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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. 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

  5. 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.

  6. 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.

  7. 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

  8. 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.

  9. 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. These characterization activities are tailored specifically to define: • The mechanical response of fuel meat, cladding, and interlayers, including diffusion barrier integrity • Whether geometry is stable and predictable; that changes in channel gap do not compromise ability to cool fuel • That fuel performance is known and predictable • A limited set of physical properties that are important for the analysis of fuel burnup limits • Whether swelling is stable and predictable.

  10. 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.

  11. 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.

  12. 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.

  13. Remotely Operated Equipment for Post Irradiation Examination of the SNS Target Vessel

    SciTech Connect

    Carroll, Adam J; Graves, Van B; Dayton, Michael J; Riemer, Bernie

    2011-01-01

    The Spallation Neutron Source produces neutrons by accelerating protons into flowing mercury contained inside a stainless steel target vessel. During facility operation the target vessel is degraded by a combination of high-energy neutrons, the proton beam, and cavitation-induced corrosion. The degradation is primarily concentrated at the nose of the target vessel, where the proton beam passes through. Currently, the Spallation Neutron Source has replaced three target vessels and is operating the fourth. To minimize the operational costs of manufacturing and disposing of target vessels, efforts are underway to increase the operational lifetimes of the target vessels by conducting post irradiation examinations of spent vessels. This examination involves remotely removing multiple coupons from the nose of the target vessel using a single piece of equipment, called the Nose Sampling Cutter, installed inside the Spallation Neutron Source s hot cell. The Cutter produces circular coupons approximately 2 inches in diameter using a carbide-tipped hole saw. The nose of the target vessel consists of four layers of material, and the Nose Sampling Cutter is capable of cutting through the layers in a single stroke. This remote operation has been successfully completed twice. In addition to the Nose Sampling Cutter, a large reciprocation saw capable of removing a sizable section of the nose of the target vessel has been constructed and tested, but never implemented. To support this large reciprocation saw other equipment has also been designed. The details of the Nose Sampling Cutter, reciprocation saw, and associated equipment are discussed.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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

  4. 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

  5. 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.

  6. 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.

  7. 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.

  8. 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

  9. Development of Commercial-Length Nuclear Fuel Post-Irradiation Examination Capabilities at the Oak Ridge National Laboratory

    SciTech Connect

    Ott, Larry J; Spellman, Donald J; Bevard, Bruce Balkcom; Chesser, Joel B; Morris, Robert Noel

    2009-01-01

    The U.S. Department of Energy Fissile Materials Disposition Program is pursuing disposal of surplus weapons-usable plutonium by reactor irradiation as the fissile constituent of mixed oxide (MOX) fuel. Lead test assemblies (LTAs) have been irradiated for approximately 36 months in Duke Energy s Catawba-1 nuclear power plant. Per the MOX fuel qualification plan, destructive post-irradiation examinations (PIEs) are to be performed on second-cycle rods (irradiated to an average burnup of approximately 42 GWd/MTHM). These LTA bundles are planned to be returned to the reactor and further irradiated to approximately 52 GWd/MTHM. Nondestructive and destructive PIEs of these commercially irradiated weapons-derived MOX fuel rods will be conducted at the Oak Ridge National Laboratory (ORNL) in the Irradiated Fuels Examination Laboratory (IFEL). PIE began in early 2009. In order to support the examination of the irradiated full-length (~3.66 m) MOX fuel rods, ORNL in 2004 began to develop the necessary infrastructure and equipment for the needed full-scope PIE capabilities. The preparations included modifying the IFEL building to handle a commercial spent-fuel shipping cask; procurement of cask-handling equipment and a skid to move the cask inside the building; development of in-cell handling equipment for cask unloading; and design, fabrication, and testing of the automated, state-of-the-art PIE examination equipment. This paper describes these activities and the full-scope PIE capabilities available at ORNL for commercial full-length fuel rods.

  10. Summary of the results from post-irradiation examination of spent targets at the FZ-Juelich

    NASA Astrophysics Data System (ADS)

    Chen, J.; Bauer, G. S.; Broome, T.; Carsughi, F.; Dai, Y.; Maloy, S. A.; Roedig, M.; Sommer, W. F.; Ullmaier, H.

    2003-05-01

    The lifetime of structural components of spallation targets (beam window, liquid metal container, return hull) is determined by the irradiation-induced changes of the mechanical properties of their materials. An extensive test program was initiated using specimens obtained from spent target components from operating spallation facilities (Los Alamos Neutron Science Center, LANSCE and the Spallation Neutron Source at Rutherford-Appleton Laboratory, ISIS). The investigated materials include a nickel-based alloy (IN 718), an austenitic stainless steel (AISI 304L), a martensitic stainless steel (DIN 1.4926) and a refractory metal (tantalum). The materials experienced 800 MeV proton irradiation to maximum fluences of >10 25 p/m 2. The mechanical property changes were investigated by microhardness measurements, three-point bending tests and tensile tests at temperatures ranging from room temperature (RT) to 250 °C. Subsequent scanning electron microscopy was employed to investigate the fracture surfaces. Generally, irradiation hardening and a decrease in ductility with increasing proton fluence was observed. Nevertheless, all materials except IN 718 tested at RT, retained some ductility up to the maximum doses explored. The transmission electron microscopy investigation showed that a high density of 'black dots' and dislocation loops appeared in all materials. No effect of long-range radiation-induced segregation at grain boundaries was detected by energy dispersive X-ray investigation on AISI 304L and IN718 which failed by intergranular fracture.

  11. Post-irradiation examinations and high-temperature tests on undoped large-grain UO2 discs

    NASA Astrophysics Data System (ADS)

    Noirot, J.; Pontillon, Y.; Yagnik, S.; Turnbull, J. A.

    2015-07-01

    Within the Nuclear Fuel Industry Research (NFIR) programme, several fuel variants -in the form of thin circular discs - were irradiated in the Halden Boiling Water Reactor (HBWR) at burn-ups up to ∼100 GWd/tHM. The design of the fuel assembly was similar to that used in other HBWR programmes: the assembly contained several rods with fuel discs sandwiched between Mo discs, which limited temperature differences within each fuel disc. One such variant was made of large-grain UO2 discs (3D grain size = ∼45 μm) which were subjected to three burn-ups: 42, 72 and 96 GWd/tHM. Detailed characterizations of some of these irradiated large-grain UO2 discs were performed in the CEA Cadarache LECA-STAR hot laboratory. The techniques used included electron probe microanalysis (EPMA), scanning electron microscopy (SEM) and secondary ion mass spectrometry (SIMS). Comparisons were then carried out with more standard grain size UO2 discs irradiated under the same conditions. Examination of the high burn-up large-grain UO2 discs revealed the limited formation of a high burn-up structure (HBS) when compared with the standard-grain UO2 discs at similar burn-up. High burn-up discs were submitted to temperature transients up to 1200 °C in the heating test device called Merarg at a relatively low temperature ramp rate (0.2 °C/s). In addition to the total gas release during these tests, the release peaks throughout the temperature ramp were monitored. Tests at 1600 °C were also conducted on the 42 GWd/tHM discs. The fuels were then characterized with the same microanalysis techniques as those used before the tests, to investigate the effects of these tests on the fuel's microstructure and on the fission gas behaviour. This paper outlines the high resistance of this fuel to gas precipitation at high temperature and to HBS formation at high burn-up. It also shows the similarity of the positions, within the grains, where HBS forms at high burn-up and where bubbles appear during the low

  12. 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.

  13. 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.

  14. 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

  15. 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

  16. 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.

  17. 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.

  18. 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.

  19. 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...

  20. 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.

  1. 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.

  2. Hot Fuel Examination Facility's neutron radiography reactor

    SciTech Connect

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

    1983-01-01

    Argonne National Laboratory-West is located near Idaho Falls, Idaho, and is operated by the University of Chicago for the United States Department of Energy in support of the Liquid Metal Fast Breeder Reactor Program, LMFBR. The Hot Fuel Examination Facility, HFEF, is one of several facilities located at the Argonne Site. HFEF comprises a large hot cell where both nondestructive and destructive examination of highly-irradiated reactor fuels are conducted in support of the LMFBR program. One of the nondestructive examination techniques utilized at HFEF is neutron radiography, which is provided by the NRAD reactor facility (a TRIGA type reactor) below the HFEF hot cell.

  3. 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.

  4. 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

  5. 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.

  6. 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).

  7. 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.

  8. 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.

  9. A comparative TEM study of in-reactor and post-irradiation tensile tested copper

    NASA Astrophysics Data System (ADS)

    Pakarinen, J.; Tähtinen, S.; Singh, B. N.

