Hot Corrosion Test Facility at the NASA Lewis Special Projects Laboratory

Science.gov (United States)

Robinson, Raymond C.; Cuy, Michael D.

1994-01-01

The Hot Corrosion Test Facility (HCTF) at the NASA Lewis Special Projects Laboratory (SPL) is a high-velocity, pressurized burner rig currently used to evaluate the environmental durability of advanced ceramic materials such as SiC and Si3N4. The HCTF uses laboratory service air which is preheated, mixed with jet fuel, and ignited to simulate the conditions of a gas turbine engine. Air, fuel, and water systems are computer-controlled to maintain test conditions which include maximum air flows of 250 kg/hr (550 lbm/hr), pressures of 100-600 kPa (1-6 atm), and gas temperatures exceeding 1500 C (2732 F). The HCTF provides a relatively inexpensive, yet sophisticated means for researchers to study the high-temperature oxidation of advanced materials, and the injection of a salt solution provides the added capability of conducting hot corrosion studies.

Environmental Audit at Santa Barbara Operations, Special Technologies Laboratory, Remote Sensing Laboratory, North Las Vegas Facilities

International Nuclear Information System (INIS)

1991-03-01

This report documents the results of the Environmental Audit of selected facilities under the jurisdiction of the DOE Nevada Operations Office (NV) that are operated by EG and G Energy Measurements, Incorporated (EG and G/EM). The facilities included in this Audit are those of Santa Barbara Operation (SBO) at Goleta, California; the Special Technologies Laboratory (STL) at Santa Barbara, California; and Las Vegas Area Operations (LVAO) including the Remote Sensing Laboratory (RSL) at Nellis Air Force Base in Nevada, and the North Las Vegas Facilities (NLVF) at North Las Vegas, Nevada. The Environmental Audit was conducted by the US Department of Energy's (DOE) Office of Environmental Audit, commencing on January 28, 1991 and ending on February 15, 1991. The scope of the Audit was comprehensive, addressing environmental activities in the technical areas of air, surface water/drinking water, groundwater, waste management, toxic and chemical materials, quality assurance, radiation, inactive waste sites, and environmental management. Also assessed was compliance with applicable Federal, state, and local regulations and requirements; internal operating requirements; DOE Orders; and best management practices. 8 tabs

Special Analysis for Disposal of High-Concentration I-129 Waste in the Intermediate-Level Vaults at the E-Area Low-Level Waste Facility

Energy Technology Data Exchange (ETDEWEB)

Collard, L.B.

2000-09-26

This revision was prepared to address comments from DOE-SR that arose following publication of revision 0. This Special Analysis (SA) addresses disposal of wastes with high concentrations of I-129 in the Intermediate-Level (IL) Vaults at the operating, low-level radioactive waste disposal facility (the E-Area Low-Level Waste Facility or LLWF) on the Savannah River Site (SRS). This SA provides limits for disposal in the IL Vaults of high-concentration I-129 wastes, including activated carbon beds from the Effluent Treatment Facility (ETF), based on their measured, waste-specific Kds.

Special Analysis for Disposal of High-Concentration I-129 Waste in the Intermediate-Level Vaults at the E-Area Low-Level Waste Facility

International Nuclear Information System (INIS)

Collard, L.B.

2000-01-01

This revision was prepared to address comments from DOE-SR that arose following publication of revision 0. This Special Analysis (SA) addresses disposal of wastes with high concentrations of I-129 in the Intermediate-Level (IL) Vaults at the operating, low-level radioactive waste disposal facility (the E-Area Low-Level Waste Facility or LLWF) on the Savannah River Site (SRS). This SA provides limits for disposal in the IL Vaults of high-concentration I-129 wastes, including activated carbon beds from the Effluent Treatment Facility (ETF), based on their measured, waste-specific Kds

Special Education in Nigeria.

Science.gov (United States)

Abang, Theresa B.

1992-01-01

This article discusses the special education system in Nigeria, focusing on integration; training of special educators; medical, health, and welfare services for children with disabilities; recreational facilities; employment opportunities; national planning; and problems and successes. (JDD)

Trends in Special Library Buildings.

Science.gov (United States)

Cohen, Elaine; Cohen, Aaron

1987-01-01

Examines special library facilities, noting impact of organizational structure, and discusses the concept of information resources management in this context. Development of online and telecommunications systems, corporate and government campuses, and special library systems are identified as reasons for growth of special libraries. Furniture and…

Annual report on strategic special nuclear material inventory differences

International Nuclear Information System (INIS)

1991-01-01

This report of unclassified Inventory Difference (ID's) covers the twelve months from April 1, 1989 through March 31, 1990 for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear material. Classified information is not included in this report. This classified information includes data for the Rocky Flats and Y-12 nuclear weapons production facilities or facilities under ID investigation. However, classified ID data from such facilities receive the same scrutiny and analyses was the included data. The data in this report have been prepared and reviewed by DOE contractors, field offices, and Headquarters. When necessary, special investigations have been performed in addition to these reviews: This ID data, explanations, reviews, and any additional special investigations, together with the absence of physical indications of any theft attempt, support a finding that no theft or diversion of significant quantities of strategic special nuclear material has occurred in DOE facilities during the twelve-month period covered by this report

Maintenance facilities, stores and records

International Nuclear Information System (INIS)

Fischer, K.

1986-01-01

The topics of this report are: on-site or off-site facilities. On-site facilities: workshops and special facilities. KWU's Service Center, a typical off-site supporting facility in Germany, capabilities and activities. A pool for special tools and equipment: devices for plugging of nozzles, for handling of RPU-studs and RPU internals etc. Devices for and management of radiological protection on-site for typical outage work. Spare parts and spare part management on site, typical examples. KWU's centralized spare part pools for components, generators and turbines etc. A computerized system for spare parts storage and maintenance planning. A system for mutual exchange of operational experience with respect to maintenance and repair activities. Systematic evaluation of failures and statistical results. (orig./GL)

Problems of development and putting into education process an electronic textbook on special discipline 'General theory and construction of heat-and-power engineering facilities'

International Nuclear Information System (INIS)

Karitskaya, S.G.; Ruzanov, K.A.; Davletov, V.S.

2005-01-01

The results of work of making the electronic textbook of special discipline ('General theory and construction of heat-and-power engineering facilities' are brought. The principles and requirements, presented towards literature of such type, are outlined. (author)

The 'SILOE' reactor at Grenoble, France and associated hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the SILOE reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

The 'OSIRIS' reactor at Saclay, France and available hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the OSIRIS reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

Interim report on the special research project 'exposure to environmental radiation due to nuclear facilities'

International Nuclear Information System (INIS)

1981-03-01

This special research project was started in 1978 as five-year plan. The purposes are to clarify the aspect of radiation exposure in human bodies due to the radioactive substances brought into the environment regarding the utilization of atomic energy, its mechanism and various factors affecting it, and to contribute to the evaluation of exposure dose, the reduction of radiation exposure, the conditions of locating nuclear facilities and the improvement of the method of disposing radioactive wastes. In addition to the fields treated in the previous special research project, the experimental research concerning the metabolism of environmental radioactive nuclides in bodies, namely the problem of the peculiarity of radioactive nuclide kinetics in infants and fetuses different from adults and the possibility of causing the changes in the intake and metabolism of nuclides in foods by the difference in their states of existence, was newly included. Also the research concerning the method of evaluating the absorbed dose in human organs at the time of irradiation outside and inside bodies in a new subject. Accordingly, this special research project is composed of (1) the research concerning the radionuclide kinetics in the environment, (2) the research concerning the radionuclide kinetics in bodies, (3) the research concerning the measurement and evaluation of dose absorbed in internal organs due to environmental radiation, and (4) the research concerning the monitoring of low level environmental radiation. The results obtained so far are reported. (Kako, I.)

The Education of Children with Special Needs in Ghana: Policies ...

African Journals Online (AJOL)

The results indicate that some policies have been put in place in the country regarding the education of special needs children. The main facilities that exist for children with special needs are in the areas of visual impairment, hearing impairment and mental retardation. No special facilities or services exist for the gifted, the ...

Results of Surveys for Special Status Reptiles at the Site 300 Facilities of Lawrence Livermore National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Woollett, J J

2008-09-18

The purpose of this report is to present the results of a live-trapping and visual surveys for special status reptiles at the Site 300 Facilities of Lawrence Livermore National Laboratory (LLNL). The survey was conducted under the authority of the Federal recovery permit of Swaim Biological Consulting (PRT-815537) and a Memorandum of Understanding issued from the California Department of Fish and Game. Site 300 is located between Livermore and Tracy just north of Tesla road (Alameda County) and Corral Hollow Road (San Joaquin County) and straddles the Alameda and San Joaquin County line (Figures 1 and 2). It encompasses portions of the USGS 7.5 minute Midway and Tracy quadrangles (Figure 2). Focused surveys were conducted for four special status reptiles including the Alameda whipsnake (Masticophis lateralis euryxanthus), the San Joaquin Whipsnake (Masticophis Hagellum ruddock), the silvery legless lizard (Anniella pulchra pulchra), and the California horned lizard (Phrynosoma coronanum frontale).

Facility of aerosol filtration

Energy Technology Data Exchange (ETDEWEB)

Duverger de Cuy, G; Regnier, J

1975-04-18

Said invention relates to a facility of aerosol filtration, particularly of sodium aerosols. Said facility is of special interest for fast reactors where sodium fires involve the possibility of high concentrations of sodium aerosols which soon clog up conventional filters. The facility intended for continuous operation, includes at the pre-filtering stage, means for increasing the size of the aerosol particles and separating clustered particles (cyclone separator).

The DIDO-reactor at Harwell, U.K. and ancillary hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the DIDO reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

Estimation methods for special nuclear materials holdup

International Nuclear Information System (INIS)

Pillay, K.K.S.; Picard, R.R.

1984-01-01

The potential value of statistical models for the estimation of residual inventories of special nuclear materials was examined using holdup data from processing facilities and through controlled experiments. Although the measurement of hidden inventories of special nuclear materials in large facilities is a challenging task, reliable estimates of these inventories can be developed through a combination of good measurements and the use of statistical models. 7 references, 5 figures

Design, Evaluation and Test Technology Facility

Data.gov (United States)

Federal Laboratory Consortium — The mission of this facility, which is composed of numerous specialized facilities, is to provide capabilities to simulate a wide range of environments for component...

The 'MELUSINE' reactor at Grenoble, France, and associated hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the MELUSINE reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities and specialized irradiation devices (loops and capsules). The information is presented in the form of six information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities

The DR 3 reactor at Risoe, Denmark and its associated hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the DR 2 reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of seven information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

Specialized computer architectures for computational aerodynamics

Science.gov (United States)

Stevenson, D. K.

1978-01-01

In recent years, computational fluid dynamics has made significant progress in modelling aerodynamic phenomena. Currently, one of the major barriers to future development lies in the compute-intensive nature of the numerical formulations and the relative high cost of performing these computations on commercially available general purpose computers, a cost high with respect to dollar expenditure and/or elapsed time. Today's computing technology will support a program designed to create specialized computing facilities to be dedicated to the important problems of computational aerodynamics. One of the still unresolved questions is the organization of the computing components in such a facility. The characteristics of fluid dynamic problems which will have significant impact on the choice of computer architecture for a specialized facility are reviewed.

10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.

Science.gov (United States)

2010-01-01

... postulated accidents that could lead to loss of safety functions. (5) Chemical protection. The design must... 10 Energy 2 2010-01-01 2010-01-01 false Requirements for new facilities or new processes at... Critical Mass of Special Nuclear Material § 70.64 Requirements for new facilities or new processes at...

Composite Structures Manufacturing Facility

Data.gov (United States)

Federal Laboratory Consortium — The Composite Structures Manufacturing Facility specializes in the design, analysis, fabrication and testing of advanced composite structures and materials for both...

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

International Nuclear Information System (INIS)

Goldberg, H.J.

1998-01-01

The Waste Receiving and Processing (WRAP) Facility will store uranium and transuranic (TRU) sources and standards for certification that WRAP meets the requirements of the Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP). In addition, WRAP must meet internal requirements for testing and validation of measuring instruments for nondestructive assay (NDA). In order to be certified for WIPP, WRAP will participate in the NDA Performance Demonstration Program (PDP). This program is a blind test of the NDA capabilities for TRU waste. It is intended to ensure that the NDA capabilities of this facility satisfy the requirements of the quality assurance program plan for the WIPP. The PDP standards have been provided by the Los Alamos National Laboratory (LANL) for this program. These standards will be used in the WRAP facility. To internally check the accuracy and sensitivity of the NDA instruments, a further set of sources and standards will also be used by the facility. Each sealed source or standard will be referred to herein as a unit. Various combinations of these units will be placed in test drums and/or boxes which will be subject to their own limits until unloaded. There will be two sealed test drums with five grams of weapons grade plutonium loaded in them. These drums will be appropriately marked and will be subject to the unit limits rather than the drum limits. This analysis shows that the storage and use of special nuclear material sources and standards within the limited control facility of WRAP (Rooms 101 and 104) is safe from a criticality standpoint. With the form, geometry, and masses involved with this evaluation, a criticality is not possible. The limits given in Section 2 should be imposed on facility operations

26 CFR 1.141-7 - Special rules for output facilities.

Science.gov (United States)

2010-04-01

.... (b) Definitions. For purposes of this section and § 1.141-8, the following definitions and rules... legislature in State X to own and operate certain power generating facilities, sells all of the power from its... generation, transmission and distribution facilities. In 2003, D transfers operating control of its...

Special emission measurements on Riley Stoker's advanced CFB pilot facility co-firing non-recyclable de-inking paper fiber and high sulfur eastern bituminous coal

International Nuclear Information System (INIS)

Dixit, V.B.; Mongeon, R.K.; Reicker, E.L.

1993-01-01

Riley Stoker has developed advanced industrial CFB designs that utilize eastern bituminous coals as fuel, and have the potential to use coal in combination with other fuels. Various fiber waste streams in paper recycling processes have sufficient carbonaceous content to be considered as possible sources of such fuels that could fire FBC combustors. The American Paper Institute estimates that by the mid-1990's more than 40% of the waste paper will be recycled, reaching much higher numbers by the year 2000. To evaluate the effectiveness of co-firing such fuels, a test program was conducted on Riley's pilot-scale circulating fluidized bed test facility. A de-inked newsprint derived fiber waste was successfully co-fired with high sulfur coal. The waste fiber material containing approximately 50% moisture had a heating value of 3500 Btu/lb. The coal was strip-mined and contained a lot of clay and excessive quantities of fines making it difficult to burn in conventional boilers. Tests were also conducted with a combination fuel consisting of coal, fiber waste and a high carbon fly ash. In addition to obtaining performance data on combustion efficiency, sulfur capture, and NO x emissions, special emission measurements were also made to quantify the organics, trace metals and hydrochloric acid levels in the flue gas. The co-firing tests achieved a maximum combustion efficiency of 98% and sulfur capture of 90%. The effect of Ca/S mole ratio and temperature is discussed. Although there are no formal regulations in place for FBC systems regarding special emissions, the levels measured were far below the allowable limits for waste incinerators. Materials handling experience on the pilot facility relating to co-firing is also discussed. This is done to identify special considerations for designing commercial facilities. A brief overview of the de-inking waste fiber combustion market is also presented

The future IKO-PION-MUON-facility

International Nuclear Information System (INIS)

Goudsmit, P.F.A.; Arnold, H.; Dantzig, R. van; Konijn, J.

1975-09-01

Information is given on the pion and muon physics facility planned at the Institute for Nuclear Physics Research (IKO) with special notice of the fluxes of pions and muons expected at this facility, as well as on the structure of these secondary beams

The FRJ 1 reactor (MERLIN) at Juelich, F.R. Germany and associated hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the FRJ 1 reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

The FR 2 reactor at Karlsruhe, F.R. Germany and associated hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the FR 2 reactor and associated hot cell facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

Electronic Warfare Signature Measurement Facility

Data.gov (United States)

Federal Laboratory Consortium — The Electronic Warfare Signature Measurement Facility contains specialized mobile spectral, radiometric, and imaging measurement systems to characterize ultraviolet,...

National Low-Temperature Neutron-Irradiation Facility

International Nuclear Information System (INIS)

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

1983-08-01

The Materials Sciences Division of the United States Department of Energy will establish a National Low Temperature Neutron Irradiation Facility (NLTNIF) which will utilize the Bulk Shielding Reactor (BSR) located at Oak Ridge National Laboratory. The facility will provide high radiation intensities and special environmental and testing conditions for qualified experiments at no cost to users. This report describes the planned experimental capabilities of the new facility

DeBeNe Test Facilities for Fast Breeder Development

International Nuclear Information System (INIS)

Storz, R.

1980-10-01

This report gives an overview and a short description of the test facilities constructed and operated within the collaboration for fast breeder development in Germany, Belgium and the Netherlands. The facilities are grouped into Sodium Loops (Large Facilities and Laboratory Loops), Special Equipment including Hot Cells and Reprocessing, Test Facilities without Sodium, Zero Power Facilities and In-pile Loops including Irradiation Facilities

Evaluation of the quality of foods for special diets produced in a school catering facility within a HACCP-based approach: a case study.

Science.gov (United States)

Petruzzelli, Annalisa; Foglini, Martina; Paolini, Francesca; Framboas, Marisa; Serena Altissimi, M; Naceur Haouet, M; Mangili, Piermario; Osimani, Andrea; Clementi, Francesca; Cenci, Telemaco; Tonucci, Franco

2014-01-01

A study was carried out to verify the appropriateness of the Hazard Analysis and Critical Control Point (HACCP) plan adopted in a school catering facility. To that end, the microbiological quality of foods, the correct implementation of special diets (lactose- and gluten-free) and the nutritional value of foods were assessed. Thirty-six samples of lactose-free and 87 samples of gluten-free special diet food preparations were subjected to microbiological, chemical, and nutritional analyses. The data collected demonstrate the effectiveness of the HACCP plan in reducing the occurrence of microbial and chemical (lactose and gluten) cross-contamination. The data obtained from the nutritional analyses showed that the dietary intake provided by the meals under study was satisfactory.

