experiments have begun. This paper provides a detailed look the NIF laser systems, laser and optical performance, and results from recent laser commissioning shots. We follow this with a discussion of NIF's high-energy-density and inertial fusion experimental capabilities, the first experiments on NIF, and plans for future capabilities of this unique facility.

  11. The National Ignition Facility

    SciTech Connect

    Miller, G H; Moses, E I; Wuest, C R

    2004-06-03

    The National Ignition Facility (NIF) at Lawrence Livermore National Laboratory is a stadium-sized facility that, when completed in 2008, will contain a 192-beam, 1.8- Megajoule, 500-Terawatt, ultraviolet laser system together with a 10-meter-diameter target chamber and room for 100 diagnostics. NIF is the world's largest and most energetic laser experimental system and will provide a scientific center to study inertial confinement fusion and matter at extreme energy densities and pressures. NIF's energetic laser beams will compress fusion targets to conditions required for thermonuclear burn, liberating more energy than required to initiate the fusion reactions. Other NIF experiments will study physical processes at temperatures approaching 10{sup 8} K and 10{sup 11} bar; conditions that exist naturally only in the interior of stars and planets. NIF has completed the first phases of its laser commissioning program. The first four beams of NIF have generated 106 kilojoules in 23-ns pulses of infrared light and over 16 kJ in 3.5- ns pulses at the third harmonic (351 nm). NIF's target experimental systems are being commissioned and experiments have begun. This paper provides a detailed look the NIF laser systems, laser and optical performance, and results from recent laser commissioning shots. We follow this with a discussion of NIF's high-energy-density and inertial fusion experimental capabilities, the first experiments on NIF, and plans for future capabilities of this unique facility.

  12. Medical Image Analysis Facility

    NASA Technical Reports Server (NTRS)

    1978-01-01

    To improve the quality of photos sent to Earth by unmanned spacecraft. NASA's Jet Propulsion Laboratory (JPL) developed a computerized image enhancement process that brings out detail not visible in the basic photo. JPL is now applying this technology to biomedical research in its Medical lrnage Analysis Facility, which employs computer enhancement techniques to analyze x-ray films of internal organs, such as the heart and lung. A major objective is study of the effects of I stress on persons with heart disease. In animal tests, computerized image processing is being used to study coronary artery lesions and the degree to which they reduce arterial blood flow when stress is applied. The photos illustrate the enhancement process. The upper picture is an x-ray photo in which the artery (dotted line) is barely discernible; in the post-enhancement photo at right, the whole artery and the lesions along its wall are clearly visible. The Medical lrnage Analysis Facility offers a faster means of studying the effects of complex coronary lesions in humans, and the research now being conducted on animals is expected to have important application to diagnosis and treatment of human coronary disease. Other uses of the facility's image processing capability include analysis of muscle biopsy and pap smear specimens, and study of the microscopic structure of fibroprotein in the human lung. Working with JPL on experiments are NASA's Ames Research Center, the University of Southern California School of Medicine, and Rancho Los Amigos Hospital, Downey, California.

  13. Robot Serviced Space Facility

    NASA Technical Reports Server (NTRS)

    Purves, Lloyd R. (Inventor)

    1992-01-01

    A robot serviced space facility includes multiple modules which are identical in physical structure, but selectively differing in function. and purpose. Each module includes multiple like attachment points which are identically placed on each module so as to permit interconnection with immediately adjacent modules. Connection is made through like outwardly extending flange assemblies having identical male and female configurations for interconnecting to and locking to a complementary side of another flange. Multiple rows of interconnected modules permit force, fluid, data and power transfer to be accomplished by redundant circuit paths. Redundant modules of critical subsystems are included. Redundancy of modules and of interconnections results in a space complex with any module being removable upon demand, either for module replacement or facility reconfiguration. without eliminating any vital functions of the complex. Module replacement and facility assembly or reconfiguration are accomplished by a computer controlled articulated walker type robotic manipulator arm assembly having two identical end-effectors in the form of male configurations which are identical to those on module flanges and which interconnect to female configurations on other flanges. The robotic arm assembly moves along a connected set or modules by successively disconnecting, moving and reconnecting alternate ends of itself to a succession of flanges in a walking type maneuver. To transport a module, the robot keeps the transported module attached to one of its end-effectors and uses another flange male configuration of the attached module as a substitute end-effector during walking.

  14. Skilled nursing or rehabilitation facilities

    MedlinePlus

    ... skilled nursing or rehabilitation facility. Who Needs to go to a Skilled Nursing or Rehabilitation Facility? Your ... ones can manage at home. Before you can go home from the hospital, you should be able ...

  15. Building a Computable Facility Model

    DTIC Science & Technology

    2002-10-01

    Building Composer; facility design; facility management; Fort Future; decision support tools; installation design; integrated software; simulation ... modeling 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF ABSTRACT Same as Report (SAR) 18. NUMBER OF PAGES 4 19. NAME OF RESPONSIBLE PERSON Wolfe

  16. NEP facilities (LeRC)

    NASA Technical Reports Server (NTRS)

    Vetrone, Robert H.