    2013-11-01

    The deformation microstructures of oxygen-free high-conductivity (OFHC) copper were examined by transmission electron microscopy (TEM) following in-reactor and post-irradiation slow strain rate tensile tests. The TEM results suggest that the main modes of deformation differ between all examined cases. Plastic deformation appeared predominantly localized in the defect-free cleared channels following post-irradiation testing and hardly any dislocations were seen outside the channels. The microstructures following in-reactor tests were characterized by a small amount of cleared channels and a distinct dislocation density within the matrix. However, the dislocations observed following in-reactor testing did not seem to interact with each other, whereas that was the main mode of deformation in the non-irradiated reference sample. The possible mechanisms of plastic deformation are discussed based on the experimental results. Dislocation-dislocation interactions played the major role if irradiation or irradiation damage is not present. As a result of the interactions, the microstructure of non-irradiated reference copper was characterized by a well-defined cellularized dislocation microstructure. Dynamic dislocation-displacement cascade interactions dominated the deformation process at the in-reactor tensile tests. As a result, the formation of defect-free cleared channels was delayed, dislocations were found from the matrix between the channels, and a clear strain hardening was observed after the yield point. No clear difference between accumulated irradiation damage at in-reactor and post-irradiation samples was found, which may be due to localized nature of SFT evolution in displacement cascades at copper. In the post-irradiation experiments, dislocations were confined to slip planes and annihilate irradiation defects, while moving on the planes and creating defect-free cleared channels. The plastic deformation is localized into these channels, causing a decrease in

  10. 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.

  11. 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…

  12. 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.

  13. Endovascular Management of Post-Irradiated Carotid Blowout Syndrome

    PubMed Central

    Chang, Feng-Chi; Luo, Chao-Bao; Lirng, Jiing-Feng; Lin, Chung-Jung; Lee, Han-Jui; Wu, Chih-Chun; Hung, Sheng-Che; Guo, Wan-Yuo

    2015-01-01

    Purpose To retrospectively evaluate the clinical and technical factors related to the outcomes of endovascular management in patients with head-and-neck cancers associated with post-irradiated carotid blowout syndrome (PCBS). Materials and Methods Between 2000 and 2013, 96 patients with PCBS underwent endovascular management. The 40 patients with the pathological lesions located in the external carotid artery were classified as group 1 and were treated with embolization. The other 56 patients with the pathological lesions located in the trunk of the carotid artery were divided into 2 groups as follows: group 2A comprised the 38 patients treated with embolization, and group 2B comprised the 18 patients treated with stent-graft placement. Fisher’s exact test was used to examine endovascular methods, clinical severities, and postprocedural clinical diseases as predictors of outcomes. Results Technical success and immediate hemostasis were achieved in all patients. The results according to endovascular methods (group 1 vs 2A vs 2B) were as follows: technical complication (1/40[2.5%] vs 9/38[23.7%] vs 9/18[50.0%], P = 0.0001); rebleeding (14/40[35.0%] vs 5/38[13.2%] vs 7/18[38.9%]), P = 0.0435). The results according to clinical severity (acute vs ongoing PCBS) were as follows: technical complication (15/47[31.9%] vs 4/49[8.2%], P = 0.0035); rebleeding (18/47[38.3%] vs 8/49[16.3%], P = 0.0155). The results according to post-procedural clinical disease (regressive vs progressive change) were as follows: alive (14/21[66.7%] vs 8/75[10.7%], P<0.0001); survival time (34.1±30.6[0.3–110] vs 3.6±4.0[0.07–22] months, P<0.0001). Conclusion The outcomes of endovascular management of PCBS can be improved by taking embolization as a prior way of treatment, performing endovascular intervention in slight clinical severity and aggressive management of the post-procedural clinical disease. PMID:26439632

  14. Examining the amenability of urban street networks for locating facilities

    NASA Astrophysics Data System (ADS)

    Zhang, Tong; Zeng, Zhe; Jia, Tao; Li, Jing

    2016-09-01

    This paper aims to characterize urban street networks from the perspective of facility location that is widely used for siting public or private services. Both topological and geometrical features of urban street networks are investigated to examine their impacts on the performance of facility location. We propose a set of efficiency and centrality measures to evaluate the amenability of street networks for locating facilities. The evaluation of 15 large cities in the U.S. reveals that facility locations are strongly affected by road network structures. For realistic street networks, grid planned road network are more amenable to locating facilities than irregular networks. The analyses on idealized network offer further evidence of the correlations between network properties and service provision efficiencies.

  15. 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.

  16. 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.

  17. 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.

  18. Waste Examination Assay Facility operations: TRU waste certification

    SciTech Connect

    Schultz, F.J.; Caylor, B.A.; Coffey, D.E.; Phoenix, L.B.

    1987-01-01

    The ORNL Waste Examination Assay Facility (WEAF) was established to nondestructively assay (NDA) transuranic (TRU) waste generated at Oak Ridge National Laboratory (ORNL). The present facility charter encompasses the NDA and nondestructive examination (NDE) of both TRU and low-level wastes (LLW). Presently, equipment includes a Neutron Assay System (NAS), a Segmented Gamma Scanner (SGS), a drum-sized Real-Time Radiography (RTR) system, and a Neutron Slab Detector (NSD). The first three instruments are computer interfaced. Approximately 2300 TRU waste drums have been assayed with the NAS and the SGS. Another 3000 TRU and LLW drums have been examined with the RTR unit. Computer data bases have been developed to collate the large amount of data generated during the assays and examinations. 6 refs., 1 tab.

  19. 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.

  20. Update on the Hot Fuel Examination Facility (HFEF) complex

    SciTech Connect

    Bacca, J.P.

    1985-01-01

    The Hot Fuel Examination Facility (HFEF) Complex continues to provide primary postirradiation handling and examination support for the US, US/Japanese, and US/United Kingdom Liquid Metal Fast Breeder Reactor (LMFBR) fuels and materials development and reactor safety programs. For the last several years, such support has also been provided for other US nuclear programs. These include the Light Water Reactor Safety Program, the Three Mile Island No. 2 (TMI-2) reactor accident-recovery programs, the Light Water Breeder Reactor Program, the US Air Force Neutron Radiography Program, and Defense Nuclear Programs. The HFEF facilities have been refurbished and upgraded and capabilities have been added to accommodate these programs and to maintain the HFEF Complex as a world-class, state-of-the-art hot-cell complex.

  1. Validation of a Monte Carlo Based Depletion Methodology Using HFIR Post-Irradiation Measurements

    SciTech Connect

    Chandler, David; Maldonado, G Ivan; Primm, Trent

    2009-11-01

    Post-irradiation uranium isotopic atomic densities within the core of the High Flux Isotope Reactor (HFIR) were calculated and compared to uranium mass spectrographic data measured in the late 1960s and early 70s [1]. This study was performed in order to validate a Monte Carlo based depletion methodology for calculating the burn-up dependent nuclide inventory, specifically the post-irradiation uranium

  2. 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.

  3. Post-Irradiated Human Submandibular Glands Display High Collagen Deposition, Disorganized Cell Junctions, and an Increased Number of Adipocytes.

    PubMed

    Nam, Kihoon; Maruyama, Christina L; Trump, Bryan G; Buchmann, Luke; Hunt, Jason P; Monroe, Marcus M; Baker, Olga J

    2016-06-01

    Salivary glands are vital for maintaining oral health. Head and neck radiation therapy is one of the most common causes of salivary gland hypofunction. Little is known about the structural changes that occur in salivary glands after radiation therapy. The aim of this study is to understand the structural changes that occur in post-irradiated human (submandibular gland [SMG]) as compared with untreated ones. We determined changes in epithelial polarity, presence of collagen deposition, and alteration in adipose tissue. We used formalin-fixed paraffin-embedded human SMG from two female subjects exposed to head and neck irradiation. We utilized hematoxylin and eosin staining and Masson's Trichrome staining. The immunostained tissue sections were examined using confocal microscopy. The number and size of adipocytes per tissue section were calculated using ImageJ, Prism, and SPSS software. Post-irradiated human SMG displayed high collagen deposition, disorganized cell junctions, and an increased number of adipocytes as compared with non-irradiated controls. These findings are important to improve our understanding of the individual risk and variation in radiation-related salivary gland dysfunction. PMID:27126825

  4. Post irradiation analysis of RERTR-7A, 7B and RERTR-8 tests

    SciTech Connect

    Hofman, G.L.; Kim, Yeon Soo; Shevlyakov, G.V.; Robinson, A.B.

    2008-07-15

    Addition of 2 wt% or more of silicon in the Al matrix for U-Mo/Al dispersion fuel has proved to be effective in reducing interaction layer growth from the RERTR-7A test to a burnup of {approx}100 at% U-235 (LEU equivalent). The recent RERTR-8 test also showed the consistent results. In this paper, we present the post irradiation analysis results of these tests. A considerable number of monolithic fuel plates were irradiated in the RERTR-7A and RERTR-8 tests. The post irradiation results of these plates are also included. The RERTR-7B test was a lower burnup test with similar power to the RERTR-7A. In this test, dispersion fuel plates with U-7Mo-1Ti and U- 7Mo-2Zr in Al-5Si were irradiated. The post irradiation results of these plates are also covered. (author)

  5. 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

  6. 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.