Report on strategic special nuclear material inventory differences

International Nuclear Information System (INIS)

1977-08-01

Information concerning accounting for significant quantities of strategic special nuclear material (SSNM) in ERDA facilities is reported. Inventory difference data are provided for fiscal year 1976 for ERDA and ERDA contractor facilities that possessed significant quantities of SSNM

ANALYSIS OF SPECIAL WASTE CONFIGURATIONS AT THE SRS WASTE MANAGEMENT FACILITIES

International Nuclear Information System (INIS)

Casella, V; Raymond Dewberry, R

2007-01-01

Job Control Waste (JCW) at the Savannah River Site (SRS) Solid Waste Management Facilities (SWMF) may be disposed of in special containers, and the analysis of these containers requires developing specific analysis methodologies. A method has been developed for the routine assay of prohibited items (liquids, etc.) contained in a 30-gallon drum that is then placed into a 55-gallon drum. Method development consisted of system calibration with a NIST standard at various drum-to-detector distances, method verification with a liquid sample containing a known amount of Pu-238, and modeling the inner container using Ortec Isotopic software. Using this method for measurement of the known standard in the drum-in-drum configuration produced excellent agreement (within 15%) with the known value. Savannah River Site Solid Waste Management also requested analysis of waste contained in large black boxes (commonly 18-feet x 12-feet x 7-feet) stored at the SWMF. These boxes are frequently stored in high background areas and background radiation must be considered for each analysis. A detection limit of less than 150 fissile-gram-equivalents (FGE) of TRU waste is required for the black-box analyses. There is usually excellent agreement for the measurements at different distances and measurement uncertainties of about 50% are obtained at distances of at least twenty feet from the box. This paper discusses the experimental setup, analysis and data evaluation for drum-in-drum and black box waste configurations at SRS

Automation in a material processing/storage facility

International Nuclear Information System (INIS)

Peterson, K.; Gordon, J.

1997-01-01

The Savannah River Site (SRS) is currently developing a new facility, the Actinide Packaging and Storage Facility (APSF), to process and store legacy materials from the United States nuclear stockpile. A variety of materials, with a variety of properties, packaging and handling/storage requirements, will be processed and stored at the facility. Since these materials are hazardous and radioactive, automation will be used to minimize worker exposure. Other benefits derived from automation of the facility include increased throughput capacity and enhanced security. The diversity of materials and packaging geometries to be handled poses challenges to the automation of facility processes. In addition, the nature of the materials to be processed underscores the need for safety, reliability and serviceability. The application of automation in this facility must, therefore, be accomplished in a rational and disciplined manner to satisfy the strict operational requirements of the facility. Among the functions to be automated are the transport of containers between process and storage areas via an Automatic Guided Vehicle (AGV), and various processes in the Shipping Package Unpackaging (SPU) area, the Accountability Measurements (AM) area, the Special Isotope Storage (SIS) vault and the Special Nuclear Materials (SNM) vault. Other areas of the facility are also being automated, but are outside the scope of this paper

Nondestructive assay of special nuclear material for uranium fuel-fabrication facilities

International Nuclear Information System (INIS)

Smith, H.A. Jr.; Schillebeeckx, P.

1997-01-01

A high-quality materials accounting system and effective international inspections in uranium fuel-fabrication facilities depend heavily upon accurate nondestructive assay measurements of the facility's nuclear materials. While item accounting can monitor a large portion of the facility inventory (fuel rods, assemblies, storage items), the contents of all such items and mass values for all bulk materials must be based on quantitative measurements. Weight measurements, combined with destructive analysis of process samples, can provide highly accurate quantitative information on well-characterized and uniform product materials. However, to cover the full range of process materials and to provide timely accountancy data on hard-to-measure items and rapid verification of previous measurements, radiation-based nondestructive assay (NDA) techniques play an important role. NDA for uranium fuel fabrication facilities relies on passive gamma spectroscopy for enrichment and U isotope mass values of medium-to-low-density samples and holdup deposits; it relies on active neutron techniques for U-235 mass values of high-density and heterogeneous samples. This paper will describe the basic radiation-based nondestructive assay techniques used to perform these measurements. The authors will also discuss the NDA measurement applications for international inspections of European fuel-fabrication facilities

Agency Data on User Facilities

Data.gov (United States)

National Aeronautics and Space Administration — The purpose of the Aerospace Technical Facility Inventory is to facilitate the sharing of specialized capabilities within the aerospace research/engineering...

Dry Well Storage Facility conceptual design study

International Nuclear Information System (INIS)

1979-02-01

The Dry Well Storage Facility described is assumed to be located adjacent to or near a Spent Fuel Receiving and Packaging Facility and/or a Packaged Fuel Transfer Facility. Performance requirements, quality levels and codes and standards, schedule and methods of performance, special requirements, quality assurance program, and cost estimate are discussed. Appendices on major mechanical equipment and electric power requirements are included

Dry Well Storage Facility conceptual design study

Energy Technology Data Exchange (ETDEWEB)

1979-02-01

The Dry Well Storage Facility described is assumed to be located adjacent to or near a Spent Fuel Receiving and Packaging Facility and/or a Packaged Fuel Transfer Facility. Performance requirements, quality levels and codes and standards, schedule and methods of performance, special requirements, quality assurance program, and cost estimate are discussed. Appendices on major mechanical equipment and electric power requirements are included.

Fast Flux Test Facility (FFTF) maintenance provisions

International Nuclear Information System (INIS)

Marshall, J.L.

1981-05-01

The Fast Flux Test Facility (FFTF) was designed with maintainability as a primary parameter, and facilities and provisions were designed into the plant to accommodate the maintenance function. This paper describes the FFTF and its systems. Special maintenance equipment and facilities for performing maintenance on radioactive components are discussed. Maintenance provisions designed into the plant to enhance maintainability are also described

Legal regime of water management facilities

Directory of Open Access Journals (Sweden)

Salma Jožef

2013-01-01

Full Text Available The paper analyzes the legal regime of water management facilities in the light of Serbian, foreign and European law. Different divisions of water management facilities are carried out (to public and private ones, natural and artificial ones, etc., with determination of their legal relevance. Account is taken of the issue of protection from harmful effects of waters to such facilities, as well. The paper points also to rules on the water management facilities, from acts of planning, to individual administrative acts and measures for maintenance of required qualitative and quantitative condition of waters, depending on their purpose (general use or special, commercial use o waters. Albeit special rules on water management facilities exist, due to the natural interlocking between all the components of the environment (water, air and soil, a comprehensive approach is required. A reference is made to other basic principles of protection of water management facilities as well, such as the principle of prevention, principle of sustainable development and the principle "polluter pays". The last one represents the achievement of contemporary law, which deviates from the idea accepted in the second half of 20th century that supported the socialization of risk from harmful effects of waters.

77 FR 60482 - Regulatory Guide 5.67, Material Control and Accounting for Uranium Enrichment Facilities...

Science.gov (United States)

2012-10-03

... Accounting for Uranium Enrichment Facilities Authorized To Produce Special Nuclear Material of Low Strategic... Accounting for Uranium Enrichment Facilities Authorized to Produce Special Nuclear Material of Low Strategic... and is applicable to the Paducah GDP and other uranium enrichment facilities that have been licensed...

SHIVA Nd: glass disk-amplifier-assembly facility and special purpose fixtures

International Nuclear Information System (INIS)

Jones, W.A.; Patton, H.G.; Stowers, I.F.; Wentworth, D.E.

1977-09-01

The facility built to assemble and maintain the laser amplifiers in the SHIVA Laser System is described. The facility is a Class-100 clean room which includes a high pressure solvent spray box, optical inspection equipment, and several unique amplifier-assembly fixtures

Decree of the Czechoslovak Atomic Energy Commission No. 191/1989 on procedures, terms and conditions for examining special professional qualification and competence of selected nuclear facility personnel

International Nuclear Information System (INIS)

1995-01-01

The procedures, terms and conditions for examining special professional competence of selected nuclear facility personnel are specified, including conditions for professional training and for issuing licenses qualifying the personnel for their work. Nuclear safety-related jobs at nuclear facilities are listed. Professional licenses with a two-year term of validity are granted by the Czechoslovak Atomic Energy Agency (CSAEC) to candidates who have passed examination before the State Examination Commission. Personnel training may only be performed by bodies authorized for that by the CSAEC. The Decree entered into force on 1 January 1990. (J.B.)

Fusion Materials Irradiation Test Facility: a facility for fusion-materials qualification

International Nuclear Information System (INIS)

Trego, A.L.; Hagan, J.W.; Opperman, E.K.; Burke, R.J.

1983-01-01

The Fusion Materials Irradiation Test Facility will provide a unique testing environment for irradiation of structural and special purpose materials in support of fusion power systems. The neutron source will be produced by a deuteron-lithium stripping reaction to generate high energy neutrons to ensure damage similar to that of a deuterium-tritium neutron spectrum. The facility design is now ready for the start of construction and much of the supporting lithium system research has been completed. Major testing of key low energy end components of the accelerator is about to commence. The facility, its testing role, and the status and major aspects of its design and supporting system development are described

New facilities of the ECN hot cell laboratory

International Nuclear Information System (INIS)

Duijves, K.A.; Konings, R.J.M.

1996-04-01

A description is given of two recent expansions of the ECN Hot Cell Laboratory in Petten; a production facility for molybdenum-99 and an actinide laboratory, a special facility to investigate unirradiated alpha- and beta-active samples. (orig.)

Licensed fuel facility status report: Inventory difference data, January 1988--June 1988

International Nuclear Information System (INIS)

1989-03-01

NRC is committed to the periodic publication of licensed fuel facilities' inventory difference data, after Agency review of the information and completion of any related investigations. Information in this report includes inventory difference data for active fuel fabrication facilities possessing more than (i) one effective kilogram of special nuclear material of low strategic significance, (ii) one effective kilogram of special nuclear material of moderate strategic significance, (iii) one effective kilogram of strategic special nuclear material contained in irradiated fuel reprocessing operations, or (iv) five formula kilograms of strategic special nuclear material

Cryogenic test facility at VECC, Kolkata

International Nuclear Information System (INIS)

Sarkar, Amit; Bhunia, Uttam; Pradhan, J.; Sur, A.; Bhandari, R.K.; Ranganathan, R.

2003-01-01

In view of proposed K-500 superconducting cyclotron project, cryogenic test facility has been set up at the centre. The facility can broadly be categorized into two- a small scale test facility and a large scale test facility. This facility has been utilized for the calibration of liquid helium level probe, cryogenic temperature probe, and I-B plot for a 7 T superconducting magnet. Spiral-shaped superconducting short sample with specific dimension and specially designed stainless steel sample holder has already been developed for the electrical characterisation. The 1/5 th model superconducting coil along with its quench detection circuit and dump resistor has also been developed

40 CFR 264.230 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Surface Impoundments § 264.230 Special requirements for incompatible wastes... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.230 Section 264.230 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

Special protective concretes

International Nuclear Information System (INIS)

Bouniol, P.

2001-01-01

Concrete is the most convenient material when large-scale radiation protection is needed. Thus, special concretes for nuclear purposes are used in various facilities like reactors, reprocessing centers, storage sites, accelerators, hospitals with nuclear medicine equipment, food ionization centers etc.. The recent advances made in civil engineering for the improvement of concrete durability and compactness are for a large part transposable to protection concretes. This article presents the basic knowledge about protection concretes with the associated typological and technological aspects. A large part is devoted to the intrinsic properties of concretes and to their behaviour in irradiation and temperature conditions: 1 - definition and field of application of special protective concretes; 2 - evolution of concepts and technologies (durability of structures, techniques of formulation, new additives, market evolution); 3 - design of protective structures (preliminary study, radiation characteristics, thermal constraints, damping and dimensioning, mechanical criteria); 4 - formulation of special concretes (general principles, granulates, hydraulic binders, pulverulent additives, water/cement ratio, reference composition of some special concretes); 5 - properties of special concretes (damping and thermo-mechanical properties); 6 - induced-irradiation and temperature phenomena (activation, radiolysis, mineralogical transformations, drying, shrinking, creep, corrosion of reinforcement). (J.S.)

Special Analysis: Updated Analysis of the Effect of Wood Products on Trench Disposal Limits at the E-Area Low-Level Waste Facility

International Nuclear Information System (INIS)

Cook, J.R.

2001-01-01

This Special Analysis (SA) develops revised radionuclide inventory limits for trench disposal of low-level radioactive waste in the presence of wood products in the E-Area Low-Level Waste Facility. These limits should be used to modify the Waste Acceptance Criteria (WAC) for trench disposal. Because the work on which this SA is based employed data from tests using 100 percent wood products, the 40 percent limitation on wood products for trench (i.e., slit or engineered trench) disposal is not needed in the modified WAC

40 CFR 264.199 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Tank Systems § 264.199 Special requirements for incompatible wastes. (a) Incompatible... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.199 Section 264.199 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 264.257 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Waste Piles § 264.257 Special requirements for incompatible wastes. (a) Incompatible... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.257 Section 264.257 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 265.313 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

..., STORAGE, AND DISPOSAL FACILITIES Landfills § 265.313 Special requirements for incompatible wastes... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 265.313 Section 265.313 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 265.282 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

..., STORAGE, AND DISPOSAL FACILITIES Land Treatment § 265.282 Special requirements for incompatible wastes... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 265.282 Section 265.282 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 264.313 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Landfills § 264.313 Special requirements for incompatible wastes. Incompatible wastes... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.313 Section 264.313 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 265.315 - Special requirements for containers.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for containers..., STORAGE, AND DISPOSAL FACILITIES Landfills § 265.315 Special requirements for containers. Unless they are very small, such as an ampule, containers must be either: (a) At least 90 percent full when placed in...

40 CFR 264.315 - Special requirements for containers.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for containers... FACILITIES Landfills § 264.315 Special requirements for containers. Unless they are very small, such as an ampule, containers must be either: (a) At least 90 percent full when placed in the landfill; or (b...

Establishing the NeuroRecovery Network Community Fitness and Wellness facilities: multi-site fitness facilities provide activity-based interventions and assessments for evidence-based functional gains in neurologic disorders.

Science.gov (United States)

Tolle, Heather; Rapacz, Andrew; Weintraub, Barry; Shogren, Carrie; Harkema, Susan J; Gibson, Jeremy L

2017-08-17

Physical fitness is a necessity for those living with a spinal cord injury, yet access to fitness facilities, equipment, and specially trained fitness experts are limited. This article introduces the concept of a network of fitness facilities specially geared towards individuals with spinal cord injury and other neurological disorders. The Community Fitness and Wellness branch of the NeuroRecovery Network was created to provide a continuum of care after traditional rehabilitation for individuals living with a spinal cord injury and other neurological disorders. Community Fitness and Wellness facilities translate activity-based interventions performed during rehabilitation into a community setting as well as provide other fitness and wellness opportunities. Community Fitness and Wellness facilities are staffed by professionals with training on the specialized needs of individuals living with spinal cord injury or other neurological disorders. Standardized assessments evaluate functional, health, and quality of life gains at regular intervals. A national database gathers information on standardized interventions and assessment outcomes providing a mechanism for evaluation of interventions performed in the community setting. The establishment of Community Fitness and Wellness facilities allows for the quick translation and evaluation of novel, effective approaches from research to individuals in the community. Implications for Rehabilitation Fitness needs of individuals with spinal cord injury living in the community necessitate the use of special equipment and trained staff. Community Fitness and Wellness Programs offer specially trained staff and adaptive equipment providing a continuity of care for those with spinal cord injuries and other neurological disorders.

Building Design Guidelines for Interior Architecture Concerned with Animal Researches Facilities

International Nuclear Information System (INIS)

ElDib, A.A. E.

2014-01-01

This paper discusses the most important design guidelines elements and characteristics for animal facilities, in order to achieve and maintain highest efficiency can be, with respect to the pivot role of Interior Architecture as one of the accurate specializations for completing the Architectural Sciences, for designer/s concerned with those types of facilities, (specially those using radioactive materials). These building types known as vivariums, are specially designed, accommodating and having sophisticated controlled environments for the care and maintenance of experimental animals, and are related to, but distinct from other research laboratories premises

21 CFR 58.43 - Animal care facilities.

Science.gov (United States)

2010-04-01

... testing facility shall have a sufficient number of animal rooms or areas, as needed, to assure proper: (1... (4) routine or specialized housing of animals. (b) A testing facility shall have a number of animal... shall exist for the collection and disposal of all animal waste and refuse or for safe sanitary storage...

40 CFR 264.177 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Use and Management of Containers § 264.177 Special requirements for incompatible wastes... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.177 Section 264.177 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 265.199 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

..., STORAGE, AND DISPOSAL FACILITIES Tank Systems § 265.199 Special requirements for incompatible wastes. (a... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 265.199 Section 265.199 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 265.257 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

..., STORAGE, AND DISPOSAL FACILITIES Waste Piles § 265.257 Special requirements for incompatible wastes. (a... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 265.257 Section 265.257 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

40 CFR 264.282 - Special requirements for incompatible wastes.

Science.gov (United States)

2010-07-01

... DISPOSAL FACILITIES Land Treatment § 264.282 Special requirements for incompatible wastes. The owner or... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for incompatible wastes. 264.282 Section 264.282 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...

42 CFR 488.60 - Special procedures for approving end stage renal disease facilities.

Science.gov (United States)

2010-10-01

... of the Public Health Service concerning the facility's contribution to the ESRD services of the network. (3) Data concerning the facility's compliance with professional norms and standards. (4) Data pertaining to the facility's qualifications for approval or for any expansion of services. (b) Determining...

36 CFR 702.12 - Space for meetings and special events.

Science.gov (United States)

2010-07-01

... special events. 702.12 Section 702.12 Parks, Forests, and Public Property LIBRARY OF CONGRESS CONDUCT ON LIBRARY PREMISES § 702.12 Space for meetings and special events. Information about the use of space for meeting and special events at the Library can be found at http://www.loc.gov/about/facilities/index.html...