    1993-01-01

    The topics are presented in viewgraph form and include the following: the Electric Propulsion Research Building (no. 16) the Electric Power Laboratory (BLDG. 301); the Tank 6 Vacuum Facility; and test facilities for electric propulsion and LeRC.

  17. Rod examination gauge

    SciTech Connect

    Bacvinskas, W.S.; Bayer, J.E.; Davis, W.W.; Fodor, G.; Kikta, T.J.; Matchett, R.L.; Nilsen, R.J.; Wilczynski, R.

    1991-12-31

    The present invention is directed to a semi-automatic rod examination gauge for performing a large number of exacting measurements on radioactive fuel rods. The rod examination gauge performs various measurements underwater with remote controlled machinery of high reliability. The rod examination gauge includes instruments and a closed circuit television camera for measuring fuel rod length, free hanging bow measurement, diameter measurement, oxide thickness measurement, cladding defect examination, rod ovality measurement, wear mark depth and volume measurement, as well as visual examination. A control system is provided including a programmable logic controller and a computer for providing a programmed sequence of operations for the rod examination and collection of data.

  18. Indoor Lighting Facilities

    NASA Astrophysics Data System (ADS)

    Matsushima, Koji; Saito, Yoshinori; Ichikawa, Shigenori; Kawauchi, Takao; Tanaka, Tsuneo; Hirano, Rika; Tazuke, Fuyuki

    According to the statistics by the Ministry of Land, Infrastructure and Transport, the total floor space of all building construction started was 188.87 million m2 (1.5% increase y/y), marking the fourth straight year of increase. Many large-scale buildings under construction in central Tokyo become fully occupied by tenants before completion. As for office buildings, it is required to develop comfortable and functional office spaces as working styles are becoming more and more diversified, and lighting is also an element of such functionalities. The total floor space of construction started for exhibition pavilions, multipurpose halls, conference halls and religious architectures decreased 11.1% against the previous year. This marked a decline for 10 consecutive years and the downward trend continues. In exhibition pavilions, the light radiation is measured and adjusted throughout the year so as not to damage the artworks by lighting. Hospitals, while providing higher quality medical services and enhancing the dwelling environment of patients, are expected to meet various restrictions and requirements, including the respect for privacy. Meanwhile, lighting designs for school classrooms tend to be homogeneous, yet new ideas are being promoted to strike a balance between the economical and functional aspects. The severe economic environment continues to be hampering the growth of theaters and halls in both the private and public sectors. Contrary to the downsizing trend of such facilities, additional installations of lighting equipment were conspicuous, and the adoption of high efficacy lighting appliances and intelligent function control circuits are becoming popular. In the category of stores/commercial facilities, the construction of complex facilities is a continuing trend. Indirect lighting, high luminance discharge lamps with excellent color rendition and LEDs are being effectively used in these facilities, together with the introduction of lighting designs

  19. A3 Altitude Test Facility

    NASA Technical Reports Server (NTRS)

    Dulreix, Lionel J.

    2009-01-01

    This slide presentation shows drawings, diagrams and photographs of the A3 Altitude Test Facility. It includes a review of the A3 Facility requirements, and drawings of the various sections of the facility including Engine Deck and Superstructure, Test Cell and Thrust Takeout, Structure and Altitude Support Systems, Chemical Steam generators, and the subscale diffuser. There are also pictures of the construction site, and the facility under construction. A Diagram of the A3 Steam system schematic is also shown

  20. The Francium facility at TRIUMF

    NASA Astrophysics Data System (ADS)

    Aubin, S.; Behr, J. A.; Chen, G.; Collister, R.; Flambaum, V. V.; Gomez, E.; Gwinner, G.; Jackson, K. P.; Melconian, D.; Orozco, L. A.; Pearson, M. R.; Ruiz, M. C.; Sheng, D.; Shin, Y. H.; Sprouse, G. D.; Tandecki, M.; Zhang, J.; Zhao, Y.

    2013-04-01

    We present the current status of the Francium Trapping Facility at ISAC at TRIUMF. The facility will enable future experiments on the weak interaction with measurements of atomic parity non-conservation laser-cooled samples of artificially produced francium. These experiments require a precisely controlled environment, which the facility is designed to provide. The facility has been constructed and is being prepared for a series of commissioning runs.

  1. PUREX facility preclosure work plan

    SciTech Connect

    Engelmann, R.H.

    1997-04-24

    This preclosure work plan presents a description of the PUREX Facility, the history of the waste managed, and addresses transition phase activities that position the PUREX Facility into a safe and environmentally secure configuration. For purposes of this documentation, the PUREX Facility does not include the PUREX Storage Tunnels (DOE/RL-90/24). Information concerning solid waste management units is discussed in the Hanford Facility Dangerous Waste Permit Application, General Information Portion (DOE/RL-91-28, Appendix 2D).