  7. 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.

  8. 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.

  9. Facility effluent monitoring plan for the 327 Facility

    SciTech Connect

    1994-11-01

    The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements.

  10. Post-irradiation mechanical properties of an AlMgSi alloy

    NASA Astrophysics Data System (ADS)

    Ismail, Z. H.; Birt, B.

    1995-03-01

    The effect of fast-neutron irradiation on the tensile properties and hardness of the age-hardenable alloy AlMgSi is investigated. Post-irradiation tensile tests are carried out in the temperature range 298 to 628 K. The results show that the degree of irradiation-produced hardening is dependent upon the initial condition of the alloy. The alloy in its soft condition exhibits a higher degree of irradiation hardening compared with that in the hard condition. The implication of the results is discussed in terms of the variation in the microstructures involved and compared with previosly published data.

  11. 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. PMID:25773266

  12. Transient and Post-irradiation Response of Optoelectronic Devices to Ionizing Radiation

    NASA Astrophysics Data System (ADS)

    Haider, F. A. A.; Chee, F. P.

    2015-01-01

    Space and ground level electronic equipment with semiconductor devices are subjected to the deleterious effects by radiation. This paper is attempted to present the transient and post-irradiation response of optoelectronic devices to gamma (γ) rays utilizing cobalt-60. In situ measurements were made on the devices under test (DUTs) up to a total dose of 60 krad followed by a post-irradiation not in-flux test for eight hours. Current transfer ratio (CTR) with is the vital merit of the optoelectronic system is found to decrease remarkably with the absorbed dose. This degradation is induced by the interaction of the energetic photons from gamma rays via two main mechanisms. The dominant effect is the mechanism by ionization while the secondary is by displacement. This radiation effect is found to arouse either a permanent or temporarily damage in the DUTs depending on their current drives and also the Total Ionizing Dose (TID) absorbed. The TID effects by gamma rays are cumulative and gradually take place throughout the lifecycle of the devices exposed to radiation. The full damage cascade phenomenon in the DUTs is calculated via the simulation.

  13. 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.

  14. 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

  15. 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.

  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. 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.

  18. 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.

  19. Remotely operated organic liquid waste incinerator for the fuels and materials examination facility

    SciTech Connect

    Sales, W.L.; Barker, R.E.; Hershey, R.B.

    1980-01-01

    The search for a practical method for the disposal of small quantities of oraganic liquid waste, a waste product of metallographic sample preparation at the Fuels and Materials Examination Facility has led to the design of an incinerator/off-gas system to burn organic liquid wastes and selected organic solids. The incinerator is to be installed in a shielded inert-atmosphere cell, and will be remotely operated and maintained. The off-gas system is a wet-scrubber and filter system designed to release particulate-free off-gas to the FMEF Building Exhaust System.

  20. The environmental impact assessment process for nuclear facilities: An examination of the Indian experience

    SciTech Connect

    Ramana, M.V.; Rao, Divya Badami

    2010-07-15

    India plans to construct numerous nuclear plants and uranium mines across the country, which could have significant environmental, health, and social impacts. The national Environmental Impact Assessment process is supposed to regulate these impacts. This paper examines how effective this process has been, and the extent to which public inputs have been taken into account. In addition to generic problems associated with the EIA process for all kinds of projects in India, there are concerns that are specific to nuclear facilities. One is that some nuclear facilities are exempt from the environmental clearance process. The second is that data regarding radiation baseline levels and future releases, which is the principle environmental concern with respect to nuclear facilities, is controlled entirely by the nuclear establishment. The third is that members of the nuclear establishment take part in almost every level of the environmental clearance procedure. For these reasons and others, the EIA process with regard to nuclear projects in India is of dubious quality. We make a number of recommendations that could address these lacunae, and more generally the imbalance of power between the nuclear establishment on the one hand, and civil society and the regulatory agencies on the other.

  1. Charge transfer inefficiency in the pre- and post-irradiated Swept Charge Device CCD236

    NASA Astrophysics Data System (ADS)

    Smith, P. H.; Gow, J. P. D.; Pool, P.; Holland, A. D.

    2015-03-01

    This paper describes the mapping of spectral response of an e2v technologies Swept Charge Device (SCD) CCD236 pre and post irradiation with a 10 MeV equivalent proton fluence of 5.0 × 108 protons cm-2. The CCD236 is a large area (4.4 cm2) X-ray detector which will be used in India's Chandrayaan-2 Large Soft X-ray Spectrometer (CLASS) and China's Hard X-ray Modulation Telescope (HXMT). To enable the suppression of surface dark current, clocking is performed continuously resulting in a linear readout. As such the flat field illumination used to measure any change in spectral response over a conventional Charge-Coupled Devices (CCDs) is not possible. An alternative masking technique has been used to expose pinpoint regions of the device to Mn-Kα and Mn-Kβ X-rays, enabling a local map of spectral response to be built up over the device. This novel approach allows for an estimation of the Charge Transfer Inefficiency (CTI) of the device to be made by allowing the creation of a CTI scatter plot similar to that typically observed in conventional CCDs.

  2. 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.

  3. Post irradiation analysis and performance modeling of dispersion and monolithic U-Mo fuels

    SciTech Connect

    Kim, Yeon Soo; Hofman, G.L.; Medvedev, P.G.; Robinson, A.B.; Shevlyakov, G.V.; Ryu, H.J.

    2008-07-15

    We analyzed fission product swelling of post-irradiation U-Mo fuels from the early RERTR tests to the recent RERTR-8 test. We found that the gas bubble swelling of the fuel-swelling model was overestimated. From the recent tests, RERTR-7A and 8, we could also collect a considerable amount of fuel swelling data from monolithic U-Mo fuel plates. The fuel swelling data from the monolithic fuel plates are considered more reliable because the interaction layer growth between the fuel and matrix in dispersion fuel, which obscures fuel swelling, does not exist. The swelling correlation comparison to the Si-added dispersion fuel data and monolithic fuel data suggested that a modification of the existing model was necessary. We also developed an interaction layer growth model for U-Mo/Al dispersion fuel plates with a Si-added matrix. PLATE code calculations with the new PIE data analysis results were performed. The updated versions predict with better accuracies for both monolithic fuel plates and dispersion fuel plates. In this paper, we present the results of fission product swelling characterization. In addition, the interaction layer growth model for U-Mo/Al with a Si-added matrix is presented. (author)

  4. 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

  5. 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.

  6. Recovery from hematopoietic injury by modulating prostaglandin E(2) signaling post-irradiation.

    PubMed

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

    2013-03-01

    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 E(2) (PGE(2)) 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 PGE(2) signaling in a mouse model of HS-ARS. Treatment with the PGE(2) analog 16,16 dimethyl PGE(2) (dmPGE(2)) 6h post-irradiation or inhibition of PGE(2) synthesis via delayed administration of the non-steroidal anti-inflammatory drug (NSAID) Meloxicam resulted in increased survival of lethally irradiated mice. Both early dmPGE(2) and delayed Meloxicam treatment were associated with increased HPC activity 35days 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

  7. 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. PMID:26613913

  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. 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."…

  10. 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

  11. 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.

  12. 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,…

  13. 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

    ... 42 Public Health 4 2014-10-01 2014-10-01 false Examination of the operations and records of health care facilities and practitioners. 476.88 Section 476.88 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) QUALITY IMPROVEMENT ORGANIZATIONS QUALITY IMPROVEMENT ORGANIZATION REVIEW...

  14. 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

    ... 42 Public Health 4 2013-10-01 2013-10-01 false Examination of the operations and records of health care facilities and practitioners. 476.88 Section 476.88 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) QUALITY IMPROVEMENT ORGANIZATIONS UTILIZATION AND QUALITY CONTROL REVIEW...

  15. 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

    ... 42 Public Health 4 2012-10-01 2012-10-01 false Examination of the operations and records of health care facilities and practitioners. 476.88 Section 476.88 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) QUALITY IMPROVEMENT ORGANIZATIONS UTILIZATION AND QUALITY CONTROL REVIEW...