Next generation storage facility

International Nuclear Information System (INIS)

Schlesser, J.A.

1994-01-01

With diminishing requirements for plutonium, a substantial quantity of this material requires special handling and ultimately, long-term storage. To meet this objective, we at Los Alamos, have been involved in the design of a storage facility with the goal of providing storage capabilities for this and other nuclear materials. This paper presents preliminary basic design data, not for the structure and physical plant, but for the container and arrays which might be configured within the facility, with strong emphasis on criticality safety features

Criteria for cesium capsules to be shipped as special form radioactive material

International Nuclear Information System (INIS)

Lundeen, J.E.

1994-01-01

The purpose of this report is to compile all the documentation which defines the criteria for Waste Encapsulation and Storage Facility (WESF) cesium capsules at the IOTECH facility and Applied Radiant Energy Corporation (ARECO) to be shipped as special form radioactive material in the Beneficial Uses Shipping System (BUSS) Cask. The capsules were originally approved as special form in 1975, but in 1988 the integrity of the capsules came into question. WHC developed the Pre-shipment Acceptance Test Criteria for capsules to meet in order to be shipped as special form material. The Department of Energy approved the criteria and directed WHC to ship the capsules at IOTECH and ARECO meeting this criteria to WHC as special form material

Anesthetic equipment, facilities and services available for pediatric ...

African Journals Online (AJOL)

Background: Facilities and equipment are known to contribute to improved patient care and outcome. Hospitals for sub‑specialized pediatric anesthetic service are routinely available worldwide. In Nigeria, such hospitals now exist. It is therefore relevant to study the facilities and equipment available for pediatric anesthetic ...

Advanced physical protection systems for facilities and transportation

International Nuclear Information System (INIS)

Jones, O.E.

1976-01-01

Sandia Laboratories is developing advanced physical protection safeguards in order to improve the security of special nuclear materials, facilities, and transportation. Computer models are being used to assess the cost-effectiveness of alternative systems for protecting facilities against external attack which may include internal assistance, and against internal theft or sabotage. Physical protection elements such as admittance controls, portals and detectors, perimeter and interior intrusion alarms, fixed and remotely activated barriers, and secure communications are being evaluated, adapted, and where required, developed. New facilities safeguards concepts which involve ''control loops'' between physical protection and materials control elements are being evolved jointly between Sandia Laboratories and Los Alamos Scientific Laboratory. Special vehicles and digital communications equipment have been developed for the ERDA safe-secure transportation system. The current status and direction of these activities are surveyed

Advanced physical protection systems for facilities and transportation

International Nuclear Information System (INIS)

Jones, O.E.

1976-01-01

Sandia Laboratories is developing advanced physical protection safeguards in order to improve the security of special nuclear materials, facilities, and transportation. Computer models are being used to assess the cost-effectiveness of alternative systems for protecting facilities against external attack which may include internal assistance, and against internal theft or sabotage. Physical protection elements such as admittance controls, portals and detectors, perimeter and interior intrusion alarms, fixed and remotely-activated barriers, and secure communications are being evaluated, adapted, and where required, developed. New facilities safeguards concepts which involve (control loops) between physical protection and materials control elements are being evolved jointly between Sandia Laboratories and Los Alamos Scientific Laboratory. Special vehicles and digital communications equipment have been developed for the ERDA safe-secure transportation system. The current status and direction of these activities are surveyed

High energy laser facilities at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

Holmes, N.C.

1981-06-01

High energy laser facilities at Lawrence Livermore National Laboratory are described, with special emphasis on their use for equation of state investigations using laser-generated shockwaves. Shock wave diagnostics now in use are described. Future Laboratory facilities are also discussed

Mobile Pit verification system design based on passive special nuclear material verification in weapons storage facilities

Energy Technology Data Exchange (ETDEWEB)

Paul, J. N.; Chin, M. R.; Sjoden, G. E. [Nuclear and Radiological Engineering Program, George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, 770 State St, Atlanta, GA 30332-0745 (United States)

2013-07-01

A mobile 'drive by' passive radiation detection system to be applied in special nuclear materials (SNM) storage facilities for validation and compliance purposes has been designed through the use of computational modeling and new radiation detection methods. This project was the result of work over a 1 year period to create optimal design specifications to include creation of 3D models using both Monte Carlo and deterministic codes to characterize the gamma and neutron leakage out each surface of SNM-bearing canisters. Results were compared and agreement was demonstrated between both models. Container leakages were then used to determine the expected reaction rates using transport theory in the detectors when placed at varying distances from the can. A 'typical' background signature was incorporated to determine the minimum signatures versus the probability of detection to evaluate moving source protocols with collimation. This established the criteria for verification of source presence and time gating at a given vehicle speed. New methods for the passive detection of SNM were employed and shown to give reliable identification of age and material for highly enriched uranium (HEU) and weapons grade plutonium (WGPu). The finalized 'Mobile Pit Verification System' (MPVS) design demonstrated that a 'drive-by' detection system, collimated and operating at nominally 2 mph, is capable of rapidly verifying each and every weapon pit stored in regularly spaced, shelved storage containers, using completely passive gamma and neutron signatures for HEU and WGPu. This system is ready for real evaluation to demonstrate passive total material accountability in storage facilities. (authors)

Energy efficiency in California laboratory-type facilities

Energy Technology Data Exchange (ETDEWEB)

Mills, E.; Bell, G.; Sartor, D. [and others

1996-07-31

The central aim of this project is to provide knowledge and tools for increasing the energy efficiency and performance of new and existing laboratory-type facilities in California. We approach the task along three avenues: (1) identification of current energy use and savings potential, (2) development of a {ital Design guide for energy- Efficient Research Laboratories}, and (3) development of a research agenda for focused technology development and improving out understanding of the market. Laboratory-type facilities use a considerable amount of energy resources. They are also important to the local and state economy, and energy costs are a factor in the overall competitiveness of industries utilizing laboratory-type facilities. Although the potential for energy savings is considerable, improving energy efficiency in laboratory-type facilities is no easy task, and there are many formidable barriers to improving energy efficiency in these specialized facilities. Insufficient motivation for individual stake holders to invest in improving energy efficiency using existing technologies as well as conducting related R&D is indicative of the ``public goods`` nature of the opportunity to achieve energy savings in this sector. Due to demanding environmental control requirements and specialized processes, laboratory-type facilities epitomize the important intersection between energy demands in the buildings sector and the industrial sector. Moreover, given the high importance and value of the activities conducted in laboratory-type facilities, they represent one of the most powerful contexts in which energy efficiency improvements stand to yield abundant non-energy benefits if properly applied.

Trip generation characteristics of special generators

Science.gov (United States)

2010-03-01

Special generators are introduced in the sequential four-step modeling procedure to represent certain types of facilities whose trip generation characteristics are not fully captured by the standard trip generation module. They are also used in the t...

Large laser system facility design

International Nuclear Information System (INIS)

Gilmartin, T.J.

1983-01-01

Optical stability of foundations and support structures, environmental control, close-in subsystem integration, spatial organization, materiel flow and access to remote subsystems is discussed and compared for four laser facilities: The Special Isotope Separation Laboratory, Argus, Shiva/Nova, and Firepond

Main principles of development stationary training facilities

International Nuclear Information System (INIS)

Tsiptsyura, R.D.

1986-01-01

The designation of stationary training facilities is shown and the main requirements for them are formulated. When considering the above-mentioned requirements, special attention was paid to obligatory correspondence between training experience and practical skill of an operator. It is shown, that the switchboard block is the major unit of the training facility, which should develop skills and habits of an operator

Post irradiation examinations cooperation and worldwide utilization of facilities

International Nuclear Information System (INIS)

Karlsson, Mikael

2009-01-01

Status of post irradiation examinations in Studsvik's facilities, cooperation and worldwide utilization of facilities, was described. Studsvik cooperate with irradiation facilities, as Halden, CEA and JAEA, as well as other hot cell facilities (examples, PSI, ITU and NFD) universities (example, the Royal Institute of Technology in Sweden) in order to be able to provide everything asked for by the nuclear community. Worldwide cooperation for effective use of expensive and highly specialized facilities is important, and the necessity of cooperation will be more and more recognized in the future. (author)

Special Analysis: Revised 14C Disposal Limits for the Saltstone Disposal Facility

International Nuclear Information System (INIS)

Kaplan, D.I.

2004-01-01

The Saltstone Special Analysis calculated a limit for 14C based on the atmospheric pathway of 52 pCi/mL using some very conservative assumptions. This was compared to the estimated Low Curie Salt concentration of 0.45 pCi/mL and since the limit was two orders of magnitude greater than the estimated concentration, the decision was made that no further analysis was needed. The 14C concentration in Tank 41 has been found to be much greater than the estimated concentration and to exceed the limit derived in the Special Analysis. A rigorous analysis of the release of 14C via the air pathway that considers the chemical effects of the Saltstone system has shown that the flux of 14C is significantly less than that assumed in the Special Analysis. The net result is an inventory limit for 14C that is significantly higher than that derived in the Special Analysis that will also meet the performance objectives of DOE Order 435.1

Nuclear facility safeguards systems modeling using discrete event simulation

International Nuclear Information System (INIS)

Engi, D.

1977-01-01

The threat of theft or dispersal of special nuclear material at a nuclear facility is treated by studying the temporal relationships between adversaries having authorized access to the facility (insiders) and safeguards system events by using a GASP IV discrete event simulation. The safeguards system events--detection, assessment, delay, communications, and neutralization--are modeled for the general insider adversary strategy which includes degradation of the safeguards system elements followed by an attempt to steal or disperse special nuclear material. The performance measure used in the analysis is the estimated probability of safeguards system success in countering the adversary based upon a predetermined set of adversary actions. An exemplary problem which includes generated results is presented for a hypothetical nuclear facility. The results illustrate representative information that could be utilized by safeguards decision-makers

Robotics for nuclear facilities

International Nuclear Information System (INIS)

Abe, Akira; Nakayama, Ryoichi; Kubo, Katsumi

1988-01-01

It is highly desirable that automatic or remotely controlled machines perform inspection and maintenance tasks in nuclear facilities. Toshiba has been working to develop multi-functional robots, with one typical example being a master-slave manipulator for use in reprocessing facilities. At the same time, the company is also working on the development of multi-purpose intelligent robots. One such device, an automatic inspection robot, to be deployed along a monorail, performs inspection by means of image processing technology, while and advanced intelligent maintenance robot is equipped with a special wheel-locomotion mechanism and manipulator and is designed to perform maintenance tasks. (author)

Healthcare facility commissioning – the transition of clinical services

CSIR Research Space (South Africa)

Van der Watt, R

2016-07-01

Full Text Available structure of bricks and mortar into a functional facility with staff, equipment, medication, supplies, etc. ready to eventually receive patients who need care and cure. Beyond these tangible elements, there are also many intangibles which are required, e... in order for the new facility to deliver the intended clinical services. These include links to the emergency services which brings patients in need of emergency care to the facility, links to other healthcare facilities for more specialized care...

An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code

Energy Technology Data Exchange (ETDEWEB)

Kristofova, Kristina; Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter [DECOM Slovakia, spol. s.r.o., J. Bottu 2, SK-917 01 Trnava (Slovakia); Lindskog, Staffan [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

2007-01-15

The presented study is focused on an analysis of decommissioning costs for the Intermediate Storage Facility for Spent Fuel (FA) facility in Studsvik prepared by SVAFO and a proposal of the advanced decommissioning costing methodology application. Therefore, this applied study concentrates particularly in the following areas: 1. Analysis of FA facility cost estimates prepared by SVAFO including description of FA facility in Studsvik, summarised input data, applied cost estimates methodology and summarised results from SVAFO study. 2. Discussion of results of the SVAFO analysis, proposals for enhanced cost estimating methodology and upgraded structure of inputs/outputs for decommissioning study for FA facility. 3. Review of costing methodologies with the special emphasis on the advanced costing methodology and cost calculation code OMEGA. 4. Discussion on implementation of the advanced costing methodology for FA facility in Studsvik together with: - identification of areas of implementation; - analyses of local decommissioning infrastructure; - adaptation of the data for the calculation database; - inventory database; and - implementation of the style of work with the computer code OMEGA.

An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code

International Nuclear Information System (INIS)

Kristofova, Kristina; Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter; Lindskog, Staffan

2007-01-01

The presented study is focused on an analysis of decommissioning costs for the Intermediate Storage Facility for Spent Fuel (FA) facility in Studsvik prepared by SVAFO and a proposal of the advanced decommissioning costing methodology application. Therefore, this applied study concentrates particularly in the following areas: 1. Analysis of FA facility cost estimates prepared by SVAFO including description of FA facility in Studsvik, summarised input data, applied cost estimates methodology and summarised results from SVAFO study. 2. Discussion of results of the SVAFO analysis, proposals for enhanced cost estimating methodology and upgraded structure of inputs/outputs for decommissioning study for FA facility. 3. Review of costing methodologies with the special emphasis on the advanced costing methodology and cost calculation code OMEGA. 4. Discussion on implementation of the advanced costing methodology for FA facility in Studsvik together with: - identification of areas of implementation; - analyses of local decommissioning infrastructure; - adaptation of the data for the calculation database; - inventory database; and - implementation of the style of work with the computer code OMEGA

Approximation algorithms for facility location problems with a special class of subadditive cost functions

NARCIS (Netherlands)

Gabor, A.F.; Ommeren, van J.C.W.

2006-01-01

In this article we focus on approximation algorithms for facility location problems with subadditive costs. As examples of such problems, we present three facility location problems with stochastic demand and exponential servers, respectively inventory. We present a (1+e,1)-reduction of the facility

Pain treatment facilities: do we need quantity or quality?

Science.gov (United States)

de Meij, Nelleke; Köke, Albère; van der Weijden, Trudy; van Kleef, Maarten; Patijn, Jacob

2014-10-01

Chronic pain patients referred to a pain treatment facility have no guarantee that they will receive a proper diagnostic procedure or treatment. To obtain information about organizational aspects of pain treatment facilities and the content of their daily pain practice, we performed a questionnaire survey. The aim of the study was to evaluate the amount of pain treatment facilities, the content of organized specialized pain care and adherence to the criteria of the internationally accepted guidelines for pain treatment services. The University Pain Centre Maastricht in the Department of Anaesthesiology and Pain Management at Maastricht University Medical Centre developed a questionnaire survey based on the Recommendations for Pain Treatment Services of the International Association for the Study of Pain (IASP). The questionnaire was sent to the medical boards of all hospitals in the Netherlands (n=94). The response rate was 86% (n=81). Of all hospitals, 88.9% (n=72) reported the provision of organized specialized pain care, which was provided by a pain management team in 86.1% (n=62) and by an individual specialist in 13.9% (n=10). Insight was obtained from pain treatment facilities in five different domains: the organizational structure of pain management, composition of the pain team, pain team practice, patient characteristics, and research and education facilities. Although 88.9% of all hospitals stated that organized specialized pain care was provided, only a few hospitals could adhere to the criteria for pain treatment services of the IASP. The outcome of the questionnaire survey may help to define quality improvement standards for pain treatment facilities. © 2014 John Wiley & Sons, Ltd.

304 Concretion facility closure plan

International Nuclear Information System (INIS)

1990-04-01

The Hanford Site, located northwest of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium Zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/Zircaloy-2 alloy, and Zircaloy-2 chips and fines were secured in concrete billets in the 304 Concretion Facility, located in the 300 Area. The beryllium/Zircaloy-2 alloy and Zircaloy-2 chips and fines are designated as low-level radioactive mixed waste (LLRMW) with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Concretion Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act of 1976 (RCRA). This closure plan presents a description of the facility, the history of materials and wastes managed, and the procedures that will be followed to close the 304 Concretion Facility (304 Facility). Clean closure of the 304 Facility is the proposed method for closure of the facility. Justification for this proposal is presented. 15 refs., 22 figs., 4 tabs

26 CFR 1.1394-1 - Enterprise zone facility bonds.

Science.gov (United States)

2010-04-01

... business definition. City J issues enterprise zone facility bonds, the proceeds of which are loaned to... TAX (CONTINUED) INCOME TAXES Definitions; Special Rules § 1.1394-1 Enterprise zone facility bonds. (a... (zones). See sections 1394, 1397B, and 1397C for other rules and definitions. (b) Period of compliance—(1...

40 CFR 264.312 - Special requirements for ignitable or reactive waste.

Science.gov (United States)

2010-07-01

..., AND DISPOSAL FACILITIES Landfills § 264.312 Special requirements for ignitable or reactive waste. (a... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for ignitable or reactive waste. 264.312 Section 264.312 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

40 CFR 265.256 - Special requirements for ignitable or reactive waste.

Science.gov (United States)

2010-07-01

... TREATMENT, STORAGE, AND DISPOSAL FACILITIES Waste Piles § 265.256 Special requirements for ignitable or... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for ignitable or reactive waste. 265.256 Section 265.256 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

40 CFR 264.281 - Special requirements for ignitable or reactive waste.

Science.gov (United States)

2010-07-01

..., AND DISPOSAL FACILITIES Land Treatment § 264.281 Special requirements for ignitable or reactive waste... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for ignitable or reactive waste. 264.281 Section 264.281 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

40 CFR 264.256 - Special requirements for ignitable or reactive waste.

Science.gov (United States)

2010-07-01

..., AND DISPOSAL FACILITIES Waste Piles § 264.256 Special requirements for ignitable or reactive waste... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for ignitable or reactive waste. 264.256 Section 264.256 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

Applying new safeguards technology to existing nuclear facilities

International Nuclear Information System (INIS)

Harris, W.J.; Wagner, E.P.

1979-01-01

The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is desinged for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both safeguards and production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

Applying new safeguards technology to existing nuclear facilities

International Nuclear Information System (INIS)

Johnson, C.E.; Wagner, E.P.