  2. NONDESTRUCTIVE EXAMINATION OF FUEL PLATES FOR THE RERTR FUEL DEVELOPMENT EXPERIMENTS

    SciTech Connect

    N.E. Woolstenhulme; S.C. Taylor; G.A. Moore; D.M. Sterbentz

    2012-09-01

    Nuclear fuel is the core component of reactors that is used to produce the neutron flux required for irradiation research purposes as well as commercial power generation. The development of nuclear fuels with low enrichments of uranium is a major endeavor of the RERTR program. In the development of these fuels, the RERTR program uses nondestructive examination (NDE) techniques for the purpose of determining the properties of nuclear fuel plate experiments without imparting damage or altering the fuel specimens before they are irradiated in a reactor. The vast range of properties and information about the fuel plates that can be characterized using NDE makes them highly useful for quality assurance and for analyses used in modeling the behavior of the fuel while undergoing irradiation. NDE is also particularly useful for creating a control group for post-irradiation examination comparison. The two major categories of NDE discussed in this paper are X-ray radiography and ultrasonic testing (UT) inspection/evaluation. The radiographic scans are used for the characterization of fuel meat density and homogeneity as well as the determination of fuel location within the cladding. The UT scans are able to characterize indications such as voids, delaminations, inclusions, and other abnormalities in the fuel plates which are generally referred to as debonds as well as to determine the thickness of the cladding using ultrasonic acoustic microscopy methods. Additionally, the UT techniques are now also being applied to in-canal interim examination of fuel experiments undergoing irradiation and the mapping of the fuel plate surface profile to determine fuel swelling. The methods used to carry out these NDE techniques, as well as how they operate and function, are described along with a description of which properties are characterized.

  3. Early Childhood Education Facilities Planner.

    ERIC Educational Resources Information Center

    North Carolina State Dept. of Public Instruction, Raleigh. Div. of School Support.

    This publication, a supplement to the "North Carolina Public School Facilities Guidelines," is intended as a resource to assist design professionals in planning facilities that meet the evolving needs of public schools in North Carolina. The publication specifically describes early childhood education programs and the facilities that…

  4. Education Funding for Residential Facilities.

    ERIC Educational Resources Information Center

    Ohio State Legislative Office of Education Oversight, Columbus.

    About 167 residential facilities in Ohio serve approximately 7,000 youth on any given day. Youth are placed in residential facilities because they have committed a crime or have behavioral problems. An "education provider" operates an on-grounds school in most facilities. Because of ongoing concerns about education funding for youth in…

  5. Industrial Arts Facility Planning Guide.

    ERIC Educational Resources Information Center

    Hughes, Thomas A., Jr.; And Others

    This guidebook presents facility guidelines to aid the school planner in determining appropriate facilities for a model curriculum. The first of four major sections, The Intent of Industrial Arts, discusses the mission and goals, instructional objectives, function of industrial arts, and the model curriculum. Section 2 focuses on facilities for…

  6. DTRA National Ignition Facility (NIF)

    DTIC Science & Technology

    2009-01-16

    DTRA National Ignition Facility ( NIF ) ___________________________________ JSR-08- 800 September 29...4. TITLE AND SUBTITLE 5a. CONTRACT NUMBER DTRA National Ignition Facility ( NIF ) 5b. GRANT NUMBER 5c...only). 13. SUPPLEMENTARY NOTES 14. ABSTRACT JASON was asked to address the utility of the National Ignition Facility ( NIF ) to the Defense Threat

  7. Directory of Environmental Education Facilities.

    ERIC Educational Resources Information Center

    National Audubon Society, New York, NY.

    The location and character of environmental education facilities and sanctuaries in the United States and Canada are outlined in a directory which is designed to help guide anyone interested in visiting the facilities or learning about preservation and the conservation of natural resources. A description of each facility includes its location by…

  8. School Nutrition Facility Planning Guide.

    ERIC Educational Resources Information Center

    Pannell, Dorothy VanEgmond

    This publication is designed to help superintendents, local facilities coordinators, and food-service directors in planning the remodeling of an outdated food-service facility or the building of a new one. The introduction describes the roles of the local facility coordinator, the local child-nutrition director, the architect, the food-service…

  9. Workforce Development Education Facilities Planner.

    ERIC Educational Resources Information Center

    North Carolina State Dept. of Public Instruction, Raleigh.

    This publication, a supplement to the "North Carolina Public Schools Facilities Guidelines," describes work force development education programs and facilities. It is intended as a resource that can assist design professionals in planning facilities that meet the evolving needs of public schools in the state. The first part of the guide…

  10. Facilities for Agricultural Education Curriculums.

    ERIC Educational Resources Information Center

    South Carolina State Dept. of Education, Columbia. Agricultural Education Section.