  16. The Change in the hardness of LCAC. TZM, and ODS molybdenum in the post-irradiated and annealed conditions

    SciTech Connect

    Cockeram, Brian V; Smith, Richard W; Byun, Thak Sang; Snead, Lance Lewis

    2009-01-01

    Hardness measurements were performed on wrought Low Carbon Arc Cast (LCAC), TZM, and Oxide Dispersion Strengthened (ODS) molybdenum in the post-irradiated and post-irradiated + annealed condition to determine the recovery kinetics. Irradiations performed in the High Flux Isotope Reactor (HFIR) at nominally 300 C and 600 C to neutron fluence levels that range from 10.5 to 246 x 10{sup 24} n/m{sup 2} (E > 0.1 MeV) resulted in relatively large increases in hardness (77-109%), while small increases in hardness (<18%) were observed for irradiations at 870-1100 C. The hardness recovery for ODS and LCAC irradiated at 300 C and 600 C were shown to be complete at 980 C and {approx} 1100-1250 C, respectively. Isothermal annealing at 700 C was used to determine the activation energy for recovery of LCAC and ODS (3.70-4.88 eV {+-} 0.28-0.77 eV), which is comparable to values reported in the literature for molybdenum vacancy self-diffusion. This suggests that recovery of LCAC and ODS is controlled by the solid-state diffusion of vacancies in the bulk, and that the finer grain size and particle size ODS does not affect this mechanism. TZM exhibited slower recovery kinetics, which can be explained by the solute atoms (titanium and zirconium) inhibiting vacancy diffusion.

  17. Review of Research on Post Irradiation Fruit Quality of Blueberries and Peaches

    Technology Transfer Automated Retrieval System (TEKTRAN)

    The commercial use of irradiation is accelerating with the approval of low dose generic treatments for insect disinfestations and the availability of irradiation facilities. Commercial adoption of irradiation treatment requires an understanding of the radiotolerance limits for individual commodities...

  18. 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.

  19. The new postirradiation examination facility of the Atomic Energy Corporation of South Africa

    SciTech Connect

    Walt, P.L. van der; Aspeling, J.C.; Jonker, W.D.; Sliep, A.S.J.F. )

    1992-01-01

    The Pelindaba Hot Cell Complex (HCC) forms an important part of the infrastructure and support services of the Atomic Energy Corporation (AEC) of South Africa. It is a comprehensive, one-stop facility designed to make South Africa self-sufficient in the fields of spent-fuel qualification and verification, reactor pressure vessel surveillance program testing, ad hoc failure analyses for the nuclear power industry, and research and development studies in conjunction with the Safari I material test reactor (MTR) and irradiation rigs. Local technology and expertise was used for the design and construction of the HCC, which start up in 1980. The facility was commissioned in 1990.

  20. An examination of the health profile, service use and care needs of older adults in residential care facilities.

    PubMed

    Aminzadeh, F; Dalziel, W 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, patterns of service use, and medical/care needs of a representative sample of 178 older adults in residential care facilities in the City of Ottawa. The results indicate great diversity in resident and facility profiles in this setting and confirm earlier impressions that special care units in the residential care sector have become increasingly close to being unlicensed pseudo-nursing homes. Despite the heavy burden of care, the evidence suggests that the care needs of the majority of residents are adequately met in the residential care environment. The results can inform future research, case finding, educational, and policy planning initiatives in this setting. PMID:15660301

  1. 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.

  2. Differences in pain measures by mini-mental state examination scores of residents in aged care facilities: examining the usability of the Abbey pain scale-Japanese version.

    PubMed

    Takai, Yukari; Yamamoto-Mitani, Noriko; Ko, Ayako; Heilemann, Marysue V

    2014-03-01

    The validity and reliability of the Abbey Pain Scale-Japanese version (APS-J) have been examined. However, the range of cognitive levels for which the APS-J can be accurately used in older adults has not been investigated. This study aimed to examine the differences between total/item scores of the APS-J and Mini-Mental State Examination (MMSE) scores of residents in aged care facilities who self-reported the presence or absence of pain. This descriptive study included 252 residents in aged care facilities. Self-reported pain, MMSE scores, and item/total APS-J scores for pain intensity were collected. The MMSE scores were used to create four groups on the basis of the cognitive impairment level. Self-reports of pain and the APS-J scores were compared with different MMSE score groups. The total APS-J score for pain intensity as well as scores for individual items such as "vocalization" and "facial expression" were significantly higher in those who reported pain than in those reporting no pain across all MMSE groups. The total APS-J score and item scores for "vocalization," "change in body language," and "behavioral changes" showed significant differences in the four MMSE groups. Pain intensity tended to be overestimated by the APS-J, especially among those with low MMSE scores. The APS-J can be used to assess pain intensity in residents despite their cognitive levels. However, caution is required when using it to compare scores among older adults with different cognitive capacity because of the possibility of overestimation of pain among residents with low cognitive capacity. PMID:23237690

  3. High temperature post-irradiation performance of spent pressurized-water-reactor fuel rods under dry-storage conditions

    SciTech Connect

    Einziger, R.E.; Atkin, S.D.; Stellrecht, D.E.; Pasupathi, V.

    1981-06-01

    Post-irradiation studies on failure mechanisms of well characterized PWR rods were conducted for up to a year at 482, 510 and 571/sup 0/C in unlimited air and inert gas atmospheres. No cladding breaches occurred even though the tests operated many orders of magnitude longer in time than the lifetime predicted by Blackburn's analyses. The extended lifetime is due to significant creep strain of the Zircaloy cladding which decreases the internal rod pressures. The cladding creep also contributes to radial cracks, through the external oxide and internal FCCI layers, which propagated into and arrested in an oxygen stabilized ..cap alpha..-Zircaloy layer. There were no signs of either additional cladding hydriding, stress-corrosion cracking or fuel pellet degradation. Using the Larson-Miller formulization, a conservative maximum storage temperature of 400/sup 0/C is recommended to ensure a 1000-year cladding lifetime. This accounts for crack propagation and assumes annealing of the irradiation-hardened cladding.

  4. The reduction of radiation damage to the spinal cord by post-irradiation administration of vasoactive drugs

    SciTech Connect

    Hornsey, S.; Myers, R.; Jenkinson, T. )

    1990-06-01

    Radiation induced white matter necrosis in the rat spinal cord is preceded by changes in permeability of the blood brain-barrier, reduced blood flow, and infarction so that the necrosis is an ischemic necrosis. Attempts have been made to modify this developing pathology by the administration of drugs post-irradiation but just prior to the changes in vascular permeability. Verapamyl, a calcium channel blocker, had no effect on the development of ataxia. Dipyridamole, a drug which increases blood flow and reduces thrombosis, delayed and reduced the onset of ataxia. A low iron diet and desferrioxamine which reduces reperfusion injury also delayed and reduced ataxia. These results support the thesis that vascular changes are an important pathway in the development of radiation necrosis and that reperfusion injury is an important factor in the development and exacerbation of radiation damage to the spinal cord.

  5. 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.

  6. Radiation resistance and post-irradiation proliferation of Listeria monocytogenes on ready-to-eat deli meat in the presence of pectin/nisin films

    Technology Transfer Automated Retrieval System (TEKTRAN)

    In this study, the ability of pectin/nisin films in combination with ionizing radiation to eliminate Listeria monocytogenes and inhibit its post-irradiation proliferation was evaluated. Pectin films containing 0.025% nisin were made by extrusion. The surface of a read-to-eat (RTE) turkey meat sample...

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

    SciTech Connect

    1998-04-01

    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: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. Changes to the FFCA site treatment plans as a result of proposals in DOE's Accelerating Cleanup: Paths to Closure strategy and contractor integration analysis. Interstate waste and materials shipments. 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 December 31, 1997 through April 30, 1998 under the NGA project. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; and provided ongoing support to state-DOE interactions in preparation for the March 30-31, 1998 NGA Federal Facilities Compliance Task Force Meeting with DOE. maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low

  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

    Jaszczyński, Janusz; Kojs, Zbigniew; Stelmach, Andrzej; Wohadło, Łukasz; Łuczyńska, Elzbieta; 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 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. PMID:27474270

  9. 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

  10. 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.

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

    SciTech Connect

    Ethan W. Brown

    2001-09-01

    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: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. 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. Interstate waste and materials shipments. 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 period from April 1, 2001 through June 30, 2001, under the NGA grant.

  12. 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

  13. 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

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

    SciTech Connect

    Ann M. Beauchesne

    1999-07-30

    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: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; 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; Interstate waste and materials shipments; and 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 May 1, 1999, through July 30, 1999, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; 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 continued to facilitate interactions between the states and DOE to develop a

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

    SciTech Connect

    Ann M. Beauchesne

    2000-01-01

    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: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; 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; Interstate waste and materials shipments; and 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 period from October 1, 1999 through January 31, 2000, under the NGA grant. The work accomplished by the NGA project team during the past three months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; convened and facilitated the October 6--8 NGA FFCA Task Force Meeting in Oak Ridge, Tennessee; 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

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

    SciTech Connect

    1998-07-01

    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: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. Changes to the FFCA site treatment plans as a result of proposals in DOE's Accelerating Cleanup: Paths to Closure strategy and contractor integration analysis. Interstate waste and materials shipments. 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 April 30, 1998 through June 30, 1998 under the NGA project. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; and provided ongoing support to state-DOE interactions. 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, DOE's Environmental Management Budget, and DOE's proposed

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

    SciTech Connect

    Ann M. Beauchesne

    1999-04-30

    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: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; 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; Interstate waste and materials shipments; and 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 February 1, 1999, through April 30, 1999, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; 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 continued to serve as a liaison between

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

    SciTech Connect

    1998-01-01

    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: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. Changes to the FFCA site treatment plans as a result of proposals in the EM 2006 cleanup plans and contractor integration analysis. Interstate waste and materials shipments. 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, 1997 through December 31, 1997, under the NGA project. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; and 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, DOE activities in the area of the Hazardous Waste Identification Rule, and DOE's proposed National Dialogue.