1979-01-01

The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is designed for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both Safeguards and Production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

40 CFR 412.21 - Special definitions.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 28 2010-07-01 2010-07-01 true Special definitions. 412.21 Section 412.21 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) EFFLUENT GUIDELINES AND... definitions. For the purposes of this subpart: (a) Dry lot means a facility for growing ducks in confinement...

42 CFR 93.50 - Special terms.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Special terms. 93.50 Section 93.50 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES HEALTH ASSESSMENTS AND HEALTH EFFECTS STUDIES OF HAZARDOUS SUBSTANCES RELEASES AND FACILITIES PUBLIC HEALTH SERVICE POLICIES ON RESEARCH...

How to Improve Engineering Competencies for Students with Special Needs?

Science.gov (United States)

Maknun, J.; Barliana, M. S.; Cahyani, D.

2018-02-01

The problem of vocational education for Children with Special Needs (CSN) is not only about the service profile, spectrum relevance and competency level, but also the carrying capacity of educational facilities. In this regard, two important things are highlighted. First, the different characteristics of the design of educational facilities between regular and exceptional schools. Second, the distinctive characteristics of the design of the school facilities are extraordinary for general education (academic) and vocational education. The purpose of this study is to describe the level of suitability of the architectural design of educational facilities with the needs of vocational learning behavior for children with special needs in West Java, Indonesia. The entire research used the Education Research and Development (R & D) method of Developing the Architectural Facility Design Guide to Support the Vocational Competence of Crew Competence in accordance with the stages developed by Thiagarajan (1974) known as Four-D Model. To achieve the above objectives, then the stages of the R & D method that is done is the define, design and develop stage. Evaluation results show the infrastructure of education of Special School (SLB) Cicendo, Indonesia has met the standards set by the government, especially on aspects of land and building areas have met the standards. Most aspects of accessibility such as the basic size of space, pedestrian pathways, and doors have been met. But other aspects such as guiding lines, ram, ladders, toilets, showers, sinks, furniture and signs do not meet accessibility requirements. The conclusion is the educational infrastructure of the school in general has met the standards set by the government.

Emergency planning for fuel cycle facilities

International Nuclear Information System (INIS)

Lacey, L.R.

1991-01-01

In April 1989, NRC published new emergency planning regulations which apply to certain by-product, source, and special nuclear materials licensees including most fuel cycle facilities. In addition to these NRC regulations, other regulatory agencies such as EPA, OSHA, and DOT have regulations concerning emergency planning or notification that may apply to fuel cycle facilities. Emergency planning requirements address such areas as emergency classification, organization, notification and activation, assessment, corrective and protective measures, emergency facilities and equipment, maintaining preparedness, records and reports, and recovery. This article reviews applicable regulatory requirements and guidance, then concentrates on implementation strategies to produce an effective emergency response capability

Pulse radiolysis facilities and activities in Japan

International Nuclear Information System (INIS)

Ogasawara, M.

1995-01-01

Pulse radiolysis studies in Japan have been reviewed in special reference to the facilities and the people who have engaged in the experiments. Main achievement is summarized with the list of selected publications. (author)

304 Concretion Facility Closure Plan

International Nuclear Information System (INIS)

1991-10-01

The Hanford Site, located northwest of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium with Zircaloy-2 and copper silicon allo , uranium-titanium alloy, beryllium/Zircaloy-2 alloy, and Zircaloy-2 chips and fines were secured in concrete billets (7.5-gal containers) in the 304 Concretion Facility (304 Facility), located in the 300 Area. The beryllium/Zircaloy-2 alloy and Zircaloy-2 chips and fines are designated as low-level radioactive mixed waste (LLRMW) with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Concretion Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act of 1976 (RCRA) and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040 (Ecology 1991). This closure plan presents a description of the facility, the history of materials and wastes managed, and the procedures that will be followed to close the 304 Facility. The strategy for closure of the 304 Facility is presented in Section 6.0

Thunder Mountain School Is Something Special.

Science.gov (United States)

NJEA Review, 1979

1979-01-01

This article describes Thunder Mountain School, operated year round by the Newton Board of Education under a special use permit granted by the National Park Service. The center includes sports facilities, nature preserves, a farm, and historic sites for use by residential and day students, kindergarten through college. (SJL)

Initial operation of the Holifield facility

International Nuclear Information System (INIS)

Ball, J.B.

1982-01-01

The Holifield Heavy Ion Research Facility (HHIRF) is located at Oak Ridge National Laboratory and operated, by the Physics Division, as a national user facility for research in heavy-ion science. The facility operates two accelerators: the new Pelletron electrostatic accelerator, designed to accelerate all ions at terminal potentials up to 25 million volts, and the Oak Ridge Isochronous Cyclotron (ORIC) which, in addition to its stand-alone capabilities, has been modified to serve also as a booster accelerator for ion beams from the Pelletron. In addition, a number of state-of-the-art experimental devices, a new data acquisition computer system, and special user accommodations have been implemented as part of the facility. The construction of the facility was completed officially in June of this year. This paper reports on the present status of facility operation, observations from testing and running of the 25 MV Pelletron, experience with coupled operation of the Pelletron with the ORIC booster, and a brief summary of the experimental devices now available at the facility

Initial operation of the Holifield Facility

International Nuclear Information System (INIS)

Ball, J.B.

1983-01-01

The Holifield Heavy Ion Research Facility (HHIRF) is located at Oak Ridge National Laboratory and operated, by the Physics Division, as a national user facility for research in heavy-ion science. The facility operates two accelerators: the new pelletron electrostatic accelerator, designed to accelerate all ions at terminal potentials up to 25 million volts, and the Oak Ridge Isochronous Cyclotron (ORIC) which, in addition to its stand-alone capabilities, has been modified to serve also as a booster accelerator for ion beams from the Pelletron. In addition, a number of state-of-the-art experimental devices, a new data acquisition computer system, and special user accommodations have been implemented as part of the facility. The construction of the facility was completed officially in June of this year. This paper reports on the present status of facility operation, observations from testing and running of the 25 MV Pelletron, experience with coupled operation of the Pelletron with the ORIC booster, and a brief summary of the experimental devices now available at the facility

Semiannual report on strategic special nuclear material inventory differences

International Nuclear Information System (INIS)

1987-07-01

This twentieth periodic semiannual report of unclassified Inventory Differences (ID's) covers the second six months of fiscal year 1986 (April 1, 1986, through September 30, 1986) for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear materials. Data for the Rocky Flats and Y-12 nuclear weapons production facilities are not included in the report in order to protect classified nuclear weapons information; however, classified ID data from these facilities receive the same scrutiny and analyses as the unclassified data

Joint Actinide Shock Physics Experimental Research (JASPER) Facility Update

International Nuclear Information System (INIS)

Conrad, C. H.; Miller, J.; Cowan, M.; Martinez, M.; Whitcomb, B.

2003-01-01

The JASPER Facility utilizes a Two-Stage Light Gas Gun to conduct equation-of-state(EOS) experiments on plutonium and other special nuclear materials. The overall facility will be discussed with emphasis on the Two-Stage Light Gas Gun characteristics and control interfaces and containment. The containment systems that were developed for this project will be presented

36 CFR 1280.10 - Are there special rules for driving on NARA property?

Science.gov (United States)

2010-07-01

... guards at that NARA facility as soon as possible. We will not tow your illegally parked car if you have... 36 Parks, Forests, and Public Property 3 2010-07-01 2010-07-01 false Are there special rules for... AND RECORDS ADMINISTRATION NARA FACILITIES USE OF NARA FACILITIES What Are the General Rules of...

A spatial decision support system for special health facility location ...

African Journals Online (AJOL)

Access to healthcare is a determinant of the wellbeing of the people. Planning the location and distribution of health facilities to ensure efficiency and equity in the face of limited resources can be challenging, especially where the type of care requires expensive equipments and specialists. This study attempts to provide a ...

Tritium handling facilities at the Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Anderson, J.L.; Damiano, F.A.; Nasise, J.E.

1975-01-01

A new tritium facility, recently activated at the Los Alamos Scientific Laboratory, is described. The facility contains a large drybox, associated gas processing system, a facility for handling tritium gas at pressures to approximately 100 MPa, and an effluent treatment system which removes tritium from all effluents prior to their release to the atmosphere. The system and its various components are discussed in detail with special emphasis given to those aspects which significantly reduce personnel exposures and atmospheric releases. (auth)

Startup of the remote laboratory-scale waste-treatment facility

International Nuclear Information System (INIS)

Knox, C.A.; Siemens, D.H.; Berger, D.N.

1981-01-01

The Remote Laboratory-Scale Waste-Treatment Facility was designed as a system to solidify small volumes of radioactive liquid wastes. The objectives in operating this facility are to evaluate solidification processes, determine the effluents generated, test methods for decontaminating the effluents, and provide radioactive solidified waste products for evaluation. The facility consists of a feed-preparation module, a waste-solidification module and an effluent-treatment module. The system was designed for remote installation and operation. Several special features for remotely handling radioactive materials were incorporated into the design. The equipment was initially assembled outside of a radiochemical cell to size and fabricate the connecting jumpers between the modules and to complete some preliminary design-verification tests. The equipment was then disassembled and installed in the radiochemical cell. When installation was completed the entire system was checked out with water and then with a nonradioactive simulated waste solution. The purpose of these operations was to start up the facility, find and solve operational problems, verify operating procedures and train personnel. The major problems experienced during these nonradioactive runs were plugging of the spray calciner nozzle and feed tank pumping failures. When these problems were solved, radioactive operations were started. This report describes the installation of this facility, its special remote design feature and the startup operations

The role of SANRAD facility in quantitative and morphological investigation

International Nuclear Information System (INIS)

Nshimirimana, Robert; Beer, Frikkie de; Radebe, Mabuti

2011-01-01

The SANRAD (South African Neutron Radiography) facility hosts a neutron/X-ray tomography system, which is extensively being utilized in non-destructive examination experiments where it is necessary to determine the properties (e.g. size, porosity, permeability and morphology) of samples. Those properties have a great importance in a variety of fields such as nuclear shielding, paleontology, geosciences, anatomy and reverse engineering studies. Quantitative and morphological investigations require a tomography system capable of producing tomograms with a high spatial resolution and free of artefacts where specialized imaging software is applied in the investigations. The SANRAD facility is used by the scientific and engineering communities in their qualitative, quantitative and morphological investigations. The capability of the SANRAD facility to investigate qualitatively and quantitatively the internal structure of several objects non-destructively is demonstrated with special emphasis on the precision and accuracy of the system.

12 CFR 725.7 - Special share accounts in federally chartered agent members.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 6 2010-01-01 2010-01-01 false Special share accounts in federally chartered agent members. 725.7 Section 725.7 Banks and Banking NATIONAL CREDIT UNION ADMINISTRATION REGULATIONS AFFECTING CREDIT UNIONS NATIONAL CREDIT UNION ADMINISTRATION CENTRAL LIQUIDITY FACILITY § 725.7 Special...

Reality of dielectric materials in special environment with radiation and others

International Nuclear Information System (INIS)

1993-01-01

In this report, the results of investigation by the expert committee on the title problem in the Institute of Electrical Engineers of Japan from April, 1989 to March, 1992 are summarized. The objectives were to collect the data on the deterioration of dielectric and insulation materials in the special environment including radiation, to investigate the deterioration mechanism, and to grasp the state of development of the materials which can withstand special environment. The actual conditions of temperature, humidity and radiation in nuclear reactors, nuclear fuel cycle facilities, spaceships, accelerator facilities and nuclear fusion experiment facilities are reported. As the new materials which can withstand special environment, the properties of aromatic engineering plastics such as polyimide, PEEK and others, no-halogen incombustible materials, thermoplastic polyurethane, ethylene propylene rubber, cross-linked polyethylene, ceramics, high temperature superconductors, fiber-reinforced composite materials, silica glass and quartz optical fibers are shown. The factors of material deterioration, the method of forecasting lifetime and the examples are explained. The new methods of measuring material properties such as ion microprobe, positron annihilation, scanning tunnel microscopes, optical detection magnetic resonance and so on are explained. (K.I.)

Specification for the delivery of special sections made of aluminum alloy for use as vacuum chambers

International Nuclear Information System (INIS)

Possible extension of the research facility by a large storage-ring facility is presently being planned at DESY. For preliminary engineering tests concerning the dimensions of the vacuum system, there is a need for two extruded special sections made of an aluminum alloy, which are to be fabricated as vacuum chambers in deflecting magnets and in focussing magnets. Conditions of the contract and technical requirements of the special sections are given

Engineered safeguards system activities at Sandia Laboratories for back-end fuel cycle facilities

International Nuclear Information System (INIS)

Sellers, T.A.; Fienning, W.C.; Winblad, A.E.

1978-01-01

Sandia Laboratories have been developing concepts for safeguards systems to protect facilities in the back-end of the nuclear fuel cycle against potential threats of sabotage and theft of special nuclear material (SNM). Conceptual designs for Engineered Safeguards Systems (ESSs) have been developed for a Fuel Reprocessing Facility (including chemical separations, plutonium conversion, and waste solidification), a Mixed-Oxide Fuel Fabrication Facility, and a Plutonium Transport Vehicle. Performance criteria for the various elements of these systems and a candidate systematic design approach have been defined. In addition, a conceptual layout for a large-scale Fuel-Cycle Plutonium Storage Facility has been completed. Work is continuing to develop safeguards systems for spent fuel facilities, light-water reactors, alternative fuel cycles, and improved transportation systems. Additional emphasis will be placed on the problems associated with national diversion of special nuclear material. The impact on safeguards element performance criteria for surveillance and containment to protect against national diversion in various alternative fuel cycle complexes is also being investigated

10 CFR 140.13b - Amount of liability insurance required for uranium enrichment facilities.

Science.gov (United States)

2010-01-01

... enrichment facilities. 140.13b Section 140.13b Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL... required for uranium enrichment facilities. Each holder of a license issued under Parts 40 or 70 of this chapter for a uranium enrichment facility that involves the use of source material or special nuclear...

STG-ET: DLR electric propulsion test facility

Directory of Open Access Journals (Sweden)

Andreas Neumann

2017-04-01

Full Text Available DLR operates the High Vacuum Plume Test Facility Göttingen – Electric Thrusters (STG-ET. This electric propulsion test facility has now accumulated several years of EP-thruster testing experience. Special features tailored to electric space propulsion testing like a large vacuum chamber mounted on a low vibration foundation, a beam dump target with low sputtering, and a performant pumping system characterize this facility. The vacuum chamber is 12.2m long and has a diameter of 5m. With respect to accurate thruster testing, the design focus is on accurate thrust measurement, plume diagnostics, and plume interaction with spacecraft components. Electric propulsion thrusters have to run for thousands of hours, and with this the facility is prepared for long-term experiments. This paper gives an overview of the facility, and shows some details of the vacuum chamber, pumping system, diagnostics, and experiences with these components.

Approximation algorithms for facility location problems with a special class of subadditive cost functions

NARCIS (Netherlands)

Gabor, Adriana F.; van Ommeren, Jan C.W.

2006-01-01

In this article we focus on approximation algorithms for facility location problems with subadditive costs. As examples of such problems, we present three facility location problems with stochastic demand and exponential servers, respectively inventory. We present a $(1+\\varepsilon, 1)$-reduction of

Construction, characteristics and present status of high-fluence irradiation facility at University of Tokyo

International Nuclear Information System (INIS)

Tabata, Yoneho; Kobayashi, Hitoshi; Tagawa, Seiichi; Kouchi, Noriyuki.

1989-01-01

New ion accelerator facility (HIT Facility) was constructed at Research Center for Nuclear Science and Technology, University of Tokyo. This facility, which was equipped with some special apparatus, has been mainly dedicated to the study of radiation effects of ion beams on materials. In this report, the construction, the characteristics and the present status of this facility are described. (author)

Joint Actinide Shock Physics Experimental Research (JASPER) Facility Overview

International Nuclear Information System (INIS)

Konrad, C.H.; Braddy, R.W.; Martinez, Mark

2001-01-01

The JASPER Facility will utilize a Two-Stage Light Gas Gun to conduct equation-of-state (EOS) experiments of plutonium and other special nuclear materials. The overall facility will be discussed with emphasis on the Two-Stage Light Gas Gun characteristics and mission. The primary and secondary containment systems that were developed for this project will be presented. Primary gun diagnostics and timing will also be discussed

Small scale homelike special care units and traditional special care units : effects on cognition in dementia; a longitudinal controlled intervention study

NARCIS (Netherlands)

Kok, Jeroen S.; van Heuvelen, Marieke J. G.; Berg, Ina J.; Scherder, Erik J. A.

2016-01-01

Background: Evidence shows that living in small scale homelike Special Care Units (SCU) has positive effects on behavioural and psychological symptoms of patients with dementia. Effects on cognitive functioning in relation to care facilities, however, are scarcely investigated. The purpose of this

Separations canyon decontamination facilities

International Nuclear Information System (INIS)

Hershey, J.H.

1975-01-01

Highly radioactive process equipment is decontaminated at the Savannah River Plant in specially equipped areas of the separations canyon building so that direct mechanical repairs or alterations can be made. Using these facilities it is possible to decontaminate and repair equipment such as 10- x 11-ft storage tanks, 8- x 8-ft batch evaporator pots and columns, 40-in. Bird centrifuges, canyon pumps and agitators, and various canyon piping systems or ''jumpers.'' For example, centrifuge or evaporator pots can be decontaminated and rebuilt for about 60 percent of the 1974 replacement cost. The combined facilities can decontaminate and repair 6 to 10 pieces of major equipment per year. Decontamination time varies with type of equipment and radioactivity levels encountered

Separations canyon decontamination facilities

International Nuclear Information System (INIS)

Hershey, J.H.