    Expansion of the vocational agriculture program to include education for off-farm agricultural occupations has placed increasing demands on existing facilities for agricultural programs. The facility requirements of the new curriculums are often not met by the existing facilities. Vocational agriculture teachers, state supervisory staff members,…

  11. Physical Recreation Facilities. A Report.

    ERIC Educational Resources Information Center

    Educational Facilities Labs., Inc., New York, NY.

    New goals in physical education are leading instructors to seek new kinds of athletic facilities. School administrators are in the process of rethinking the classical facilities, i.e., the box-shaped gymnasium -- facilities designed without sensitivity to the students' desire to participate in the games they can continue to play after graduation.…

  12. Examine Your Skin

    MedlinePlus Videos and Cool Tools

    ... Store In Memory Melanoma Info Melanoma Facts Melanoma Prevention Sunscreen Suggestions Examine Your Skin Newly Diagnosed? Understanding ... video. UPDATED: November 23, 2016 Melanoma Facts Melanoma Prevention Sunscreen Suggestions Examine Your Skin Newly Diagnosed? Understanding ...

  13. The preparticipation physical examination.

    PubMed

    Pedraza, Jaime; Jardeleza, Julie Ann

    2013-12-01

    This article reviews the components of the preparticipation physical examination. It looks at some of the key elements of the history and the physical examination that help determine whether an athlete can participate in an organized sport.

  14. Physics 300 Provincial Examination.

    ERIC Educational Resources Information Center

    Manitoba Dept. of Education and Training, Winnipeg.

    This document consists of the physics 300 provincial examination (English version), a separate "provincial summary report" on the results of giving the test, and a separate French language version of the examination. This physics examination contains a 53-item multiple choice section and an 12 item free response section. Subsections of…

  15. Equating Practical Examinations.

    ERIC Educational Resources Information Center

    Lunz, Mary E.; And Others

    This paper describes and illustrates a method for equating examinations with multiple facets (i.e., items, examinees, judges, tasks, and rating scales). The data are from the practical section of two histotechnology certification examinations. The first practical examination involved 210 examinees, 14 judges, 15 slides, 3 tasks, and 2 rating…

  16. Physics 300 Provincial Examination.

    ERIC Educational Resources Information Center

    Manitoba Dept. of Education and Training, Winnipeg.

    This document consists of the physics 300 provincial examination (English version), a separate "provincial summary report" on the results of giving the test, and a separate French language version of the examination. This physics examination contains a 53-item multiple choice section and an 12 item free response section. Subsections of…

  17. A Generalized Management Information System for Computer Facilities at Educational Institutions.

    ERIC Educational Resources Information Center

    Bowman, Patrick Awalt

    The problem of managing computer facilities at educational institutions is examined. User categories are defined, and the interrelations between user requirements and the goals/objectives of the facility are discussed. Enumerations of the factors that influence computer facility operations is also accomplished. In addition, management information…

  18. The Feasibility of Replacing Existing Central Computers with A Single Computer Facility.

    ERIC Educational Resources Information Center

    Richey, R. Wayne

    1979-01-01

    The feasibility of replacing existing central processing units with a single computer facility is discussed. An analysis of the computing facilities for the Iowa state universities is presented and supports the retention of decentralized facilities. Efficiency, costs, and operating considerations are examined. (SF)

  19. USEPA Facility Registry Service Datasets

    EPA Pesticide Factsheets

    This collection contains datasets relating to location and facility identification information from EPA's Facility Registry Service (FRS). Using vigorous verification and data management procedures, FRS integrates facility data from EPA's national program systems, other federal agencies, and State and tribal master facility records and provides EPA with a centrally managed, single source of comprehensive and authoritative information on facilities. This collection provides access to a variety of live data services, APIs and downloadable FRS data, many of which are also enumerated here: https://www.epa.gov/enviro/frs-data-resources .

  20. Microbiology facilities aboard Space Station Freedom (SSF)

    NASA Technical Reports Server (NTRS)

    Cioletti, L. A.; Mishra, S. K.; Richard, Elizabeth E.; Taylor, R.

    1990-01-01

    A comprehensive microbiological facility is being designed for use on board Space Station Freedom (SSF). Its purpose will be to conduct microbial surveillance of the SSF environment and to examine clinical specimens. Air, water, and internal surfaces will be periodically monitored to satisfy requirements for a safe environment. Crew health will remain a principle objective for every mission. This paper will review the Microbiology Subsystem capabilities planned for SSF application.

  1. Regional analysis of energy facility siting

    SciTech Connect

    Lipfert, F W; Meier, P M; Kleinman, L I

    1980-01-01

    This paper has examined some of the regional environmental parameters of energy facility siting, with emphasis on air quality impacts. An example of a siting optimization study was presented, and it was shown how difficult it presently is to specify an environmental objective function that is universally applicable. The importance of regional background effects was discussed, and long-range transport models were used to analyze the relative importance of local and long-range impacts.