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

    SciTech Connect

    Hill, Carolyn D.

    2004-08-01

    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.

  20. 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. PMID:15824586

  1. Post-irradiation plastic deformation in bcc Fe grains investigated by means of 3D dislocation dynamics simulations

    NASA Astrophysics Data System (ADS)

    Gururaj, K.; Robertson, C.; Fivel, M.

    2015-04-01

    Post-irradiation tensile straining is investigated by means of three-dimensional dislocation dynamics simulations adapted to body centred cubic Fe. Namely, 1 μm Fe grains are strained at various temperatures in the 100-300 K range, in absence and in presence of radiation-induced defect dispersions. The defect-induced hardening is consistent with the disperse barrier effect up to 5 ×1021m-3 loops and is weakly dependent on the straining temperature. The dislocation-loops interaction rate augments with the accumulated plastic strain, loop density and strength; while it is mainly independent of the number of active slip systems and thermally activated screw dislocation mobility. An additional, radiation-induced hardening mechanism known as dislocation "decoration" is also implemented and tested for comparison. Those results show that the plastic flow localisation transition depends on the total yield point rise rather than on the lone, dispersed loop density. The simulation results are then rationalized through an original micro-mechanical model relating the grain-scale stress-strain behaviour to dislocation sub-structure formation and spreading. That model combines strain dependent and strain independent hardening mechanisms, which both contribute to the associated stress-strain response and plastic flow spreading.

  2. Effect of boron on post irradiation tensile properties of reduced activation ferritic steel (F-82H) irradiated in HFIR

    SciTech Connect

    Shiba, Kiyoyuki; Suzuki, Masahide; Hishinuma, Akimichi; Pawel, J.E.

    1994-12-31

    Reduced activation ferritic/martensitic steel, F-82H (Fe-8Cr-2W-V-Ta), was irradiated in the High Flux Isotope Reactor (HFIR) to doses between 11 and 34 dpa at 400 and 500 C. Post irradiation tensile tests were performed at the nominal irradiation temperature in vacuum. Some specimens included {sup 10}B or natural boron (nB) to estimate the helium effect on tensile properties. Tensile properties including the 0.2% offset yield stress, the ultimate tensile strength, the uniform elongation and the total elongation were measured. The tensile properties were not dependent on helium content in specimens irradiated to 34 dpa, however {sup 10}B-doped specimens with the highest levels of helium showed slightly higher yield strength and less ductility than boron-free specimens. Strength appears to go through a peak, and ductility through a trough at about 11 dpa. The irradiation to more than 21 dpa reduced the strength and increased the elongation to the unirradiated levels. Ferritic steels are one of the candidate alloys for nuclear fusion reactors because of their good thermophysical properties, their superior swelling resistance, and the low corrosion rate in contact with potential breeder and coolant materials.

  3. Post service examination of a tritium permeator and a turbomolecular pump from the CAPER Facility at the Tritium Laboratory Karlsruhe

    SciTech Connect

    Caldwell-Nichols, C. J.; Adami, H. D.; Bekris, N.; Demange, D.; Glugla, M.; Kramer, F.; Simon, K. H.

    2008-07-15

    After 8 years of operation at the CAPER facility at the Tritium Laboratory Karlsruhe, a permeator used to separate hydrogen species from processed gases ceased operation due to multiple heater failures. This was subjected to post service examination to find the cause of the failures. This paper describe the methods used to locate the failures in the heaters and the likely cause. It was also necessary to determine the tritium inventory embedded in the structure for safe disposal. Destructive examination, adapted from a full combustion technique, was used on sections of the permeator. A fine black powder deposit, presumed to be mostly carbon, coated the surfaces of the inlet section of the feed side. This powder contained nearly half of the tritium within the permeator. The likely source of the powder and the consequences for the operation and eventual decommissioning of the ITER Tritium Plant are discussed. A failed turbomolecular pump from CAPER was also examined. There was evidence of wear on the emergency support bearing, but more importantly, when the pump internals were exposed to the glove box atmosphere (dry air) large quantities of tritium were rapidly released, this despite the isotopic swamping before removal from the CAPER glove box. Significant uptake of tritium in electrical insulation was also found. (authors)

  4. Fast Flux Test Facility interim examination and maintenance cell contaminated sodium recovery system: Remote handling design consideration

    SciTech Connect

    Carteret, B.A.

    1988-11-01

    The Westinghouse Hanford Company is installing a remotely operated Contaminated Sodium Recovery System (CSRS) at the Fast Flux Test Facility (FFTF) located in Richland, Washington. The CSRS will recover activated sodium that accumulates in fuel transfer machines during core component transfer operations. Drip pots from the FFTF fuel handling machines will be delivered to the shielded, argon-inerted Interim Examination and Maintenance (IEM) Cell, a hot cell located in the FFTF containment structure. Installation of the CSRS replaces a previously manual operation that required disposal of radioactive sodium with a completely remote operation that will return sodium to service in the plant. The CSRS will minimize the accumulation of hazardous waste and reduce personnel exposure to radioactive materials. Equipment for the CSRS is currently being fabricated and tested before installation in the IEM Cell. 6 figs.

  5. 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.

  6. 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

  7. Effects of Irradiation and Post-Irradiation Annealing on the Thermal Conductivity/ Diffusivity of Monolithic SIC and SIC/SIC Composites

    SciTech Connect

    Youngblood, Gerald E.; Senor, David J.; Jones, Russell H.

    2004-08-01

    Laser flash thermal diffusivity measurements were made on high-purity monolithic CVD-SiC (impurity concentration <5 wppm) and 2D f-SiC/PyC/ICVI-SiC composite samples (plain weave Hi-Nicalon (Trademark) fabric layers with 0-90 layup made by the isothermal chemical vapor infiltration process and with either a “thick” 1.0 µm or a “thin” 0.11 µm PyC fiber coating) before and after irradiation in the HFIR reactor (250 to 800°C, 4-8 dpa-SiC) and after post-irradiation annealing composite samples to 1200°C. Thermal conductivity in SiC is controlled by phonon transport. Point defects introduced into SiC during neutron irradiation are effective scattering centers for phonons, and as a consequence the thermal conductivity is sharply reduced. For irradiation temperatures below ~800°C, the accumulation of point defects (in SiC mostly single or small clusters of interstitials and isolated vacancies) saturates when the interstitial-vacancy recombination rate equals the defect production rate. For saturation conditions, the relative reduction in the SiC thermal conductivity decreases in a manner similar to its swelling reduction with increasing irradiation temperature. Examination of SiC swelling data at various irradiation temperatures and doses indicates that saturation occurs for ~2 dpa-SiC at 200°C and decreases continuously to ~0.4 dpa-SiC at 800°C. Based on a model that assumes a uniform distribution of the phonon scattering defects, the calculated defect concentration for unirradiated CVD-SiC was less than 1 appm, which is consistent with the manufacturer’s value of <5 wppm impurities. The defect concentrations estimated for the irradiated CVD-SiC samples decreased continuously from ~25,000 to 940 appm as the irradiation temperature increased from 252 to 800°C. The small intrinsic defect concentration in comparison to the rather large extrinsic irradiation-induced defect concentrations illustrates why CVD-SiC makes an ideal irradiation damage monitor.

  8. 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. PMID:26634866

  9. 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.

  10. 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

    ... SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) QUALITY IMPROVEMENT ORGANIZATIONS UTILIZATION AND QUALITY CONTROL REVIEW Review Responsibilities of Utilization and Quality Control Quality... facility to perform quality review functions under a subcontract with the QIO. (b) Limitations on access...

  11. 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

  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. 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/.

  14. 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

    ... SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) QUALITY IMPROVEMENT ORGANIZATIONS UTILIZATION AND QUALITY CONTROL REVIEW Review Responsibilities of Utilization and Quality Control Quality Improvement Organizations (QIOs) Qio Review Functions § 476.88 Examination of the operations and records...

  15. 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

  16. Low-dose γ-irradiation induces dual radio-adaptive responses depending on the post-irradiation time by altering microRNA expression profiles in normal human dermal fibroblasts.