1975-05-01

Highly radioactive process equipment is decontaminated at the Savannah River Plant in specially equipped areas of the separations canyon buildings so that direct mechanical repairs or alterations can be made. Using these facilities it is possible to decontaminate and repair equipment such as 10- x 11-ft storage tanks, 8- x 8-ft batch evaporator pots and columns, 40-in. Bird centrifuges, canyon pumps and agitators, and various canyon piping systems or ''jumpers.'' For example, centrifuge or evaporator pots can be decontaminated and rebuilt for about 60 percent of the 1974 replacement cost. The combined facilities can decontaminate and repair 6 to 10 pieces of major equipment per year. Decontamination time varies with type of equipment and radioactivity levels encountered. (U.S.)

49 CFR 37.9 - Standards for accessible transportation facilities.

Science.gov (United States)

2010-10-01

... alterations begun before January 26, 1992, in a good faith effort to make a facility accessible to individuals..., including advertisement in appropriate media, such as newspapers of general and special interest circulation...

Visitor centres at nuclear facility sites

International Nuclear Information System (INIS)

1993-01-01

Communications strategies in the nuclear field are often based on the creation of visitor centres at nuclear facility sites. Today, the design, as well as the realization and management of such centres has become a specialized function, and its role is very complementary to the nuclear operator's. It also uses the latest technology in the field of audio-visual, experiment and interactivity. This publication contains the proceedings of an international seminar organized by the OECD Nuclear Energy Agency on the role of visitor centres at nuclear facility sites. It includes the main papers presented at this Seminar

User Facilities: The Education of New Neutron Users

International Nuclear Information System (INIS)

Hernandez, Yamali; Brown, Craig M.

2009-01-01

Neutron scattering is a particularly useful tool enabling the study of compositional, structural and dynamical properties of materials down to the atomic scale. Due to the complexity of operating an intense source of neutrons, this technique is primarily practiced at large national facilities that cater to the research needs of chemists, biologists, physicists, engineers, and material scientists in general. In particular, these user facilities provide specialized instrumentation along with the scientific and technical support required to efficiently utilize it. Since neutron scattering experiments are performed at central facilities rather than in the home-laboratories of individual investigators, the facilities themselves must play a key role in the education and development of new users. The role of neutron scattering facilities in educating young scientists will be examined using examples from current programs at the National Institute of Standards and Technology Center for Neutron Research.

Incineration facilities for treatment of radioactive wastes: a review

Energy Technology Data Exchange (ETDEWEB)

Perkins, B.L.

1976-02-01

A description is given of incinerator installations in the US and in foreign countries. Included are descriptions of inactive incinerators, incinerator facilities currently in operation, and incinerator installations under construction. Special features of each installation and operational problems of each facility are emphasized. Problems in the incineration of radioactive waste are discussed in relation to the composition of the waste and the amount and type of radioactive contaminant.

Incineration facilities for treatment of radioactive wastes: a review

International Nuclear Information System (INIS)

Perkins, B.L.

1976-02-01

A description is given of incinerator installations in the US and in foreign countries. Included are descriptions of inactive incinerators, incinerator facilities currently in operation, and incinerator installations under construction. Special features of each installation and operational problems of each facility are emphasized. Problems in the incineration of radioactive waste are discussed in relation to the composition of the waste and the amount and type of radioactive contaminant

On computing special functions in marine engineering

Science.gov (United States)

Constantinescu, E.; Bogdan, M.

2015-11-01

Important modeling applications in marine engineering conduct us to a special class of solutions for difficult differential equations with variable coefficients. In order to be able to solve and implement such models (in wave theory, in acoustics, in hydrodynamics, in electromagnetic waves, but also in many other engineering fields), it is necessary to compute so called special functions: Bessel functions, modified Bessel functions, spherical Bessel functions, Hankel functions. The aim of this paper is to develop numerical solutions in Matlab for the above mentioned special functions. Taking into account the main properties for Bessel and modified Bessel functions, we shortly present analytically solutions (where possible) in the form of series. Especially it is studied the behavior of these special functions using Matlab facilities: numerical solutions and plotting. Finally, it will be compared the behavior of the special functions and point out other directions for investigating properties of Bessel and spherical Bessel functions. The asymptotic forms of Bessel functions and modified Bessel functions allow determination of important properties of these functions. The modified Bessel functions tend to look more like decaying and growing exponentials.

Criteria, standards and policies regarding decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Detilleux, E.; Lennemann, W.L.

1977-01-01

At the end of this century, there will probably be around 2500 operating nuclear power reactors, along with all the other nuclear fuel cycle facilities supporting their operation. Eventually these facilities, one by one, will be shut down and it will be necessary to dispose of them as with any redundant industrial facility or plant. Some parts of a nuclear fuel cycle facility can be dismantled by conventional methods, but those parts which have become contaminated with radioactive nuclear products or induced radioactivity must be subject to rigid controls and restrictions and handled by special dismantling and disposal procedures. In many cases, the resulting quantity of radioactive waste is likely to be relatively large and dismantling quite costly. Decommissioning nuclear facilities is a multifaceted problem involving planners, design engineers, operators, waste managers and regulatory authorities. Preparation for decommissioning should begin as early as site selection and plant design. The corner stone for the preparation of a decommissioning programme is the definition of its extent, meeting the requirements for public and environmental protection during the period that the radioactive material is of concern. The paper discusses the decontamination and decommissioning experience at the Eurochemic fuel reprocessing plant, the implications and the knowledge gained from this experience. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who should jointly make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities

Environmental licensing of nuclear facilities: compatibility of technical competencies

International Nuclear Information System (INIS)

Shu, J.; Paiva, R.L.C. de; Mezrahi, A.; Cardoso, E.M.; Aquino, W.P.; Deppe, A.L.; Menezes, R.M.; Prado, V.; Franco, N.M.F.L.; Nouailhetas, Y.; Xavier, A.M.

1996-01-01

The Brazilian Nuclear Energy Commission (CNEN) has the technical competency for diagnosing environmental radiological impacts, as well as evaluating the safety and requiring adequate control of the facilities which, due to their activities, represent a potential risk of radiological contamination for the environment. The institution is responsible for emission of radioprotection guidelines, controls and surveys in nuclear safety according to the country's regulations and international recommendations. The methodology to assure the limitation of radiation exposure is consequence from shared control over the nuclear activities, in special the nuclear facilities. According to the Federal Constitution of 1988, the nuclear activities must be under exclusive control of the Union in special related to the nuclear policies, economical, laboral and nuclear safety aspects, while the health and environmental controls of these activities are shared by the Federation, Union, States, Federal District and Counties. The controls related to specific aspects have to be harmonized in such a way to be optimized and effective. In this paper the results of compatibilization of nuclear legislation and environmental legislation are presented aiming to optimize the licensing of nuclear facilities. (author)

Low temperature irradiation facility at Kyoto University Reactor (KUR)

International Nuclear Information System (INIS)

Atobe, Kozo; Okada, Moritami; Yoshida, Hiroyuki; Kodaka, Hisao; Miyata, Kiyomi.

1977-01-01

A new refrigeration system has been substituted to the low temperature irradiation facility at KUR instead of the previous one, since April in 1975. The model 1204 CTi He liquifier was designed to be modified for the refrigerator with the capacity of 30 watts at 10 K. The refrigeration capacity of 38 watts at 10 K was defined using a special cryostat and transfer-tubes, and the lowest temperature of about 18 K was measured using the irradiation loop without reactor operation. The reconstructed facility enables us to hold the many specimens simultaneously in the sample chamber of the irradiation loop at about 25 K during reactor operation of 5 MW. The irradiation dose has been reached about 6.6 x 10 16 n sub(f)/cm 2 and 6.1 x 10 17 n sub(th)/cm 2 with the normal reactor operation cycle of up to 77 hours. The stable operation condition of the machine and the special safety system for the refrigeration system enable us to maintain easily the facility with a constant operation condition for such a long time irradiation. Many kinds of low temperature neutron irradiation experiments are carried out using the facility, which techniques are partially reported. (auth.)

FEMP Focus - Special Issue 2006 - EPACT 2005 and Presidential Memo

Energy Technology Data Exchange (ETDEWEB)

None

2006-03-01

Features information about Presidential Memorandum on Energy Conservation, Energy Policy Act 2005 Special Section, ESET FEMP Deploys Teams in Response to Natural Gas Concerns, Natural Gas Tips for Facility Managers, and more for federal agencies.

WASH and gender in health care facilities: The uncharted territory.

Science.gov (United States)

Kohler, Petra; Renggli, Samuel; Lüthi, Christoph

2017-11-08

Health care facilities in low- and middle-income countries are high-risk settings, and face special challenges to achieving sustainable water, sanitation, and hygiene (WASH) services. Our applied interdisciplinary research conducted in India and Uganda analyzed six dimensions of WASH services in selected health care facilities, including menstrual hygiene management. To be effective, WASH monitoring strategies in health care facilities must include gender sensitive measures. We present a novel strategy, showing that applied gender sensitive multitool assessments are highly productive in assessments of WASH services and facilities from user and provider perspectives. We discuss its potential for applications at scale and as an area of future research.

Special requirements of aquaponics in Finland

OpenAIRE

Soppela, Olli

2016-01-01

This thesis brings together observations about special features that should be taken into consideration when designing the technical aspects of aquaponics practices and production units in Finland. Market demands, water purification and facility temperature control methods; sources of healthy feed and the needs for artificial lighting vary significantly around the globe. The unique combination of climate conditions, legislation and zoological conditions should be taken into consideration whe...

A novel DC Magnetron sputtering facility for space research and synchrotron radiation optics

DEFF Research Database (Denmark)

Hussain, A.M.; Christensen, Finn Erland; Pareschi, G.

1998-01-01

A new DC magnetron sputtering facility has been build up at the Danish Space Research Institute (DSRI), specially designed to enable uniform coatings of large area curved optics, such as Wolter-I mirror optics used in space telescopes and curved optics used in synchrotron radiation facilities...

Unique life sciences research facilities at NASA Ames Research Center

Science.gov (United States)

Mulenburg, G. M.; Vasques, M.; Caldwell, W. F.; Tucker, J.

1994-01-01

The Life Science Division at NASA's Ames Research Center has a suite of specialized facilities that enable scientists to study the effects of gravity on living systems. This paper describes some of these facilities and their use in research. Seven centrifuges, each with its own unique abilities, allow testing of a variety of parameters on test subjects ranging from single cells through hardware to humans. The Vestibular Research Facility allows the study of both centrifugation and linear acceleration on animals and humans. The Biocomputation Center uses computers for 3D reconstruction of physiological systems, and interactive research tools for virtual reality modeling. Psycophysiological, cardiovascular, exercise physiology, and biomechanical studies are conducted in the 12 bed Human Research Facility and samples are analyzed in the certified Central Clinical Laboratory and other laboratories at Ames. Human bedrest, water immersion and lower body negative pressure equipment are also available to study physiological changes associated with weightlessness. These and other weightlessness models are used in specialized laboratories for the study of basic physiological mechanisms, metabolism and cell biology. Visual-motor performance, perception, and adaptation are studied using ground-based models as well as short term weightlessness experiments (parabolic flights). The unique combination of Life Science research facilities, laboratories, and equipment at Ames Research Center are described in detail in relation to their research contributions.

Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

International Nuclear Information System (INIS)

Shields, K.D.; Ballinger, M.Y.

1999-03-01

This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment 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. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities

Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

Energy Technology Data Exchange (ETDEWEB)

Shields, K.D.; Ballinger, M.Y.

1999-04-02

This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment 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. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities.

International safeguards for critical facilities

International Nuclear Information System (INIS)

Ney, J.F.; Todd, J.L.

1979-01-01

A study was undertaken to investigate various approaches to provide international safeguards for critical facilities and to select an optimized system. Only high-inventory critical facilities were considered. The goal of the study was to detect and confirm the protracted or abrupt diversion of 8kg of plutonium or 25kg of the uranium isotope 235 within approximately a week of the diversion. The general safeguards alternatives considered were (1) continuous inspections by resident inspectors, with varying degrees of comprehensiveness, (2) periodic inspections by regional inspectors at varying time intervals, (3) unattended containment/surveillance measures, and (4) various combinations of the above. It was concluded that a practical and effective international safeguards system can be achieved by employing a method of continuously monitoring facility activities which could lead to diversion. This is in addition to the routine inspections typical of current international safeguards. Monitoring detects inventory discrepancies and violations of agreed-upon procedural restrictions, as well as unauthorized removal of Special Nuclear Materials (SNM). A special inventory is used following detection to confirm any suspected diversion. Comparison of 28 safeguards options led to the selection of a system for further development which uses a combination of surveillance and inspection by resident IAEA personnel, containment/surveillance by unattended equipment, and routine inventory sampling. A development programme is described which is intended to demonstrate the feasibility of several containment and surveillance measures proposed in the study. Included are a personnel portal and an instrument/material pass-through as well as associated recording and tamper-protection features. (author)

Design of radioisotope power systems facility

International Nuclear Information System (INIS)

Eschenbaum, R.C.; Wiemers, M.J.

1991-01-01

Radioisotope power systems currently produced for the U.S. Department of Energy Office of Special Applications by the Mound Laboratory at Miamisburg, Ohio, have been used in a variety of configurations by the Department of Defense and the National Aeronautics and Space Administration. A forecast of fugure radioisotope power systems requirements showed a need for an increased production rate beyond the capability of the existing Mound Laboratory. Westinghouse Hanford Company is modifying the Fuels and Materials Examination Facility on the Hanford Site near Richland, Washington, to install the new Radioisotope Power Systems Facility for assembling future radioisotope power systems. The facility is currently being prepared to assemble the radioisotope thermoelectric generators required by the National Aeronautics and Space Administration missions for Comet Rendezvous Asteroid Flyby in 1995 and Cassini, an investigation of Saturn and its moons, in 1996

Startup of the Whiteshell irradiation facility

International Nuclear Information System (INIS)

Barnard, J.W.; Stanley, F.W.

1989-01-01

Recently, a 10-MeV, 1-kW electron linear accelerator was installed in a specially designed irradiation facility at the Whiteshell Nuclear Research Establishment. The facility was designed for radiation applications research in the development of new radiation processes up to the pilot scale level. The accelerator is of advanced design. Automatic startup via computer control makes it compatible with industrial processing. It has been operated successfully as a fully integrated electron irradiator for a number of applications including curing of plastics and composites, sterilization of medical disposables and animal feed irradiation. We report here on our experience during the first six months of operation. (orig.)

Startup of the whiteshell irradiation facility

Science.gov (United States)

Barnard, J. W.; Stanley, F. W.

1989-04-01

Recently, a 10-MeV, 1-kW electron linear accelerator was installed in a specially designed irradiation facility at the Whiteshell Nuclear Research Establishment. The facility was designed for radiation applications research in the development of new radiation processes up to the pilot scale level. The accelerator is of advanced design. Automatic startup via computer control makes it compatible with industrial processing. It has been operated successfully as a fully integrated electron irradiator for a number of applications including curing of plastics and composites, sterilization of medical disposables and animal feed irradiation. We report here on our experience during the first six months of operation.

User's guide for evaluating physical security capabilities of nuclear facilities by the EASI method

International Nuclear Information System (INIS)

Bennett, H.A.

1977-06-01

This handbook is a guide for evaluating physical security of nuclear facilities using the ''Estimate of Adversary Sequence Interruption (EASI)'' method and a hand-held programmable calculator. The handbook is intended for use by personnel at facilities where special nuclear materials are used, processed, or stored. It may also be used as a design aid for such facilities by potential licensees

Idaho National Engineering Laboratory irradiation facilities and their applications

International Nuclear Information System (INIS)

Gupta, V.P.; Herring, J.S.; Korenke, R.E.; Harker, Y.D.

1986-05-01

Although there is a growing need for neutron and gamma irradiation by governmental and industrial organizations in the United States and in other countries, the number of facilities providing such irradiations are limited. At the Idaho National Engineering Laboratory, there are several unique irradiation facilities producing high neutron and gamma radiation environments. These facilities could be readily used for nuclear research, materials testing, radiation hardening studies on electronic components/circuitry and sensors, and production of neutron transmutation doped (NTD) silicon and special radioisotopes. In addition, a neutron radiography unit, suitable for examining irradiated materials and assemblies, is also available. This report provides a description of the irradiation facilities and the neutron radiography unit as well as examples of their unique applications

Complying with the Federal Facilities Compliance Act

International Nuclear Information System (INIS)

Pavetto, C.S.; Watmore, A.S.

1994-01-01

The Federal Facilities Compliance Act (FFCA), signed into law on October 6, 1992, amended the Resource Conservation and Recovery Act (RCRA) to place significant additional environmental compliance responsibilities on federal facilities. The federal government has expressly waived sovereign immunity regarding hazardous waste enforcement action taken against these facilities by the states and the EPA. An exception exists for mixed waste violations. The FFCA defines mixed waste as hazardous waste, as defined by RCRA, combined with source, special nuclear or by-product material that is subject to the Atomic Energy Act of 1954. As the majority owner of mixed waste in the United States, the Department of Energy (DOE) must satisfy several new requirements under the FFCA for their facilities. This paper reviews the FFCA's requirements and how they apply to and may affect the DOE and other federal facilities. Included in the review are responsibilities of federal agencies involved and the role of the EPA and the states. In addition, this paper discusses the intent of the FFCA to encourage development of federal facility agreements (FFA) between federal agencies, the EPA and state environmental regulatory agencies

The Modernization ISS in APPS of Important Facility for Protection from Insider Actions

OpenAIRE

D.A. Poladiev; S. I. Zhurin

2012-01-01

This report is about functions of protection from insider actions in modern Automatically Physical Protection System (APPS) of important facility. These functions can be held on special software of APPS and on software of information protection. The usage of this approach can improve the security of important facility in fut

Analytical methods and laboratory facility for the Defense Waste Processing Facility

International Nuclear Information System (INIS)

Coleman, C.J.; Dewberry, R.A.; Lethco, A.J.; Denard, C.D.