  2. Deodorization of laboratory animal facilities by ozone.

    PubMed

    Pan, T M; Shimoda, K; Cai, Y; Kiuchi, Y; Nakama, K; Akimoto, T; Nagashima, Y; Kai, M; Ohira, M; Saegusa, J

    1995-07-01

    Deodorizing effect of ozone was investigated comparing two types of compact ozonizing apparatus made on an experimental basis. The concentrations of ammonia and trimethylamine were examined as an indicator for deodorizing effect of ozone in animal rooms of rats and guinea pigs at laboratory animal facilities of three different universities. Both of the ozonizing apparatus were able to remove ammonia and trimethylamine in animal rooms, with no significant difference in the performance of the two apparatus.

  3. Facilities removal working group

    SciTech Connect

    1997-03-01

    This working group`s first objective is to identify major economic, technical, and regulatory constraints on operator practices and decisions relevant to offshore facilities removal. Then, the group will try to make recommendations as to regulatory and policy adjustments, additional research, or process improvements and/or technological advances, that may be needed to improve the efficiency and effectiveness of the removal process. The working group will focus primarily on issues dealing with Gulf of Mexico platform abandonments. In order to make the working group sessions as productive as possible, the Facilities Removal Working Group will focus on three topics that address a majority of the concerns and/or constraints relevant to facilities removal. The three areas are: (1) Explosive Severing and its Impact on Marine Life, (2) Pile and Conductor Severing, and (3) Deep Water Abandonments This paper will outline the current state of practice in the offshore industry, identifying current regulations and specific issues encountered when addressing each of the three main topics above. The intent of the paper is to highlight potential issues for panel discussion, not to provide a detailed review of all data relevant to the topic. Before each panel discussion, key speakers will review data and information to facilitate development and discussion of the main issues of each topic. Please refer to the attached agenda for the workshop format, key speakers, presentation topics, and panel participants. The goal of the panel discussions is to identify key issues for each of the three topics above. The working group will also make recommendations on how to proceed on these key issues.

  4. Fan Noise Test Facility

    NASA Image and Video Library

    1969-01-21

    The Fan Noise Test Facility built at the Lewis Research Center to obtain far-field noise data for the National Aeronautics and Space Administration (NASA) and General Electric Quiet Engine Program. The engine incorporated existing noise reduction methods into an engine of similar power to those that propelled the Boeing 707 or McDonnell-Douglas DC-8 airliner. The new the low-bypass ratio turbofan engines of the 1960s were inherently quieter than their turbojet counterparts, researchers had a better grasp of the noise generation problem, and new acoustic technologies had emerged. Lewis contracted General Electric in 1969 to build and aerodynamically test three experimental engines with 72-inch diameter fans. The engines were then brought to Lewis and tested with an acoustically treated nacelle. This Fan Noise Test Facility was built off of the 10- by 10-Foot Supersonic Wind Tunnel’s Main Compressor and Drive Building. Lewis researchers were able to isolate the fan’s noise during these initial tests by removing the core of the engine. The Lewis test rig drove engines to takeoff tip speeds of 1160 feet per second. The facility was later used to test a series of full-scale model fans and fan noise suppressors to be used with the quiet engine. NASA researchers predicted low-speed single-stage fans without inlet guide vanes and with large spacing between rotors and stators would be quieter. General Electric modified a TF39 turbofan engine by removing the the outer protion of the fan and spacing the blade rows of the inner portion. The tests revealed that the untreated version of the engine generated less noise than was anticipated, and the acoustically treated nacelle substantially reduced engine noise.

  5. Large coil test facility

    SciTech Connect

    Nelms, L.W.; Thompson, P.B.

    1980-01-01

    Final design of the facility is nearing completion, and 20% of the construction has been accomplished. A large vacuum chamber, houses the test assembly which is coupled to appropriate cryogenic, electrical, instrumentation, diagnostc systems. Adequate assembly/disassembly areas, shop space, test control center, offices, and test support laboratories are located in the same building. Assembly and installation operations are accomplished with an overhead crane. The major subsystems are the vacuum system, the test stand assembly, the cryogenic system, the experimental electric power system, the instrumentation and control system, and the data aquisition system.

  6. Constellation Training Facility Support

    NASA Technical Reports Server (NTRS)

    Flores, Jose M.