    PubMed

    Bae, Seunghee; Kim, Karam; Cha, Hwa Jun; Choi, Yeongmin; Shin, Shang Hun; An, In-Sook; Lee, Jae Ho; Lee, Su Jae; Kim, Ji Young; Nam, Seon Young; An, Sungkwan

    2015-01-01

    Exposure to high-dose ionizing radiation, including γ-radiation, induces severe skin disorders. However, the biological consequences and molecular mechanisms responsible for the response of human skin to low-dose γ-radiation (LDR) are largely unknown. In the present study, we demonstrate that LDR (0.1 Gy) induces distinct cellular responses in normal human dermal fibroblasts (NHDFs) depending on the post-irradiation time point. A MTT-based cell viability assay and propidium iodide staining-based cell cycle assay revealed that the viability and proportion of the cells in the G2/M phase were differed at 6 and 24 h post-irradiation. Reverse transcription quantitative PCR (RT-qPCR) revealed that LDR significantly upregulated the mRNA expression of collagen type I alpha 1 (COL1A1), but downregulated the mRNA expression of matrix metalloproteinase 1 (MMP1) at 24 h post-irradiation. MicroRNA (miRNA) microarray analysis further demonstrated that LDR induced changes in the expression profiles of specific miRNAs and that some of the deregulated miRNAs were specific to either the early or late radio-adaptive response. Our results suggest that LDR generates dual radio-adaptive responses depending on the post-irradiation time by altering specific miRNA expression profiles in NHDFs. PMID:25384363

  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. 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.

  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. 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.

  1. Effects of irradiation and post-irradiation annealing on the thermal conductivity/diffusivity of monolithic SiC and f-SiC/SiC composites

    NASA Astrophysics Data System (ADS)

    Youngblood, G. E.; Senor, D. J.; Jones, R. H.

    2004-08-01

    Laser flash thermal diffusivity measurements were made on high-purity monolithic CVD-SiC and 2D f-SiC(Hi-Nicalon™)/ICVI-SiC composite samples before and after irradiation (250-800 °C, 4-8 dpa-SiC) and after post-irradiation annealing composite samples to 1200 °C. For irradiated CVD-SiC, the defect concentrations at saturation were estimated to range from 25 300 appm (250 °C) down to 940 appm (800 °C). The transverse thermal conductivity ratios after-to-before irradiation ( Kir/ Ko) determined at the irradiation temperatures ranged from: 0.044 (250 °C) up to 0.12 (800 °C) for irradiated CVD-SiC and 0.18 (330 °C) up to 0.29 (800 °C) for the irradiated Hi-Nicalon™ composite. Analysis of thermal diffusivity values for the Hi-Nicalon composite measured in air, argon, helium and vacuum indicated that thermal conductivity degradation occurred primarily due to point defect accumulation in the matrix component. After annealing to 1200 °C and cooling to ambient, fiber/matrix debonding occurred due to net shrinkage in the fiber and PyC interface components.

  2. Effects of irradiation and post-irradiation annealing on the thermal conductivity/diffusivity of monolithic SiC and f-SiC/SiC composites

    SciTech Connect

    Youngblood, Gerald E.; Senor, David J.; Jones, Russell H.

    2004-08-01

    Laser flash thermal diffusivity measurements were made on high-purity monolithic CVD-SiC and 2D f-SiC(Hi-Nicalon)/ICVI-SiC composite samples before and after irradiation (250 to 800C, 4-8 dpa-SiC) and after post-irradiation annealing composite samples to 1200C. For irradiated CVD-SiC, the defect concentrations at saturation were estimated to range from 25,300 appm (250C) down to 940 appm (800C). The transverse thermal conductivity ratios after-to-before irradiation (Kir/Ko) determined at the irradiation temperatures were: 0.044 up to 0.12 (250 up to 800C) for irradiated CVD-SiC and 0.18 up to 0.29 (330 up to 800C) for the irradiated Hi-Nicalon composite. Analysis of thermal diffusivity values for the Hi-Nicalon composite measured in air, argon, helium and vacuum indicated that thermal conductivity degradation occurred primarily due to point defect accumulation in the matrix component. After annealing to 1200C and cooling to the irradiation temperature, fiber/matrix debonding occurred due to net shrinkage in the fiber and PyC interface components.

  3. 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

  4. Bone marrow dose estimates from work-related medical x-ray examinations given between 1943 and 1966 for personnel from five U.S. nuclear facilities.

    PubMed

    Anderson, Jeri L; Daniels, Robert D

    2006-06-01

    Inclusion of dose from work-related medical x-ray examinations with occupational external dose in an epidemiological study may reduce misclassification of exposures and provide more accurate assessment of leukemia risk from occupational exposure to ionizing radiation. In a multi-site leukemia case-control study, annual bone marrow doses due to work-related x-ray examinations given between 1943 and 1966 were estimated for cases and controls employed at five nuclear facilities. Only active bone marrow dose from photofluorographic chest and routine lumbar spine x rays were included. Bone marrow dose assigned for a single exposure ranged from 1.0 to 1.4 mGy. Mean and median cumulative bone marrow doses for each of the five sites from work-related x-ray examinations ranged from 2.0 to 14 mGy and 2.1 to 8.8 mGy, respectively. Results suggest that bone marrow dose from work-related photofluorographic and lumbar spine x-ray examinations given during the time period of this study may be significant compared to occupational bone marrow dose. PMID:16691102

  5. 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.

  6. 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. PMID:21199822

  7. 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. PMID:25717060

  8. 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

  9. 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.

  10. Post-irradiation cutaneous angiosarcoma.

    PubMed

    Mehta, Rohtesh S; Mikhail, Michael

    2008-01-01

    Angiosarcoma is a rare and highly malignant tumor with potential to recur despite treatment, and carries a poor prognosis. Previous radiation therapy and lymphedema are some of the known risk factors. We present a case of cutaneous angiosarcoma which occurred at lumpectomy site in a patient with a history of breast cancer and radiation to the breast. The tumor kept on recurring repetitively despite continual treatments, and the patient finally succumbed to the disease roughly four years after initial diagnosis. PMID:18925942

  11. 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.

  12. 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.

  13. 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.

  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. Post-irradiation annealing behavior of neutron-irradiated FeCu, FeMnNi and FeMnNiCu model alloys investigated by means of small-angle neutron scattering

    NASA Astrophysics Data System (ADS)

    Bergner, F.; Ulbricht, A.; Lindner, P.; Keiderling, U.; Malerba, L.

    2014-11-01

    Neutron irradiation of reactor pressure vessel steels gives rise to the formation of thermodynamically stable and unstable nano-features. The present work is focused on the stability of Cu-, Mn- and Ni-containing solute clusters in model alloys exposed to post-irradiation annealing. Fe0.1Cu, Fe1.2Mn0.7Ni and Fe1.2Mn0.7Ni0.1Cu (wt%) model alloys irradiated up to neutron exposures of 0.1 and 0.19 dpa (displacements per atom) were annealed at stepwise increasing temperatures in the range from 300 °C (i.e. near irradiation temperature) to 500 °C and characterized by means of small-angle neutron scattering (SANS). We have found characteristic differences in the annealing behavior of the alloys. In particular, there is a non-trivial (synergistic-antagonistic) interplay of Mn/Ni and Cu.

  16. The NGA-DOE grant to examine critical issues related to radioactive waste and materials disposition involving DOE facilities. Quarterly report, October 1--December 31, 1997

    SciTech Connect

    Beauchesne, A.M.

    1997-12-31

    Topics explored through this project include: decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; changes to the FFCA site treatment plans as a result of proposals in the EM 2006 cleanup plans and contractor integration analysis; interstate waste and materials shipments; and reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; and 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, DOE activities in the area of the Hazardous Waste Identification Rule, and DOE`s proposed National Dialogue.

  17. High-dose neutron irradiation of MgAl 2O 4 spinel: effects of post-irradiation thermal annealing on EPR and optical absorption

    NASA Astrophysics Data System (ADS)

    Ibarra, A.; Bravo, D.; Lopez, F. J.; Garner, F. A.

    2005-02-01

    Electron paramagnetic resonance (EPR) and optical absorption spectra were measured during thermal annealing of stoichiometric MgAl 2O 4 spinel that was previously irradiated in the Materials Open Test Assembly in the Fast Flux Test Facility (FFTF/MOTA) at ≈680 K to ≈50 dpa. Both F and F + centres are to persist up to very high temperatures (over 1000 K) suggesting the operation of an annealing mechanism controlled by the thermal stability of extended defects. Using X-ray irradiation following the different annealing steps it was shown that an optical absorption band at 37 000 cm -1 is related to a sharp EPR band at g = 2.0005 and that the defect causing these effects is the F + centre.

  18. Examination of criticality accident alarm coverage on the operating floors of the X-333, X-330, and X-326 facilities at the Portsmouth Gaseous Diffusion Plant

    SciTech Connect

    Lee, B.L. Jr.; Dobelbower, M.C.; Woollard, J.; Skapik, C.W.