1985-01-01

This paper describes the analytical methods, instruments, and laboratory that will support vitrification of defense waste. The Defense Waste Processing Facility (DWPF) is now being constructed at Savannah River Plant (SRP). Beginning in 1989, SRP high-level defense waste will be immobilized in borosilicate glass for disposal in a federal repository. The DWPF will contain an analytical laboratory for performing process control analyses. Additional analyses will be performed for process history and process diagnostics. The DWPF analytical facility will consist of a large shielded sampling cell, three shielded analytical cells, a laboratory for instrumental analysis and chemical separations, and a counting room. Special instrumentation is being designed for use in the analytical cells, including microwave drying/dissolution apparatus, and remote pipetting devices. The instrumentation laboratory will contain inductively coupled plasma, atomic absorption, Moessbauer spectrometers, a carbon analyzer, and ion chromatography equipment. Counting equipment will include intrinsic germanium detectors, scintillation counters, Phoswich alpha, beta, gamma detectors, and a low-energy photon detector

Preliminary Design of the AEGIS Test Facility

CERN Document Server

Dassa, Luca; Cambiaghi, Danilo

2010-01-01

The AEGIS experiment is expected to be installed at the CERN Antiproton Decelerator in a very close future, since the main goal of the AEGIS experiment is the measurement of gravity impact on antihydrogen, which will be produced on the purpose. Antihydrogen production implies very challenging environmental conditions: at the heart of the AEGIS facility 50 mK temperature, 1e-12 mbar pressure and a 1 T magnetic field are required. Interfacing extreme cryogenics with ultra high vacuum will affect very strongly the design of the whole facility, requiring a very careful mechanical design. This paper presents an overview of the actual design of the AEGIS experimental facility, paying special care to mechanical aspects. Each subsystem of the facility – ranging from the positron source to the recombination region and the measurement region – will be shortly described. The ultra cold region, which is the most critical with respect to the antihydrogen formation, will be dealt in detail. The assembly procedures will...

Facilities for the production and processing of radioisotopes

International Nuclear Information System (INIS)

Fourie, P.J.

1980-01-01

Radioisotopes which are used in South Africa are produced in the nuclear reactor SAFARI 1 of the AEB and the CSIR cyclotron in Pretoria or are being imported from various overseas manufactures. The safe and efficient production and use of radioisotopes is possible when being handled by sufficiently trained personnel using special designed equipment and facilities. The Isotope Production Centre is situated next to the reactor and waste treatment buildings. New production facilities shielded with lead and equipped with remote handling equipment are being erected and will be commissioned early during 1980 [af

International safeguards for a modern MOX [mixed-oxide] fuel fabrication facility

International Nuclear Information System (INIS)

Pillay, K.K.S.; Stirpe, D.; Picard, R.R.

1987-03-01

Bulk-handling facilities that process plutonium for commercial fuel cycles offer considerable challenges to nuclear materials safeguards. Modern fuel fabrication facilities that handle mixed oxides of plutonium and uranium (MOX) often have large inventories of special nuclear materials in their process lines and in storage areas for feed and product materials. In addition, the remote automated processing prevalent at new MOX facilities, which is necessary to minimize radiation exposures to personnel, tends to limit access for measurements and inspections. The facility design considered in this study incorporates all these features as well as state-of-the-art measurement technologies for materials accounting. Key elements of International Atomic Energy Agency (IAEA) safeguards for such a fuel-cycle facility have been identified in this report, and several issues of primary importance to materials accountancy and IAEA verifications have been examined. We have calculated detection sensitivities for abrupt and protracted diversions of plutonium assuming a single materials balance area for all processing areas. To help achieve optimal use of limited IAEA inspection resources, we have calculated sampling plans for attributes/variables verification. In addition, we have demonstrated the usefulness of calculating σ/sub (MUF-D)/ and detection probabilities corresponding to specified material-loss scenarios and resource allocations. The data developed and the analyses performed during this study can assist both the facility operator and the IAEA in formulating necessary safeguards approaches and verification procedures to implement international safeguards for special nuclear materials

International safeguards for a modern MOX (mixed-oxide) fuel fabrication facility

Energy Technology Data Exchange (ETDEWEB)

Pillay, K.K.S.; Stirpe, D.; Picard, R.R.

1987-03-01

Bulk-handling facilities that process plutonium for commercial fuel cycles offer considerable challenges to nuclear materials safeguards. Modern fuel fabrication facilities that handle mixed oxides of plutonium and uranium (MOX) often have large inventories of special nuclear materials in their process lines and in storage areas for feed and product materials. In addition, the remote automated processing prevalent at new MOX facilities, which is necessary to minimize radiation exposures to personnel, tends to limit access for measurements and inspections. The facility design considered in this study incorporates all these features as well as state-of-the-art measurement technologies for materials accounting. Key elements of International Atomic Energy Agency (IAEA) safeguards for such a fuel-cycle facility have been identified in this report, and several issues of primary importance to materials accountancy and IAEA verifications have been examined. We have calculated detection sensitivities for abrupt and protracted diversions of plutonium assuming a single materials balance area for all processing areas. To help achieve optimal use of limited IAEA inspection resources, we have calculated sampling plans for attributes/variables verification. In addition, we have demonstrated the usefulness of calculating sigma/sub (MUF-D)/ and detection probabilities corresponding to specified material-loss scenarios and resource allocations. The data developed and the analyses performed during this study can assist both the facility operator and the IAEA in formulating necessary safeguards approaches and verification procedures to implement international safeguards for special nuclear materials.

Hazard characterization and special considerations for environmental and decontamination and decommissioning activities

International Nuclear Information System (INIS)

Kerr, N.R.

1993-08-01

The mission of the US Department of Energy (DOE) has changed from defense production of special nuclear materials to cleanup of production facilities at the Hanford Site. The DOE contractors have formed the Energy Facility Contractors Group to support this change in mission. In addition, the Safety Analysis Working Subgroup for Environmental Restoration and Decontamination and Decommissioning (ER/D ampersand D) was formed to identify, develop, and share information that supports safety analyses and engineering of ER/D ampersand D activities. Safety analysis is in part the process of identifying and understanding the hazards that could result in exposures to radiological or chemical hazardous substances. The following paragraphs address the special considerations given to hazard characterization for ER/D ampersand D activities

INEEL special case waste storage and disposal alternatives

International Nuclear Information System (INIS)

Larson, L.A.; Bishop, C.W.; Bhatt, R.N.

1997-07-01

Special case waste is historically defined as radioactive waste that does not have a path forward or fit into current Department of Energy management plans for final treatment or disposal. The objectives of this report, relative to special case waste at the Idaho National Engineering and Environmental Laboratory, are to (a) identify its current storage locations, conditions, and configuration; (b) review and verify the currently reported inventory; (c) segregate the inventory into manageable categories; (d) identify the portion that has a path forward or is managed under other major programs/projects; (e) identify options for reconfiguring and separating the disposable portions; (f) determine if the special case waste needs to be consolidated into a single storage location; and (g) identify a preferred facility for storage. This report also provides an inventory of stored sealed sources that are potentially greater than Class C or special case waste based on Nuclear Regulatory Commission and Site-Specific Waste Acceptance Criteria

Radiological characterization of two Spanish uranium mine facilities

International Nuclear Information System (INIS)

Quindos Poncela, L.S.; Fernandez, P.I.; Gomez Arozamena, J.; Bordonoba, M.L.

2000-01-01

During the last decade our Department of Applied and Medical Physics has been involved in the development of a Radiation Protection Programme to monitor and control the environmental radiation conditions existing in the only two Spanish uranium mill facilities located at La Haba (Badajoz) and Salacious (Salamanca). Both mines are located in the west of the country, geographical area with high natural radiation levels. In the framework of this Programme, measurements of radon, radon progeny and external gamma radiation indoors and outdoors, as well as of radon exhalation rate and natural radionuclide concentrations in tailings and soils, have been systematically carried out. In particular, two ore body areas in these uranium mill sites have been specially studied to determine the natural radiation background to be used as a reference value to design reliable criteria for the closure of both facilities, which is planned for the next year. This paper summarizes the main results obtained from the measurements of external gamma radiation, radon concentrations, radon exhalation rate and natural radionuclide activity concentrations made in the above mentioned facilities with special emphasis on the results achieved from the ore body areas. Correlations between experimental results and a short description of the devices and methods used in the measurements are also shown. (author)

Nuclear facility safeguards as specified by the Czechoslovak administrative law

International Nuclear Information System (INIS)

Elias, J.; Svab, J.

1978-01-01

A study is presented of the legal aspects of nuclear safeguards for the operation of nuclear power facilities evaluating the development of the legal arrangement over the past five years, i.e., encoding nuclear safeguards for nuclear facilities in the new building regulations (Act No. 50/1976 Coll. of Laws on Urban Planning and Building Regulations and implementing provisions). It also discusses the juridical position of State surveillance over the nuclear safety of nuclear facilities and its relation to surveillance carried out by specialized bodies of the State work safety inspection and to surveillance carried out by hygiene inspection bodies. (J.S.)

Experimental Breeder Reactor II (EBR-II) Fuel-Performance Test Facility (FPTF)

International Nuclear Information System (INIS)

Pardini, J.A.; Brubaker, R.C.; Veith, D.J.; Giorgis, G.C.; Walker, D.E.; Seim, O.S.

1982-01-01

The Fuel-Performance Test Facility (FPTF) is the latest in a series of special EBR-II instrumented in-core test facilities. A flow control valve in the facility is programmed to vary the coolant flow, and thus the temperature, in an experimental-irradiation subassembly beneath it and coupled to it. In this way, thermal transients can be simulated in that subassembly without changing the temperatures in surrounding subassemblies. The FPTF also monitors sodium flow and temperature, and detects delayed neutrons in the sodium effluent from the experimental-irradiation subassembly beneath it. This facility also has an acoustical detector (high-temperature microphone) for detecting sodium boiling

Centralized computer-based controls of the Nova Laser Facility

International Nuclear Information System (INIS)

Krammen, J.

1985-01-01

This article introduces the overall architecture of the computer-based Nova Laser Control System and describes its basic components. Use of standard hardware and software components ensures that the system, while specialized and distributed throughout the facility, is adaptable. 9 references, 6 figures

Radonclose - the system of Soviet designed regional waste management facilities

International Nuclear Information System (INIS)

Horak, W.C.; Reisman, A.; Purvis, E.E. III.

1997-01-01

The Soviet Union established a system of specialized regional facilities to dispose of radioactive waste generated by sources other than the nuclear fuel cycle. The system had 16 facilities in Russia, 5 in Ukraine, one in each of the other CIS states, and one in each of the Baltic Republics. These facilities are still being used. The major generators of radioactive waste they process these are research and industrial organizations, medical and agricultural institution and other activities not related to nuclear power. Waste handled by these facilities is mainly beta- and gamma-emitting nuclides with half lives of less than 30 years. The long-lived and alpha-emitting isotopic content is insignificant. Most of the radwaste has low and medium radioactivity levels. The facilities also handle spent radiation sources, which are highly radioactive and contain 95-98 percent of the activity of all the radwaste buried at these facilities

Report of the committee on a commercially developed space facility

Science.gov (United States)

Shea, Joseph F.; Stever, H. Guyford; Cutter, W. Bowman, III; Demisch, Wolfgang H.; Fink, Daniel J.; Flax, Alexander H.; Gatos, Harry C.; Glicksman, Martin E.; Lanzerotti, Louis J.; Logsdon, John M., III

1989-01-01

Major facilities that could support significant microgravity research and applications activity are discussed. The ground-based facilities include drop towers, aircraft flying parabolic trajectories, and sounding rockets. Facilities that are intrinsically tied to the Space Shuttle range from Get-Away-Special canisters to Spacelab long modules. There are also orbital facilities which include recoverable capsules launched on expendable launch vehicles, free-flying spacecraft, and space stations. Some of these existing, planned, and proposed facilities are non-U.S. in origin, but potentially available to U.S. investigators. In addition, some are governmentally developed and operated whereas others are planned to be privately developed and/or operated. Tables are provided to show the facility, developer, duration, estimated gravity level, crew interaction, flight frequency, year available, power to payload, payload volume, and maximum payload mass. The potential of direct and indirect benefits of manufacturing in space are presented.

42 CFR 412.105 - Special treatment: Hospitals that incur indirect costs for graduate medical education programs.

Science.gov (United States)

2010-10-01

... 42 Public Health 2 2010-10-01 2010-10-01 false Special treatment: Hospitals that incur indirect costs for graduate medical education programs. 412.105 Section 412.105 Public Health CENTERS FOR... SYSTEMS FOR INPATIENT HOSPITAL SERVICES Special Treatment of Certain Facilities Under the Prospective...

303-K Radioactive Mixed-Waste Storage Facility closure plan

International Nuclear Information System (INIS)

1991-11-01

The Hanford Site, located northwest of Richland, Washington, houses reactors chemical-separation systems, and related facilities used for the production o special nuclear materials. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 303-K Radioactive Mixed-Waste Storage Facility (303-K Facility) has been used since 1943 to store various radioactive,and dangerous process materials and wastes generated by the fuel manufacturing processes in the 300 Area. The mixed wastes are stored in US Department of Transportation (DOT)-specification containers (DOT 1988). The north end of the building was used for storage of containers of liquid waste and the outside storage areas were used for containers of solid waste. Because only the north end of the building was used, this plan does not include the southern end of the building. This closure plan presents a description of the facility, the history of materials and wastes managed, and a description of the procedures that will be followed to chose the 303-K Facility as a greater than 90-day storage facility. The strategy for closure of the 303-K Facility is presented in Chapter 6.0

Selection of portable tools for use in a size reduction facility

International Nuclear Information System (INIS)

Hawley, L.N.

1986-07-01

A range of portable tools are identified for development and eventual use within a remote operations facility for the size reduction of plutonium contaminated materials. The process of selection defines the work to be performed within the facility and matches this to the general categories of suitable tools. Specific commercial tools are then selected or, where none exists, proposals are made for the development of special tools. (author)

3718-F Alkali Metal Treatment and Storage Facility Closure Plan

International Nuclear Information System (INIS)

1992-11-01

The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed

Facility Service Market an European Overview based on EU Statistics

Directory of Open Access Journals (Sweden)

Alexander Redlein

2017-01-01

Full Text Available The macro-economic impact of facility management and facility services in special was not scientifically analysed by now. Some studies analysed single countries but were mainly lacking solid data. Especially a Pan European comparison is lacking. This paper presents the results of an in depth analysis of the Eurostat figures. It compares the facility service industry with other industries in particular the construction industry. It also compares the largest European economies (Germany, France and Italy. The study concentrates on the outsourced services only, as these are listed in the European Statistics. The results show big differences between the European countries. It also highlights that the facility service industry is the third largest regarding number of employees and the fourth largest regarding value added.

Quality assurance aspects of the major procurements for the Large Coil Test Facility

International Nuclear Information System (INIS)

Taylor, D.J.; Thompson, P.B.; Ryan, T.L.; Queen, C.C.; Halstead, E.L.; Murphy, J.L.; Wood, R.J.

1983-01-01

The Large Coil Test Facility (LCTF) project is comprised of the test stand, supporting cryogenic systems, instrumentation, data acquisition, and utilities necessary for testing the large superconducting coils of the Large Coil Program (LCP). A significant portion of the facility hardware has been obtained through procurement actions with industrial suppliers. This paper addresses the project's experience in formulation and execution of quality assurance (QA) actions relative to several of the major items procured. Project quality assurance planning and specific features related to procurement activities for several of the more specialized test facility components are described. These component procurements include: (1) the coil test stand's major structural item (the bucking post) purchased from foreign industry; (2) fabrication and testing of high-current power supplies; (3) industrial fabrication of specialized instrumentation (voltage-tap signal conditioning modules); and (4) fabrication, installation, and testing of the liquid helium piping system

Multidisciplinary approach to evaluating welfare of veal calves in commercial facilities.

Science.gov (United States)

Stull, C L; McDonough, S P

1994-09-01

Due to pending legislation and public concerns, a multidisciplinary approach was designed to investigate the welfare of special-fed veal calves in commercial veal facilities. Concerns included housing conditions, dietary regimens, management practices, and behavioral aspects imposed on special-fed calves. Four categories of parameters including environment and housing, nutrition, health and stress, and behavior provided a broad base of evaluating veal systems. Observations and samples were collected on 550 Holstein bull calves located in 10 commercial veal facilities. Each facility was visited to collect data during wk 0 (week of arrival of the calves), 2, 4, 8, 12, and 16. Nine facilities used individual stalls 48 to 55 cm in width with tethers attached to the front of the stalls. One facility housed 30 calves in group pens after obtaining calves at 8 wk of age. Ammonia, carbon monoxide, and hydrogen sulfide gas did not exceed the permissible limit for humans in any facility. All facilities exceeded the 2-foot-candle recommendation for lighting. The average daily gain of calves was .85 kg during wk 0 to 8 and 1.18 kg during wk 8 to 16. Dietary iron levels decreased from 209 ppm at wk 0 to 32 ppm at wk 16. At 16 wk, 25% of calves were marginally anemic and 10% clinically anemic. Overall mortality was 4.2%. Stress indices such as plasma cortisol concentrations or neutrophil to lymphocyte ratios declined as calves approached market weight. In either pens or stalls, calves spent approximately 25 and 75% of time in standing and lying positions, respectively.(ABSTRACT TRUNCATED AT 250 WORDS)

Evaluation of multiple emission point facilities

International Nuclear Information System (INIS)

Miltenberger, R.P.; Hull, A.P.; Strachan, S.; Tichler, J.

1988-01-01

In 1970, the New York State Department of Environmental Conservation (NYSDEC) assumed responsibility for the environmental aspect of the state's regulatory program for by-product, source, and special nuclear material. The major objective of this study was to provide consultation to NYSDEC and the US NRC to assist NYSDEC in determining if broad-based licensed facilities with multiple emission points were in compliance with NYCRR Part 380. Under this contract, BNL would evaluate a multiple emission point facility, identified by NYSDEC, as a case study. The review would be a nonbinding evaluation of the facility to determine likely dispersion characteristics, compliance with specified release limits, and implementation of the ALARA philosophy regarding effluent release practices. From the data collected, guidance as to areas of future investigation and the impact of new federal regulations were to be developed. Reported here is the case study for the University of Rochester, Strong Memorial Medical Center and Riverside Campus

Advanced accounting techniques in automated fuel fabrication facilities

International Nuclear Information System (INIS)

Carlson, R.L.; DeMerschman, A.W.; Engel, D.W.