    2008-01-01

    The National Aeronautics and Space Administration is developing the next set of vehicles that will take men back to the moon under the Constellation Program. The Constellation Training Facility (CxTF) is a project in development that will be used to train astronauts, instructors, and flight controllers on the operation of Constellation Program vehicles. It will also be used for procedure verification and validation of flight software and console tools. The CxTF will have simulations for the Crew Exploration Vehicle (CEV), Crew Module (CM), CEV Service Module (SM), Launch Abort System (LAS), Spacecraft Adapter (SA), Crew Launch Vehicle (CLV), Pressurized Cargo Variant CM, Pressurized Cargo Variant SM, Cargo Launch Vehicle, Earth Departure Stage (EDS), and the Lunar Surface Access Module (LSAM). The Facility will consist of part-task and full-task trainers, each with a specific set of mission training capabilities. Part task trainers will be used for focused training on a single vehicle system or set of related systems. Full task trainers will be used for training on complete vehicles and all of its subsystems. Support was provided in both software development and project planning areas of the CxTF project. Simulation software was developed for the hydraulic system of the Thrust Vector Control (TVC) of the ARES I launch vehicle. The TVC system is in charge of the actuation of the nozzle gimbals for navigation control of the upper stage of the ARES I rocket. Also, software was developed using C standards to send and receive data to and from hand controllers to be used in CxTF cockpit simulations. The hand controllers provided movement in all six rotational and translational axes. Under Project Planning & Control, support was provided to the development and maintenance of integrated schedules for both the Constellation Training Facility and Missions Operations Facilities Division. These schedules maintain communication between projects in different levels. The Cx

  7. The LERIX User Facility

    SciTech Connect

    Seidler, G.T.; Fister, T.T.; Cross, J.O.; Nagle, K.P.

    2007-01-18

    We describe the lower energy resolution inelastic x-ray scattering (LERIX) spectrometer, located at sector 20 PNC-XOR of the Advanced Photon Source. This instrument, which is now available to general users, is the first user facility optimized for high throughput measurements of momentum transfer dependent nonresonant inelastic x-ray scattering (NRIXS) from the core shell electrons of relatively light elements or the less-tightly bound electrons of heavier elements. By means of example, we present new NRIXS measurements of the near-edge structure for the L-edges of Al and the K-edge in Si.

  8. National Transonic Facility status

    NASA Technical Reports Server (NTRS)

    Mckinney, L. W.; Bruce, W. E., Jr.; Gloss, B. B.

    1989-01-01

    The National Transonic Facility (NTF) was operational in a combined checkout and test mode for about 3 years. During this time there were many challenges associated with movement of mechanical components, operation of instrumentation systems, and drying of insulation in the cryogenic environment. Most of these challenges were met to date along with completion of a basic flow calibration and aerodynamic tests of a number of configurations. Some of the major challenges resulting from cryogenic environment are reviewed with regard to hardware systems and data quality. Reynolds number effects on several configurations are also discussed.

  9. Thermal Simulation Facilities Handbook.

    DTIC Science & Technology

    1983-02-01

    DOE tests is not expected. 4.4.3 Costs The cost of a test at the CRTF solar furnace will be based on the time of the manpower, materials, and utilities ...fires, JP-4 fuel fires, and con- centrated solar radiation. The facility has several different types of sources for thermal radiant energy . The two... optical axis. Normally the solar image can be stablilzed to within *0.1 inch (25 mm) of the optical axis. Winds in excess of 15 miles per hour (7 cm/sec

  10. 310 Facility chemical specifications

    SciTech Connect

    Hagerty, K.J.

    1997-05-21

    The 300 area Treated Effluent Disposal Facility (TEDF) was designed and built to treat the waste water from the 300 area process sewer system. Several treatment technologies are employed to remove the trace quantities of contaminants in the stream, including iron coprecipitation, clarification, filtration, ion exchange, and ultra violet light/hydrogen peroxide oxidation of organics. The chemicals that will be utilized in the treatment process are hydrogen peroxide, sulfuric acid, sodium hydroxide, and ferric chloride. This document annotates the required chemical characteristics of TEDF bulk chemicals as well as the criteria that were used to establish these criteria. The chemical specifications in appendix B are generated from this information.

  11. The assess facility descriptor module

    SciTech Connect

    Jordan, S.E.; Winblad, A.; Key, B.; Walker, S.; Renis, T.; Saleh, R.

    1989-01-01

    The Facility Descriptor (Facility) module is part of the Analytic System and Software for Evaluating Safeguards and Security (ASSESS). Facility is the foundational software application in the ASSESS system for modelling a nuclear facility's safeguards and security system to determine the effectiveness against theft of special nuclear material. The Facility module provides the tools for an analyst to define a complete description of a facility's physical protection system which can then be used by other ASSESS software modules to determine vulnerability to a spectrum of insider and outsider threats. The analyst can enter a comprehensive description of the protection system layout including all secured areas, target locations, and detailed safeguards specifications. An extensive safeguard component catalog provides the reference data for calculating delay and detection performance. Multiple target locations within the same physical area may be specified, and the facility may be defined for two different operational states such as dayshift and nightshift. 6 refs., 5 figs.

  12. Not in whose backyard Minority population concentrations and noxious facility sites

    SciTech Connect

    Nieves, L.A.