    1996-01-01

    This report summarizes the results of an evaluation of Criticality Accident Alarm System (CAAS) coverage of the operating floors (first floors) of the X-333, X-330, and X-326 buildings. CAAS coverage of the process cell floors (second floors) has been evaluated in previous reports. Coverage of the roadways around the three processing buildings by the cell floor detectors in these buildings has also been verified in a previous report. In order to evaluate coverage, the facilities were modeled using the Monte Carlo N-Particle Transport Computer Code (MCNP). MCNP was then used to simulate criticality accidents at various locations throughout the operating floors of the buildings and the associated neutron flux at the current detector locations was calculated. The neutron flux was then converted to an absorbed dose rate (in tissue) and compared with the Portsmouth criticality accident alarm set-point of 5mrad/hr. The parameters defining the simulated criticality accidents have been calculated as ``the minimum accident of concern`` as defined in ANSI Standard ANS 8.3-1986. These calculations are documented in Portsmouth report number POEF-SH-31. The results of this evaluation indicate that the X-333 Operating Floor CAAS may not alarm in response to a minimum accident of concern. This is primarily because of shielding provided by the numerous concrete columns used to support the second floor of this building and the large distances between the CAAS detectors. Conversely, the results indicate that the X-326 and the X-330 CAAS systems would alarm in response to a minimum accident of concern occurring on the operating floors of these buildings. It should be noted that the cell floors in these two buildings are supported with steel I-beams instead of the concrete columns used in the X-333 building.

  19. 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

  20. 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.

  1. 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.

  2. 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 ...

  3. Handbook on Planning School Facilities.

    ERIC Educational Resources Information Center

    Clutter, Wayne, Comp.; Elswick, Bill, Comp.

    This guide details the development of a 10-year Comprehensive Educational Facilities Plan (CEFP), along with its components and governing regulations. Chapters examine the CEFP process and requirements in the following areas: educational facilities planning; site design; common facilities necessary for school operation; facilities for primary…

  4. 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.

  5. Ear examination

    MedlinePlus

    King EF, Couch ME. History, physical examination, and the preoperative evaluation. In: Flint PW, Haughey BH, Lund LJ, et al, eds. Cummings Otolaryngology: Head & Neck Surgery . 6th ed. Philadelphia, ...

  6. 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…

  7. [Examination procedures].

    PubMed

    Vassault, A; Arnaud, J; Szymanovicz, A

    2010-12-01

    Examination procedures have to be written for each examination according to the standard requirements. Using CE marked devices, technical inserts can be used, but because of their lack of homogeneity, it could be easier to document their use as a standard procedure. Document control policy applies for those procedures, the content of which could be as provided in this document. Electronic manuals can be used as well. PMID:21613016

  8. 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…

  9. 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

  10. Health Facilities

    MedlinePlus

    Health facilities are places that provide health care. They include hospitals, clinics, outpatient care centers, and specialized care centers, ... psychiatric care centers. When you choose a health facility, you might want to consider How close it ...

  11. RCRA FACILITIES

    EPA Science Inventory

    Points represent facilities that are regulated by the EPA under the Resource Conservation and Recovery Act (RCRA). Facilities regulated under RCRA generate, dispose of, treate or transport hazardous waste. RCRA is a law enacted by Congress in 1976 and amended in 1984 to include ...

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

    SciTech Connect

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

    2013-04-19

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

  13. Track and Field Facilities.

    ERIC Educational Resources Information Center

    Wood, Tony

    2001-01-01

    Discusses planning and design tips that help ensure track and field facilities are successful and well-suited to both school and community use. Examines approaches to determining the best track surface and ways to maximize track and field flexibility with limited space. (GR)

  14. 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 ...

  15. 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)

  16. Production facilities

    SciTech Connect

    Not Available

    1989-01-01

    This book presents a cross section of different solutions to the many unique production problems operators face. Sections address benefit vs. cost options for production facility designs, oil and gas separation processes and equipment, oil treating and desalting systems, and water treating methods and equipment. Papers were selected to give an overall view of factors involved in optimizing the design of cost-effective production facilities.

  17. 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…

  18. 38 CFR 13.2 - Field examinations.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 38 Pensions, Bonuses, and Veterans' Relief 1 2010-07-01 2010-07-01 false Field examinations. 13.2... ADMINISTRATION, FIDUCIARY ACTIVITIES § 13.2 Field examinations. (a) Authority to conduct; generally. Field... facility Director are authorized, when assigned, to conduct investigations (field examinations) and...

  19. 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.

  20. Planning Facilities.

    ERIC Educational Resources Information Center

    Flynn, Richard B., Ed.; And Others

    1983-01-01

    Nine articles give information to help make professionals in health, physical education, recreation, dance, and athletics more knowledgeable about planning facilities. Design of natatoriums, physical fitness laboratories, fitness trails, gymnasium lighting, homemade play equipment, indoor soccer arenas, and dance floors is considered. A…

  1. 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 a pressing…

  2. 10 CFR 55.46 - Simulation facilities.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Simulation facilities. 55.46 Section 55.46 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) OPERATORS' LICENSES Written Examinations and Operating Tests § 55.46 Simulation facilities. (a) General. This section addresses the use of a simulation facility for the administration of the operating test...

  3. 10 CFR 55.46 - Simulation facilities.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Simulation facilities. 55.46 Section 55.46 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) OPERATORS' LICENSES Written Examinations and Operating Tests § 55.46 Simulation facilities. (a) General. This section addresses the use of a simulation facility for the administration of the operating test...

  4. 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.

  5. 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.

  6. 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

  7. Lifelong Learning Facilities in Japan.

    ERIC Educational Resources Information Center

    Hirai, Akishige

    1997-01-01

    Examines Japan's educational system and the role of national policy and local government in fostering lifelong learning. Reasons why Japan is building a lifelong learning society are examined, as are the opportunities available in Japan for learning beyond traditional education, the national and local government's role, access to facilities,…

  8. 49 CFR 109.9 - Transportation for examination and analysis.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION HAZARDOUS MATERIALS AND OIL TRANSPORTATION DEPARTMENT... carrier to transport the package to a facility capable of conducting such examination and analysis....

  9. 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.

  10. 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.

  11. 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…

  12. 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.

  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. Carcinoma of the prostate: results of post-irradiation biopsy

    SciTech Connect

    Freiha, F.S.; Bagshaw, M.A.

    1984-01-01

    One hundred and forty-six patients with clinically localized carcinoma of the prostate were surgically staged and treated with external beam irradiation to the prostate and to the lymph node-bearing areas. Sixty-four (44%) of these patients had needle biopsy of the prostate 18 months or more following completion of therapy. Thirty-nine (61%) of the biopsies were interpreted as positive and 25 (39%) as negative. Twenty-eight (72%) of the 39 patients with a positive biopsy have subsequently developed metastases as compared to only 6 of 25 (24%) of the patients with a negative biopsy. It is concluded that an apparently positive postirradiation biopsy is likely to indicate active disease and identifies patients at a higher risk for development of metastases. Other details of staging, grading, and outcomes that compare these two groups are discussed.

  15. Examining 'risks' of overspecifying TMVs.

    PubMed

    Makin, Tom; Tench, Ken

    2014-05-01

    Dr. Tom Makin, a highly experienced microbiologist and former Directorate manager at the Department of Medical Microbiology at the Royal Liverpool University Hospital, and Ken Tench, compliance manager, Estates and Facilities Directorate, at Central Manchester University Hospitals NHS Foundation Trust, who has worked in operational estate functions since 1984, examine the widespread use of thermostatic mixing valves, or TMVs, in healthcare premises. They argue that such devices have, in recent years especially, been overspecified, particularly given the potential for increased contamination of the outlets, and the resulting heightened risk of spread of potentially life-threatening nosocomial waterborne diseases. PMID:24930184

  16. Materials and Fuels Complex Tour

    ScienceCinema

    Miley, Don

    2013-05-28

    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.

  17. 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.

  18. Patient Eye Examinations - Adults

    MedlinePlus

    ... Examinations, Adults Patient Eye Examinations, Children Refractive Errors Scientists in the Laboratory Visual Acuity Testing Patient Eye Examinations, Adults × Warning message Automatic fallback to the cURL connection method kicked in to handle the request. Result code ...

  19. 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

  20. The Association Between Dialysis Facility Quality and Facility Characteristics, Neighborhood Demographics, and Region.

    PubMed

    Zhang, Yue

    2016-07-01

    The Centers for Medicare & Medicaid Services (CMS) initiated the End-Stage Renal Disease Quality Incentive Program in 2012. For each dialysis facility, an overall quality performance score is determined based on various quality measures. This article studies the association between the overall dialysis facility quality and facility characteristics, neighborhood demographics, and region. Data from the CMS Payment Year 2014 Dialysis Compare File were used, and were linked to 2010 US Census data (n = 4086). Multiple linear regression was used to examine the association between dialysis facility quality and facility characteristics, neighborhood demographics, and region. The analysis demonstrates that dialysis facility quality varies significantly by facility profit status, chain membership, and facility size. Dialysis facilities in neighborhoods with a higher proportion of African Americans have significantly lower quality. Regional differences in quality exist. PMID:25838553

  1. 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…

  2. 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…

  3. 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…

  4. 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.