1977-01-01

The accountability system being designed for automated fuel fabrication facilities will provide real-time information on all Special Nuclear Material (SNM) located in the facility. It will utilize a distributed network of microprocessors and minicomputers to monitor material movement and obtain nuclear materials measurements directly from remote, in-line Nondestructive Assay instrumentation. As SNM crosses an accounting boundary, the accountability computer will update the master files and generate audit trail records. Mass balance accounting techniques will be used around each unit process step, while item control will be used to account for encapsulated material, and SNM in transit

High level radioactive waste management facility design criteria

International Nuclear Information System (INIS)

Sheikh, N.A.; Salaymeh, S.R.

1993-01-01

This paper discusses the engineering systems for the structural design of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS). At the DWPF, high level radioactive liquids will be mixed with glass particles and heated in a melter. This molten glass will then be poured into stainless steel canisters where it will harden. This process will transform the high level waste into a more stable, manageable substance. This paper discuss the structural design requirements for this unique one of a kind facility. A special emphasis will be concentrated on the design criteria pertaining to earthquake, wind and tornado, and flooding

Renovating animal facilities to withstand disasters.

Science.gov (United States)

Cartwright, Jim; Contratto, Jim; Gould, Nathan; Freeman, William

2013-10-01

In the aftermath of Superstorm Sandy, new attention has been drawn to planning for and mitigating the effects of disasters on laboratory animal facilities. A number of design approaches and solutions can be easily incorporated into a new vivarium, enhancing its ability to withstand and recover from a disaster. Renovating a vivarium poses special challenges, however. Existing conditions in the project area may dictate which approaches or solutions are feasible, and retrofitting is often more complex and expensive than incorporating the same features into new construction. The authors explain how project design teams can evaluate the types of disasters that a renovated facility will need to address and develop a design strategy that responds to these disasters in the most effective way.

The high-energy dual-beam facility

International Nuclear Information System (INIS)

Kaletta, D.

1984-07-01

This proposal presents a new experimental facility at the Kernforschungszentrum Karlsruhe (KfK) to study the effects of irradiation on the first wall and blanket materials of a fusion reactor. A special effort is made to demonstrate the advantages of the Dual Beam Technique (DBT) as a future research tool for materials development within the European Fusion Technology Programme. The Dual-Beam-Technique allows the production both of helium and of damage in thick metal and ceramic specimens by simultaneous irradiation with high energy alpha particles and protons produced by the two KfK cyclotrons. The proposal describes the Dual Beam Technique the planned experimental activities and the design features of the Dual Beam Facility presently under construction. (orig.) [de

The NAF: National analysis facility at DESY

International Nuclear Information System (INIS)

Haupt, Andreas; Kemp, Yves

2010-01-01

Within the framework of a broad collaboration among German particle physicists, the strategic Helmholtz Alliance P hysics a the Terascale , an analysis facility has been set up at DESY. The facility is intended to provide the best possible analysis infrastructure for researches of the ATLAS, CMS, LHCb and ILC experiments and also for theory researchers. In a first part of the contribution, we will present the concept of the NAF and its place in the existing distributed grid landscape of the experiments. In a second part, the building blocks of the NAF will be detailed with an emphasis on technical implementations of some parts: - Usage of VOMS for separating grid resources between collaboration-wide and NAF-specific resources. - interactive and batch cluster and integration with PROOF. - usage of grid proxies to access work group servers and AFS. - the usage and operation of Lustre for fast data access. A special focus is the seamless integration of the facility into the two geographically separated DESY sites and its implications. In a third part, the experience of running the facility for one year will be reported.

Approaches to the management of waste from health care facilities in Czech Republic and Kazakhstan

OpenAIRE

Kaireshev, Ruslan

2015-01-01

Waste from healthcare facilities or similar facilities includes components of various physical, chemical and biological character that require special approaches during the handling, specifically with regard to possible risks to human health and the environment. Nowadays a challenge for waste management system becomes waste produced in healthcare facilities and contributes too many reasons, such as population growth and rising life expectancy. The rate of waste production from healthcare faci...

Biosecurity measures in 48 isolation facilities managing highly infectious diseases.

Science.gov (United States)

Puro, Vincenzo; Fusco, Francesco M; Schilling, Stefan; Thomson, Gail; De Iaco, Giuseppina; Brouqui, Philippe; Maltezou, Helena C; Bannister, Barbara; Gottschalk, René; Brodt, Hans-Rheinhard; Ippolito, Giuseppe

2012-06-01

Biosecurity measures are traditionally applied to laboratories, but they may also be usefully applied in highly specialized clinical settings, such as the isolation facilities for the management of patients with highly infectious diseases (eg, viral hemorrhagic fevers, SARS, smallpox, potentially severe pandemic flu, and MDR- and XDR-tuberculosis). In 2009 the European Network for Highly Infectious Diseases conducted a survey in 48 isolation facilities in 16 European countries to determine biosecurity measures for access control to the facility. Security personnel are present in 39 facilities (81%). In 35 facilities (73%), entrance to the isolation area is restricted; control methods include electronic keys, a PIN system, closed-circuit TV, and guards at the doors. In 25 facilities (52%), identification and registration of all staff entering and exiting the isolation area are required. Access control is used in most surveyed centers, but specific lacks exist in some facilities. Further data are needed to assess other biosecurity aspects, such as the security measures during the transportation of potentially contaminated materials and measures to address the risk of an "insider attack."

Decommissioning of nuclear power facilities

International Nuclear Information System (INIS)

Nosovskij, A.V.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Yashchenko, Ya.V.

2005-01-01

This is the first manual in Ukraine giving the complete review of the decommissioning process of the nuclear power facilities including the issues of the planning, design documentation development, advanced technology description. On the base of the international and domestic experience, the issues on the radwaste management, the decontamination methods, the equipment dismantling, the remote technology application, and also the costs estimate at decommissioning are considered. The special attention to the personnel safety provision, population and environment at decommissioning process is paid

Support facilities

International Nuclear Information System (INIS)

Williamson, F.S.; Blomquist, J.A.; Fox, C.A.

1977-01-01

Computer support is centered on the Remote Access Data Station (RADS), which is equipped with a 1000 lpm printer, 1000 cpm reader, and a 300 cps paper tape reader with 500-foot spools. The RADS is located in a data preparation room with four 029 key punches (two of which interpret), a storage vault for archival magnetic tapes, card files, and a 30 cps interactive terminal principally used for job inquiry and routing. An adjacent room provides work space for users, with a documentation library and a consultant's office, plus file storage for programs and their documentations. The facility has approximately 2,600 square feet of working laboratory space, and includes two fully equipped photographic darkrooms, sectioning and autoradiographic facilities, six microscope cubicles, and five transmission electron microscopes and one Cambridge scanning electron microscope equipped with an x-ray energy dispersive analytical system. Ancillary specimen preparative equipment includes vacuum evaporators, freeze-drying and freeze-etching equipment, ultramicrotomes, and assorted photographic and light microscopic equipment. The extensive physical plant of the animal facilities includes provisions for holding all species of laboratory animals under controlled conditions of temperature, humidity, and lighting. More than forty rooms are available for studies of the smaller species. These have a potential capacity of more than 75,000 mice, or smaller numbers of larger species and those requiring special housing arrangements. There are also six dog kennels to accommodate approximately 750 dogs housed in runs that consist of heated indoor compartments and outdoor exercise areas

Characteristics of U.S. Mental Health Facilities That Offer Suicide Prevention Services.

Science.gov (United States)

Kuramoto-Crawford, S Janet; Smith, Kelley E; McKeon, Richard

2016-01-01

This study characterized mental health facilities that offer suicide prevention services or outcome follow-up after discharge. The study analyzed data from 8,459 U.S. mental health facilities that participated in the 2010 National Mental Health Services Survey. Logistic regression analyses were used to compare facilities that offered neither of the prevention services with those that offered both or either service. About one-fifth of mental health facilities reported offering neither suicide prevention services nor outcome follow-up. Approximately one-third offered both, 25% offered suicide prevention services only, and 21% offered only outcome follow-up after discharge. Facilities that offered neither service were less likely than facilities that offered either to offer comprehensive support services or special programs for veterans; to offer substance abuse services; and to be accredited, licensed, or certified. Further examination of facilitators and barriers in implementing suicide prevention services in mental health facilities is warranted.

Criteria, standards and policies regarding decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Detilleux, E.; Lennemann, W.

1977-01-01

The paper discusses the decontamination and decommissioning experiences encountered at the Eurochemic fuel reprocessing plant, their implications and the knowledge gained from these experiences. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The conlusions which are presented should weigh heavily in the considerations of the national authorities involved in regulating nuclear power programmes. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who jointly should make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities [fr

Licensed fuel facility status report. Inventory difference data, July 1, 1995--June 30, 1996

International Nuclear Information System (INIS)

Pham, T.N.

1998-02-01

The U.S. Nuclear Regulatory Commission is committed to an annual publication of licensed fuel cycle facility inventory difference data, following Agency review of the information and completion of any related investigations. Information in this report includes inventory difference results for active fuel fabrication facilities possessing more than one effective kilogram of special nuclear material. 1 tab

NDA for a new facility at SRP

International Nuclear Information System (INIS)

Studley, R.V.

1987-01-01

In 1980, plans were initiated to build a new facility to process high purity highly enriched 235 U. Interest in improving nuclear safeguards had been increasing in the previous few years. A basic objective of the design, therefore, included achievement of maximum performance in special nuclear material (SNM) accountability. A near-real-time accountability system with high accuracy assay measurements was developed for this purpose. Simultaneous design of facility, process equipment, and the accountability system allowed maximum integration of equipment and also permitted influence on process design and material characteristics to optimize accountability performance. This was an ideal situation in which to pursue maximum improvement in nondestructive assay (NDA) measurement performance. The resulting systems are described

The inner-city Skater Facility - playground or control mechanism?

DEFF Research Database (Denmark)

Gravesen, David Thore

2016-01-01

special Social services, School and Police unit), that observe, mingle and socialize at the facility. The social workers affiliated with the SSP understand and define their role in contradiction to the official agenda. The social workers seek to pull the young people off the street and get them to enroll......The inner-city Skater Facility - playground or control mechanism? In 2013, the municipality in Horsens, a medium-sized provincial town in Denmark, bestowed the city's children and young people a skater facility at the city's central squares. Officially, the municipality donated the facility to give...... local children and young people an opportunity to use their leisure time stimulating their bodies, having a great time with friends and other urban dwellers. The gift is accompanied by a number of (more or less camouflaged) crime prevention- and social education agendas, carried out by the SSP (a...

18 CFR 292.208 - Special requirements for hydroelectric small power production facilities located at a new dam or...

Science.gov (United States)

2010-04-01

... for hydroelectric small power production facilities located at a new dam or diversion. 292.208 Section... requirements for hydroelectric small power production facilities located at a new dam or diversion. (a) A hydroelectric small power production facility that impounds or diverts the water of a natural watercourse by...

Fast Flux Test Facility replacement of a primary sodium pump

International Nuclear Information System (INIS)

Krieg, S.A.; Thomson, J.D.

1985-01-01

The Fast Flux Test Facility is a 400 MW Thermal Sodium Cooled Fast Reactor operated by Westinghouse Hanford Company for the US Department of Energy. During startup testing in 1979, the sodium level in one of the primary sodium pumps was inadvertently raised above the normal height. This resulted in distortion of the pump shaft. Pump replacement was carried out using special maintenance equipment. Nuclear radiation and contamination were not significant problems since replacement operations were carried out shortly after startup of the Fast Flux Test Facility

Radiological performance assessment for the E-Area Vaults Disposal Facility

International Nuclear Information System (INIS)

Cook, J.R.

2000-01-01

This report is the first revision to ''Radiological Performance Assessment for the E-Area Vaults Disposal Facility, Revision 0'', which was issued in April 1994 and received conditional DOE approval in September 1994. The title of this report has been changed to conform to the current name of the facility. The revision incorporates improved groundwater modeling methodology, which includes a large data base of site specific geotechnical data, and special Analyses on disposal of cement-based wasteforms and naval wastes, issued after publication of Revision 0

In Vivo Radiobioassay and Research Facility

International Nuclear Information System (INIS)

Lynch, Timothy P.

2011-01-01

Bioassay monitoring for intakes of radioactive material is an essential part of the internal dosimetry program for radiation workers at the Department of Energy's (DOE) Hanford Site. This monitoring program includes direct measurements of radionuclides in the body by detecting photons that exit the body and analyses of radionuclides in excreta samples. The specialized equipment and instrumentation required to make the direct measurements of these materials in the body are located at the In Vivo Radiobioassay and Research Facility (IVRRF). The IVRRF was originally built in 1960 and was designed expressly for the in vivo measurement of radioactive material in Hanford workers. Most routine in vivo measurements are performed annually and special measurements are performed as needed. The primary source terms at the Hanford Site include fission and activation products (primarily 137Cs and 90Sr), uranium, uranium progeny, and transuranic radionuclides. The facility currently houses five shielded counting systems, men's and women's change rooms and an instrument maintenance and repair shop. Four systems include high purity germanium detectors and one system utilizes large sodium iodide detectors. These systems are used to perform an average of 7,000 measurements annually. This includes approximately 5000 whole body measurements analyzed for fission and activation products and 2000 lung measurements analyzed for americium, uranium, and plutonium. Various other types of measurements are performed periodically to estimate activity in wounds, the thyroid, the liver, and the skeleton. The staff maintains the capability to detect and quantify activity in essentially any tissue or organ. The in vivo monitoring program that utilizes the facility is accredited by the Department of Energy Laboratory Accreditation Program for direct radiobioassay.

International safeguards for fast critical facilities

International Nuclear Information System (INIS)

Gunderson, D.O.; Todd, J.L.

1978-12-01

It was concluded that practical routine inventory verification techniques can be effective in detecting protracted diversion but will not meet the seven-day timeliness criteria either for protracted or large one-time diversions. An effective international safeguards system requires a method of continuously monitoring facility activities either with instrumentation, inspectors, or a combination thereof. It was also concluded that a resident inspector is required at this type of facility because of the many nonroutine operations. However, a single inspector cannot adequately monitor all activities to assure that no diversion is taking place. The use of existing structural features and unattended monitoring at portals as well as surveillance by a resident inspector can provide an effective detection capability. A rapid special inventory verification is required following detection to verify any suspected diversion

Health physics and quality control management of a cyclotron-based PET facility

International Nuclear Information System (INIS)

Jerabek, P.A.

1995-01-01

This paper provides an overview of the operation and management of a Positron Emission Tomography (PET) facility at the University of Texas. The facility components are discussed from an operations perspective with an emphasis on devices, and on practices and procedures which are implemented to ensure that personnel exposures are as low as reasonably achievable. The cyclotron-based PET facility uses in-house production of PET radioisotopes for preparation of radiopharmaceuticals. A combination of specially designed cyclotron equipped devices, radiopharmaceutical preparation devices, and shielded devices along with health physics practices have helped to make PET operations become routine

Catering for children with special needs in the regular classroom ...

African Journals Online (AJOL)

The National Policy on Education specifically stipulates that there is need for equality of educational opportunities to all Nigerian children irrespective of any real or imagined disabilities (FNG 2004). The policy further states that Education of children with special needs shall be free at all levels and all necessary facilities that ...

Power Reactor Thoria Reprocessing Facility (PRTRF), Trombay

International Nuclear Information System (INIS)

Dhami, P.S; Yadav, J.S; Agarwal, K.

2017-01-01

Exploitation of the abundant thorium resources to meet sustained energy demand forms the basis of the Indian nuclear energy programme. To gain reprocessing experience in thorium fuel cycle, thoria was irradiated in research reactor CIRUS in early sixties. Later in eighties, thoria bundles were used for initial flux flattening in some of the pressurized heavy water reactors (PHWRs). The research reactor irradiated thoria contained small content (∼ 2-3ppm) of "2"3"2U in "2"3"3U product, which did not pose any significant radiological problems during processing in Uranium Thorium Separation Facility (UTSF), Trombay. Thoria irradiated in PHWRs on discharge contained (∼ 0.5-1.5% "2"3"3U with significant "2"3"2U content (100-500 ppm) requiring special radiological attention. Based on the experience from UTSF, a new facility viz. Power Reactor Thoria Reprocessing Facility (PRTRF), Trombay was built which was hot commissioned in the year 2015

General problems specific to hot nuclear materials research facilities

International Nuclear Information System (INIS)

Bart, G.

1996-01-01

During the sixties, governments have installed hot nuclear materials research facilities to characterize highly radioactive materials, to describe their in-pile behaviour, to develop and test new reactor core components, and to provide the industry with radioisotopes. Since then, the attitude towards the nuclear option has drastically changed and resources have become very tight. Within the changed political environment, the national research centres have defined new objectives. Given budgetary constraints, nuclear facilities have to co-operate internationally and to look for third party research assignments. The paper discusses the problems and needs within experimental nuclear research facilities as well as industrial requirements. Special emphasis is on cultural topics (definition of the scope of nuclear research facilities, the search for competitive advantages, and operational requirements), social aspects (overageing of personnel, recruitment, and training of new staff), safety related administrative and technical issues, and research needs for expertise and state of the art analytical infrastructure

Engendering a conducive environment for university students with physical disabilities: assessing availability of assistive facilities in Nigeria.