    1992-01-01

    The NIMBY (not in may backyard) syndrome has become the nemesis of facility siting efforts in the USA. Given people's reluctance to live near noxious facilities, in whose backyard are such facilities located This study employs US county-level data to examine relative concentrations of minorities living near noxious facilities. Facility types analyzed include electric generating plants, manufacturing plants, Superfund sites, and radioactive waste disposal sites. While this study does not address which cam first, the minority population concentration or the noxious facilities, it documents their current degree of association.

  13. Not in whose backyard? Minority population concentrations and noxious facility sites

    SciTech Connect

    Nieves, L.A.

    1992-04-01

    The NIMBY (not in may backyard) syndrome has become the nemesis of facility siting efforts in the USA. Given people`s reluctance to live near noxious facilities, in whose backyard are such facilities located? This study employs US county-level data to examine relative concentrations of minorities living near noxious facilities. Facility types analyzed include electric generating plants, manufacturing plants, Superfund sites, and radioactive waste disposal sites. While this study does not address which cam first, the minority population concentration or the noxious facilities, it documents their current degree of association.

  14. Exploring Space Management Goals in Institutional Care Facilities in China

    PubMed Central

    Zhang, Jiankun

    2017-01-01

    Space management has been widely examined in commercial facilities, educational facilities, and hospitals but not in China's institutional care facilities. Poor spatial arrangements, such as wasted space, dysfunctionality, and environment mismanagement, are increasing; in turn, the occupancy rate is decreasing due to residential dissatisfaction. To address these problems, this paper's objective is to explore the space management goals (SMGs) in institutional care facilities in China. Systematic literature analysis was adopted to set SMGs' principles, to identify nine theoretical SMGs, and to develop the conceptual model of SMGs for institutional care facilities. A total of 19 intensive interviews were conducted with stakeholders in seven institutional care facilities to collect data for qualitative analysis. The qualitative evidence was analyzed through open coding, axial coding, and selective coding. As a result, six major categories as well as their interrelationships were put forward to visualize the path diagram for exploring SMGs in China's institutional care facilities. Furthermore, seven expected SMGs that were explored from qualitative evidence were confirmed as China's SMGs in institutional care facilities by a validation test. Finally, a gap analysis among theoretical SMGs and China's SMGs provided recommendations for implementing space management in China's institutional care facilities.

  15. Preconceptual design for a Monitored Retrievable Storage (MRS) transfer facility

    SciTech Connect

    Woods, W.D.; Jowdy, A.K. Co., Pasadena, CA ); Smith, R.I. )

    1990-09-01

    The contract between the DOE and the utilities specifies that the DOE will receive spent fuel from the nuclear utilities in 1998. This study investigates the feasibility of employing a simple Transfer Facility which can be constructed quickly, and operate while the full-scale MRS facilities are being constructed. The Transfer Facility is a hot cell designed only for the purpose of transferring spent fuel assemblies from the Office of Civilian Radioactive Waste Management (OCRWM) transport casks (shipped from the utility sites) into onsite concrete storage casks. No operational functions other than spent fuel assembly transfers and the associated cask handling, opening, and closing would be performed in this facility. Radioactive waste collected in the Transfer Facility during operations would be stored until the treatment facilities in the full-scale MRS facility became operational, approximately 2 years after the Transfer Facility started operation. An alternate wherein the Transfer Facility was the only waste handling building on the MRS site was also examined and evaluated. 6 figs., 26 tabs.

  16. Fitness facilities still lack accessibility for people with disabilities.

    PubMed

    Rimmer, James H; Padalabalanarayanan, Sangeetha; Malone, Laurie A; Mehta, Tapan

    2017-04-01

    Fitness facilities have potential to serve as places of 'health enhancement' for many underserved populations, particularly among people with physical/mobility disabilities where walking outdoors to meet recommendations for regular physical activity is not an option due to mobility or safety issues. To examine the accessibility and usability of fitness facilities across the U.S. from a broader framework of physical and program access. A convenience sample of 227 fitness facilities in 10 states were assessed by trained evaluators using the Accessibility Instrument Measuring Fitness and Recreation Environments (AIMFREE) tool. Non-parametric tests were performed to determine whether AIMFREE section scores were different by geographic region (urban, suburban), business type (nonprofit, for-profit), facility affiliation (fitness center/health club, park district/community center, hospital/rehabilitation facility, university/college), and facility construction date (pre/post passage of the Americans with Disabilities Act, ADA). Raw scores were converted to scaled scores with higher scores indicating better accessibility based on a criterion-referenced approach. Section scale scores (11/13) were low (<70) with differences found across facility affiliation. While facilities built after passage of the ADA had higher accessibility scores compared to pre-ADA facilities, only programs and water fountains had scaled scores ≥70 regardless of facility construction date. There exists a strong and urgent need to encourage owners and operators of fitness facilities to reach a higher level of accessibility. Until then, many people with physical/mobility disabilities will continue to have limited access to programs, equipment, and services offered at these facilities. Copyright © 2016 The Author(s). Published by Elsevier Inc. All rights reserved.