  5. R2 REGULATED FACILITIES

    EPA Science Inventory

    The Facility Registry System (FRS) is a centrally managed database that identifies facilities, sites or places subject to environmental regulations or of environmental interest. FRS creates high-quality, accurate, and authoritative facility identification records through rigorous...

  6. Wood's lamp examination

    MedlinePlus

    ... this page: //medlineplus.gov/ency/article/003386.htm Wood's lamp examination To use the sharing features on this page, please enable JavaScript. A Wood's lamp examination is a test that uses ultraviolet ( ...

  7. Wood's lamp examination

    MedlinePlus

    A Wood's lamp examination is a test that uses ultraviolet (UV) light to look at the skin closely. ... Gebhard RE. Wood's light examination. In: Pfenninger JL, Fowler GC, eds. ... Care . 3rd ed. Philadelphia, PA: Elsevier Mosby; 2010:chap ...

  8. The neurological examination.

    PubMed

    April, R S

    1995-06-01

    This chapter describes methods of clinical history taking and examination of the PLDD candidate with lumbar radicular symptoms. It stresses features of the classical neurological examination of the back and lower extremities in a concise, systematic fashion. PMID:10150641

  9. Wood's Lamp Examination

    MedlinePlus

    ... dermatologists to assist in the diagnosis of various pigment and infectious disorders. The examination is performed in ... lamp. If a fungal or bacterial infection or pigment disorder is present, Wood's lamp examination can strengthen ...

  10. Your Language Laboratory Facilities Present and Future.

    ERIC Educational Resources Information Center

    Theuma, Jean R.

    Rationale and facilities of the University of Hawaii's language laboratories are examined. The two-fold summary defines present (Fall 1968) and future (Fall 1969) needs, physical facilities, expected language enrollments, schedules, staff, services, research, experimentation, and planning. Also treated is the financial aspect of laboratory…

  11. 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…

  12. 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.…

  13. Guide for School Facility Appraisal. 1998 Edition.

    ERIC Educational Resources Information Center

    Hawkins, Harold L.; Lilley, H. Edward

    This guide provides a comprehensive method for measuring the quality and educational effectiveness of school facilities and may be used to perform a post-occupancy review; to formulate a formal record; to highlight specific appraisal needs; to examine the need for new facilities or renovations; or to serve as an instructional tool. Suggestions are…

  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 the test…

  15. Lighting Quantity and Quality in Educational Facilities.

    ERIC Educational Resources Information Center

    Elwazanim, Salim A.

    1998-01-01

    Discusses educational facility lighting management, and examines how light quantity, distribution, and quality-enhancement strategies can improve the indoor environment while reducing lighting costs. Informational tables provide lighting pattern, color, and illuminance data. (GR)

  16. 9 CFR 93.412 - Ruminant quarantine facilities.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    .... (1) The temporary inspection facility must have adequate space for Federal or State veterinarians to conduct examinations and testing of the imported ruminants. (2) The examination space of the temporary... space. The facility must have adequate space for APHIS representatives to conduct examinations and...

  17. 9 CFR 93.412 - Ruminant quarantine facilities.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    .... (1) The temporary inspection facility must have adequate space for Federal or State veterinarians to conduct examinations and testing of the imported ruminants. (2) The examination space of the temporary... space. The facility must have adequate space for APHIS representatives to conduct examinations and...

  18. 9 CFR 93.412 - Ruminant quarantine facilities.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    .... (1) The temporary inspection facility must have adequate space for Federal or State veterinarians to conduct examinations and testing of the imported ruminants. (2) The examination space of the temporary... space. The facility must have adequate space for APHIS representatives to conduct examinations and...

  19. 9 CFR 93.412 - Ruminant quarantine facilities.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    .... (1) The temporary inspection facility must have adequate space for Federal or State veterinarians to conduct examinations and testing of the imported ruminants. (2) The examination space of the temporary... space. The facility must have adequate space for APHIS representatives to conduct examinations and...

  20. 9 CFR 93.412 - Ruminant quarantine facilities.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    .... (1) The temporary inspection facility must have adequate space for Federal or State veterinarians to conduct examinations and testing of the imported ruminants. (2) The examination space of the temporary... space. The facility must have adequate space for APHIS representatives to conduct examinations and...

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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,…

  6. 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.

  7. 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. PMID:27583542

  8. Computer grading of examinations

    NASA Technical Reports Server (NTRS)

    Frigerio, N. A.

    1969-01-01

    A method, using IBM cards and computer processing, automates examination grading and recording and permits use of computational problems. The student generates his own answers, and the instructor has much greater freedom in writing questions than is possible with multiple choice examinations.

  9. Examination Syllabus Comparisons.

    ERIC Educational Resources Information Center

    Mallatratt, J. L.

    1983-01-01

    A study was conducted based on an analysis of computer study courses leading to CSE and 0-level examinations. Several findings are discussed and questions about future developments are raised. Syllabus content (including history, hardware, basic computer science, programming, applications, and implications), format, and examinations are among the…

  10. 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.

  11. 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

  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. 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.

  14. 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)

  15. The Educational Facilities Charrette

    ERIC Educational Resources Information Center

    Chase, William W.

    1970-01-01

    The deputy director for the Division of Facilities Development of the U.S. Office of Education discusses a technique for studying and resolving educational facilities development problems within the context of total community planning needs." (Author/AA)

  16. HAWAII NPDES MAJOR FACILITIES

    EPA Science Inventory

    Point coverage representing locations of NPDES facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from wastewater treatment facilities that discharge into waters of the US. Wastewater treatment facilitie...

  17. SAMOA NPDES MAJOR FACILITIES

    EPA Science Inventory

    Point coverage representing locations of NPDES facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from wastewater treatment facilities that discharge into waters of the US. Wastewater treatment facilitie...

  18. GUAM NPDES MAJOR FACILITIES

    EPA Science Inventory

    Point coverage representing locations of NPDES facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from wastewater treatment facilities that discharge into waters of the US. Wastewater treatment facilitie...

  19. ARIZONA NPDES MAJOR FACILITIES

    EPA Science Inventory

    Point coverage representing locations of NPDES facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from wastewater treatment facilities that discharge into waters of the US. Wastewater treatment facilitie...

  20. NEVADA NPDES MAJOR FACILITIES

    EPA Science Inventory

    Point coverage representing locations of NPDES facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from wastewater treatment facilities that discharge into waters of the US. Wastewater treatment facilitie...

  1. CALIFORNIA NPDES MAJOR FACILITIES

    EPA Science Inventory

    Point coverage representing locations of NPDES facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from wastewater treatment facilities that discharge into waters of the US. Wastewater treatment facilitie...

  2. 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.

  3. Genesis Preliminary Examination Plans

    NASA Technical Reports Server (NTRS)

    McNamara, K. M.; Stansbery, E. K.

    2004-01-01

    The purpose of preliminary examination of the Genesis sample collectors is to provide information on the condition and availability of collector materials to the science community as a basis for allocation requests. Similarly, the information will be used by the Genesis Sample Allocation sub-committee of CAPTEM to determine the optimum allocation scheme, and by the Genesis Curator to determine the processing sequence for allocation production. The plan includes a decision process and detailed examination and documentation protocol for whole arrays and individual collectors (wafers, concentrator targets, bulk metallic glass, gold foil, and polished aluminum). It also includes a plan for communicating the information obtained to the scientific community. The plan does not include a detailed plan for preliminary examination of the SRC lid foil collectors, the process for removal of individual collectors from their frames, or for the subsequent subdivision of collector materials for allocation.

  4. 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

  5. Florida Educational Facilities, 1998.

    ERIC Educational Resources Information Center

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

    This document contains information, photographs, and floor plans of many of Florida's new elementary through high school facilities occupied in 1998. Each entry lists the facility's type, building size, student capacity, and general structural information. Also provided is information on the facility's total construction cost; the architects and…

  6. Florida Educational Facilities, 1996.

    ERIC Educational Resources Information Center

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

    This document contains information, photographs, and floor plans of many of Florida's new elementary through high school facilities occupied in 1996. Each entry lists the facility's type, building size, student capacity, and general structural information. Also provided is information on the facility's total construction cost; the architects and…

  7. Florida Educational Facilities, 1997.

    ERIC Educational Resources Information Center

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

    This document contains information, photographs, and floor plans of many of Florida's new elementary through high school facilities occupied in 1997. Each entry lists the facility's type, building size, student capacity, and general structural information. Also provided is information on the facility's total construction cost; the architects and…

  8. 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

  9. 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.

  10. 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…