  17. SPHERES National Lab Facility

    NASA Technical Reports Server (NTRS)

    Benavides, Jose

    2014-01-01

    SPHERES is a facility of the ISS National Laboratory with three IVA nano-satellites designed and delivered by MIT to research estimation, control, and autonomy algorithms. Since Fall 2010, The SPHERES system is now operationally supported and managed by NASA Ames Research Center (ARC). A SPHERES Program Office was established and is located at NASA Ames Research Center. The SPHERES Program Office coordinates all SPHERES related research and STEM activities on-board the International Space Station (ISS), as well as, current and future payload development. By working aboard ISS under crew supervision, it provides a risk tolerant Test-bed Environment for Distributed Satellite Free-flying Control Algorithms. If anything goes wrong, reset and try again! NASA has made the capability available to other U.S. government agencies, schools, commercial companies and students to expand the pool of ideas for how to test and use these bowling ball-sized droids. For many of the researchers, SPHERES offers the only opportunity to do affordable on-orbit characterization of their technology in the microgravity environment. Future utilization of SPHERES as a facility will grow its capabilities as a platform for science, technology development, and education.

  18. NVESD mine lane facility

    NASA Astrophysics Data System (ADS)

    Habersat, James D.; Marshall, Christopher; Maksymonko, George

    2003-09-01

    The NVESD Mine Lane Facility has recently undergone an extensive renovation. It now consists of an indoor, dry lane portion, a greenhouse portion with moisture-controlled lanes, a control room, and two outdoor lanes. The indoor structure contains six mine lanes, each approximately 2.5m (width) × 1.2m (depth) × 33m(length). These lanes contain six different soil types: magnetite/sand, silt, crusher run gravel (bluestone gravel), bank run gravel (tan gravel), red clay, and white sand. An automated trolley system is used for mounting the various mine detection systems and sensors under test. Data acquisition and data logging is fully automated. The greenhouse structure was added to provide moisture controlled lanes for measuring the effect of moisture on sensor effectiveness. A gantry type crane was installed to permit remotely controlled positioning of a sensor package over any portion of the greenhouse lanes at elevations from ground level up to 5m without shadowing the target area. The roof of the greenhouse is motorized, and can be rolled back to allow full solar loading. A control room overlooking the lanes is complete with recording and monitoring devices and contains controls to operate the trolleys. A facility overview is presented and typical results from recent data collection exercises are presented.

  19. Studsvik Processing Facility Update

    SciTech Connect

    Mason, J. B.; Oliver, T. W.; Hill, G. M.; Davin, P. F.; Ping, M. R.

    2003-02-25

    Studsvik has completed over four years of operation at its Erwin, TN facility. During this time period Studsvik processed over 3.3 million pounds (1.5 million kgs) of radioactive ion exchange bead resin, powdered filter media, and activated carbon, which comprised a cumulative total activity of 18,852.5 Ci (6.98E+08 MBq). To date, the highest radiation level for an incoming resin container has been 395 R/hr (3.95 Sv/h). The Studsvik Processing Facility (SPF) has the capability to safely and efficiently receive and process a wide variety of solid and liquid Low Level Radioactive Waste (LLRW) streams including: Ion Exchange Resins (IER), activated carbon (charcoal), graphite, oils, solvents, and cleaning solutions with contact radiation levels of up to 400 R/hr (4.0 Sv/h). The licensed and heavily shielded SPF can receive and process liquid and solid LLRWs with high water and/or organic content. This paper provides an overview of the last four years of commercial operations processing radioactive LLRW from commercial nuclear power plants. Process improvements and lessons learned will be discussed.

  20. The National Ignition Facility

    SciTech Connect

    Miller, G H

    2003-12-19

    The National Ignition Facility (NIF) at Lawrence Livermore National Laboratory is a stadium-sized facility containing a 192-beam, 1.8-Megajoule, 500-Terawatt, ultraviolet laser system together with a 10-meter diameter target chamber and room for 100 diagnostics. NIF is the world's largest and most energetic laser experimental system, providing a scientific center to study inertial confinement fusion and matter at extreme energy densities and pressures. NIF's energetic laser beams will compress fusion targets to conditions required for thermonuclear burn, liberating more energy than required to initiate the fusion reactions. Other NIF experiments will study physical processes at temperatures approaching 10{sup 8} K and 10'' bar; conditions that exist naturally only in the interior of stars and planets. NIF has completed the first phases of its laser commissioning program. The first four beams of NIF have generated 106 kilojoules in 23-ns pulses of infrared light and over 16 kJ in 3.5 ns pulses at the third harmonic (351 nm). NIF's target experimental systems are being commissioned and experiments have begun. This paper discusses NIF's current and future experimental capability, plans for diagnostics, cryogenic target systems, specialized optics for experiments, and potential enhancements to NIF such as multi-color laser operation and high-energy short pulse operation.