Science.gov (United States)

Ijadunola, Macellina Y; Ojo, Temitope O; Akintan, Florence O; Adeyemo, Ayoade O; Afolayan, Ademola S; Akanji, Olakunle G

2018-03-12

This study assessed awareness and availability of assistive facilities in a Nigerian public university. Study was conducted in Obafemi Awolowo University (OAU), Ile Ife Nigeria using a mixed methods approach. Fifty two students with disability (SWD) were interviewed with a semistructured, self-administered questionnaire. A checklist was used to assess assistive facilities on campus while in-depth interviews (IDI) were conducted with university officials, to assess their perspectives about the availability and use of assistive facilities in the university. Almost three-thirds (57.7%) of SWD were male while more than two-thirds were aged between 21 and 30 years. About seven in 10 (71.1%) respondents, had mobility impairment, while two-fifth had visual impairment (40.8%) and a few had hearing impairment. Only the university's administrative building had a functioning elevator. Slightly more than half (54.5%) of the lecture theatres have public address systems, while only two have special entrances and exits with ramps for SWD. Almost all respondents were unaware of facilities that aid learning (96.2%) and facilities for library use (90.4%). University officials were aware of assistive facilities for SWD but do not know the actual number of SWD. Assistive facilities for SWD on campus are limited. More assistive facilities need to be provided alongside increased awareness about these facilities and a disability register should be open for students on campus. Assistive facilities to aid learning and make SWD more comfortable are required. Implications for Rehabilitation Universities should have an official policy on students with disabilities and implement it, such a policy should address special considerations for disabled students, such as having an updated register for students with disability, having examination questions in large fonts for students with visual disabilities, giving them extra time for examinations and providing special counselling services for

Off-Site Storage and Special Collections: A Study in Use and Impact in ARL Libraries in the United States

Science.gov (United States)

Priddle, Charlotte; McCann, Laura

2015-01-01

Special collections libraries collect and preserve materials of intellectual and cultural heritage, providing access to unique research resources. As their holdings continue to expand, special collections in research libraries confront increased space pressures. Off-site storage facilities, used frequently by research libraries for general…

Concepts for inventory verification in critical facilities

International Nuclear Information System (INIS)

Cobb, D.D.; Sapir, J.L.; Kern, E.A.; Dietz, R.J.

1978-12-01

Materials measurement and inventory verification concepts for safeguarding large critical facilities are presented. Inspection strategies and methods for applying international safeguards to such facilities are proposed. The conceptual approach to routine inventory verification includes frequent visits to the facility by one inspector, and the use of seals and nondestructive assay (NDA) measurements to verify the portion of the inventory maintained in vault storage. Periodic verification of the reactor inventory is accomplished by sampling and NDA measurement of in-core fuel elements combined with measurements of integral reactivity and related reactor parameters that are sensitive to the total fissile inventory. A combination of statistical sampling and NDA verification with measurements of reactor parameters is more effective than either technique used by itself. Special procedures for assessment and verification for abnormal safeguards conditions are also considered. When the inspection strategies and inventory verification methods are combined with strict containment and surveillance methods, they provide a high degree of assurance that any clandestine attempt to divert a significant quantity of fissile material from a critical facility inventory will be detected. Field testing of specific hardware systems and procedures to determine their sensitivity, reliability, and operational acceptability is recommended. 50 figures, 21 tables

Monitoring of the storage facility Asse II

International Nuclear Information System (INIS)

Regenauer, Urban; Wittwer, Christiane

2012-01-01

The storage facility Asse II is former salt mine near Wolfenbuettel in Niedersachsen. From 1967 to 1978 totally 125787 barrels with low-and medium-level radioactive wastes were disposed in the salt cavern. Since 1988 ingress of saturated brines from the adjoining rocks were observed in the mine. An extensive monitoring concept was installed for the surveillance of possible radionuclides released with the mine air into the surrounding. The report is aimed to n describe the actual situation in the salt mine Asse II with special emphasis to the monitoring concept. The discussion is based on the history of the storage facility that was primarily a research mine. Furthermore a regional accompanying process is described that was created in 2007.

3718-F Alkali Metal Treatment and Storage Facility Closure Plan. Revision 1

Energy Technology Data Exchange (ETDEWEB)

None

1992-11-01

The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed.

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

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Schedule of fees for production and utilization facilities, review of standard referenced design approvals, special projects, inspections and import and export... AMENDED Schedule of Fees § 170.21 Schedule of fees for production and utilization facilities, review of...

Breast cancer screening activity in the Mie medical network, with special reference to the actual circumstances of detailed examination

International Nuclear Information System (INIS)

Nakai, Masahiro; Kawaguchi, Kanako; Kobayashi, Shigeki

2009-01-01

For clarifying both the current circumstances and problems of closed examination performed at facilities equipped for detailed examination in Mie Prefecture, we analyzed the results of closed examinations carried out on 1,001 responders who were selected by primary mammography screening done at 87 facilities in 2006. The overall breast cancer detection rate was 3.3%, with a range of 0-10.3%, for facilities that included family doctors, and 13 hospitals having performed the closed examination on 21 women or more. Although the location of a facility for closed examination and the background of examinees might be taken into consideration, it appeared that a higher cancer detection rate was obtained when more pathological examinations were carried out, and that the indications for pathological examination varied among physicians. At facilities where pathological examinations were frequently performed, mostly clinicians specializing in breast cancer performed either fine-needle aspiration biopsy or large-needle biopsy (a specific aspiration biopsy technique for calcified lesions), whereas at facilities with low rates of pathological examination, most surgeons not specializing in breast cancer performed open biopsy. These results suggest a need to draw up guidelines for detailed examination, including the standard of facilities for closed examination, clinicians who perform the examinations, and the examination methods. (author)

Defense waste processing facility radioactive operations. Part 1 - operating experience

International Nuclear Information System (INIS)

Little, D.B.; Gee, J.T.; Barnes, W.M.

1997-01-01

The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation's first and the world's largest vitrification facility. Following a ten year construction program and a 3 year non-radioactive test program, DWPF began radioactive operations in March 1996. This paper presents the results of the first 9 months of radioactive operations. Topics include: operations of the remote processing equipment reliability, and decontamination facilities for the remote processing equipment. Key equipment discussed includes process pumps, telerobotic manipulators, infrared camera, Holledge trademark level gauges and in-cell (remote) cranes. Information is presented regarding equipment at the conclusion of the DWPF test program it also discussed, with special emphasis on agitator blades and cooling/heating coil wear. 3 refs., 4 figs

Defense Waste Processing Facility -- Radioactive operations -- Part 3 -- Remote operations

International Nuclear Information System (INIS)

Barnes, W.M.; Kerley, W.D.; Hughes, P.D.

1997-01-01

The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, South Carolina is the nation's first and world's largest vitrification facility. Following a ten year construction period and nearly three years of non-radioactive testing, the DWPF began radioactive operations in March 1996. Radioactive glass is poured from the joule heated melter into the stainless steel canisters. The canisters are then temporarily sealed, decontaminated, resistance welded for final closure, and transported to an interim storage facility. All of these operations are conducted remotely with equipment specially designed for these processes. This paper reviews canister processing during the first nine months of radioactive operations at DWPF. The fundamental design consideration for DWPF remote canister processing and handling equipment are discussed as well as interim canister storage

The US nuclear science user facilities - 5276

International Nuclear Information System (INIS)

Kennedy, J.R.

2015-01-01

The primary mission of the NSUF (Nuclear Science User Facilities) is to provide access, at no cost to the researcher, to world-class, state-of-the art capabilities and expertise to advance nuclear science and technology through high impact research. Through the NSUF, nuclear energy researchers can access specialized and often unique and expensive equipment and facilities, as well as the accompanying expertise, including nuclear test reactors, ion beam accelerators, hot cell post-irradiation examination (PIE) equipment, synchrotron beam lines, and advanced radiologically qualified materials science PIE instrumentation. The NSUF can also support the design and fabrication of an irradiation experiment, the transport of that experiment to and from the reactor, the PIE activities, the analysis and interpretation of the data, and final material disposition. A special feature of the NSUF is its Sample Library of irradiated specimens made available to users that reduces investigation time and costs. Enhancing the Sample Library for future applications of advanced instrumentation and new ideas is a key goal of the NSUF. Similar to the effort on building a Sample Library, the NSUF is creating a searchable database of the infrastructure available to DOE-NE (Department Of Energy - Office of Nuclear Energy) supported researchers

Licensed fuel facility status report: Inventory difference data, July 1, 1994--June 30, 1995. Volume 15

International Nuclear Information System (INIS)

Joy, D.R.

1996-05-01

The Nuclear Regulatory Commission (NRC) is committed to the periodic publication of licensed fuel facility inventory difference data, following agency review of the information and completion of any related NRC investigations. Information in this report includes inventory difference data for active fuel fabrication facilities possessing more than one effective kilogram of special nuclear material

Health Care Needs of Prison Inmates: Treating a population that has special needs

OpenAIRE

Wachsmuth, Anne

1991-01-01

Prisoners in correctional facilities constitute a unique population requiring specialized medical care. Drug withdrawal, self-destructive behavior, infectious diseases (including AIDS), and serious mental disorders are some of the challenges to the physician who provides medical services to these inmates.

42 CFR 412.104 - Special treatment: Hospitals with high percentage of ESRD discharges.

Science.gov (United States)

2010-10-01

..., DEPARTMENT OF HEALTH AND HUMAN SERVICES MEDICARE PROGRAM PROSPECTIVE PAYMENT SYSTEMS FOR INPATIENT HOSPITAL SERVICES Special Treatment of Certain Facilities Under the Prospective Payment System for Inpatient... established that ESRD beneficiary discharges, excluding discharges classified into MS-DRG 652 (Renal Failure...

The Radiological Research Accelerator Facility:

International Nuclear Information System (INIS)

Hall, E.J.; Goldhagen, P.

1988-07-01

The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generated a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Radiological Research Laboratory (RRL) of Columbia University, and its operation is supported as a National Facility by the U.S. Department of Energy. As such, RARAF is available to all potential users on an equal basis, and scientists outside the RRL are encouraged to submit proposals for experiments at RARAF. Facilities and services are provided to users, but the research projects themselves must be supported separately. RARAF was located at BNL from 1967 until 1980, when it was dismantled and moved to the Nevis Laboratories of Columbia University, where it was then reassembled and put back into operation. Data obtained from experiment using RARAF have been of pragmatic value to radiation protection and to neutron therapy. At a more fundamental level, the research at RARAF has provided insight into the biological action of radiation and especially its relation to energy distribution in the cell. High-LET radiations are an agent of special importance because they can cause measurable cellular effects by single particles, eliminating some of the complexities of multievent action and more clearly disclosing basic features. This applies particularly to radiation carcinogenesis. Facilities are available at RARAF for exposing objects to different radiations having a wide range of linear energy transfers (LETs)

Los Alamos Critical Experiments Facility

International Nuclear Information System (INIS)

Malenfant, R.E.

1991-01-01

The Critical Experiments Facility of the Los Alamos National Laboratory has been in existence for 45 years. In that period of time, thousands of measurements have been made on assemblies containing every fissionable material in various configurations that included bare metal and compounds of the nitrate, sulfate, fluoride, carbide, and oxide. Techniques developed or applied include Rossi-α, source-jerk, rod oscillator, and replacement measurements. Many of the original measurements of delay neutrons were performed at the site, and a replica of the Hiroshima weapon was operated at steady state to assist in evaluating the relative biological effectiveness (RBE) of neutrons. Solid, liquid, and gas fissioning systems were run at critical. Operation of this original critical facility has demonstrated the margin of safety that can be obtained through remote operation. Eight accidental excursions have occurred on the site, ranging from 1.5 x 10 16 to 1.2 x 10 17 fissions, with no significant exposure to personnel or damage to the facility beyond the machines themselves -- and in only one case was the machine damaged beyond further use. The present status of the facility, operating procedures, and complement of machines will be described in the context of programmatic activity. New programs will focus on training, validation of criticality alarm systems, experimental safety assessment of process applications, and dosimetry. Special emphasis will be placed on the incorporation of experience from 45 years of operation into present procedures and programs. 3 refs

105-DR Large Sodium Fire Facility decontamination, sampling, and analysis plan

International Nuclear Information System (INIS)

Knaus, Z.C.

1995-01-01

This is the decontamination, sampling, and analysis plan for the closure activities at the 105-DR Large Sodium Fire Facility at Hanford Reservation. This document supports the 105-DR Large Sodium Fire Facility Closure Plan, DOE-RL-90-25. The 105-DR LSFF, which operated from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility in the 100-D Area of the Hanford Site. The LSFF was established to investigate fire fighting and safety associated with alkali metal fires in the liquid metal fast breeder reactor facilities. The decontamination, sampling, and analysis plan identifies the decontamination procedures, sampling locations, any special handling requirements, quality control samples, required chemical analysis, and data validation needed to meet the requirements of the 105-DR Large Sodium Fire Facility Closure Plan in compliance with the Resource Conservation and Recovery Act

Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

International Nuclear Information System (INIS)

1978-03-01

Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase future decommissioning needs, the NRC staff began an in-depth review and re-evaluation of NRC's regulatory approach to decommissioning in 1975. Major technical studies on decommissioning have been initiated at Battelle Pacific Northwest Laboratory in order to provide a firm information base on the engineering methodology, radiation risks, and estimated costs of decommissioning light water reactors and associated fuel cycle facilities. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. The report sets forth in detail the NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

Summary on experimental facilities and future developments at SINQ

Energy Technology Data Exchange (ETDEWEB)

Bauer, G S [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

1996-11-01

With 13 experimental facilities under construction to become available during the first year of SINQ operation, a nearly complete suite of options for users will be made available to carry out research with neutrons at PSI. Three more facilities are under design and will come on line somewhat later. To complete the suite, three more specialized instruments are being evaluated. SINQ being a novel neutron source concept, significant scope for improvement is also seen on the source side. It is a major goal of PSI to exploit these opportunities and to make - among others - use of neutron instruments to carry out the necessary research. (author) 9 figs., 1 tab., 11 refs.

Waste Encapsulation and Storage Facility (WESF) Waste Analysis Plan

International Nuclear Information System (INIS)

SIMMONS, F.M.

2000-01-01

The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Waste Encapsulation and Storage Facility (WESF) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (3), (4), (5), and (6). WESF is an interim status other storage-miscellaneous storage unit. WESF stores mixed waste consisting of radioactive cesium and strontium salts. WESF is located in the 200 East Area on the Hanford Facility. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

Neuropsychiatric Symptoms in People With Korsakoff Syndrome and Other Alcohol-Related Cognitive Disorders Living in Specialized Long-Term Care Facilities: Prevalence, Severity, and Associated Caregiver Distress.

Science.gov (United States)

Gerridzen, Ineke J; Hertogh, Cees M P M; Depla, Marja F; Veenhuizen, Ruth B; Verschuur, Els M L; Joling, Karlijn J

2018-03-01

Caring for people with Korsakoff syndrome (KS) residing in specialized long-term care facilities (LTCFs) can be distressing because of challenging neuropsychiatric symptoms (NPS). However, good-quality studies on NPS in this under-researched population are lacking. This study examined the prevalence and severity of NPS in people with KS living in specialized LTCFs and the associated caregiver distress. Cross-sectional, observational study. Data were obtained using structured interviews with care staff, elderly care physicians, and residents. Nine specialized LTCFs in the Netherlands. KS residents admitted for at least 3 months. The prevalence and severity of NPS were measured with the Neuropsychiatric Inventory-Questionnaire (NPI-Q). The associated caregiver distress was assessed with the NPI Distress Scale (NPI-D) according to the nurse or nurse assistant. Almost all of the 281 residents (96.4%) showed at least 1 NPS and 45.8% showed 5 or more symptoms. Irritability/lability (68.3%), agitation/aggression (58.7%), and disinhibition (52.7%) were most prevalent. Although the mean level of severity for all NPS was relatively low, half of the residents (49.1%) had at least 1 severe NPS. Care staff experienced low levels of distress associated with NPS. NPS are highly prevalent in KS residents. Unexpectedly, these did not have any severe impact on residents and care staff. Acquiring more insight into the persistence and course of NPS, and its associations, among KS residents is important to better understand and reduce these symptoms and, ultimately, improve the quality of care for these residents. Copyright © 2017 AMDA – The Society for Post-Acute and Long-Term Care Medicine. Published by Elsevier Inc. All rights reserved.

Semi-annual report on strategic special nuclear material inventory differences

International Nuclear Information System (INIS)

1981-08-01

This eighth periodic semiannual report of inventory differences covers the second six months of fiscal year 1980 (April 1, 1980, through September 30, 1980), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic special nuclear material. Strategic special nuclear material is plutonium or uranium-233 or uranium-235 in material whose uranium-235 content is 20 percent or greater (known as highly enriched uranium). A significant quantity is either 2 kilograms of plutonium or uranium-233 or 5 kilograms of uranium-235 in highly enriched uranium or the appropriate weighted combination. All Inventory Differences reported here have been analyzed, investigated when necessary, and resolved. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic special nuclear material has occurred

Steps for safety. Radioactive waste management facilities and Y2K

International Nuclear Information System (INIS)

Warnecke, E.

1999-01-01

As part of the IAEA activities concerned with Year 2000 (Y2K) problem special attention is paid to operation of radioactive waste management facilities although, fortunately, in the management of radioactive materials the response of a process or activity to a failure would be slow in many instance, providing more time to resolve the issue before any radiological consequences occur. To facilitate greater cooperation, the IAEA organized an international workshop on the exchange of information concerning safety measure to address the Y2K issues on radioactive waste management and nuclear fuel cycle facilities

Healthcare waste management: current practices in selected healthcare facilities, Botswana.

Science.gov (United States)

Mbongwe, Bontle; Mmereki, Baagi T; Magashula, Andrew

2008-01-01

Healthcare waste management continues to present an array of challenges for developing countries, and Botswana is no exception. The possible impact of healthcare waste on public health and the environment has received a lot of attention such that Waste Management dedicated a special issue to the management of healthcare waste (Healthcare Wastes Management, 2005. Waste Management 25(6) 567-665). As the demand for more healthcare facilities increases, there is also an increase on waste generation from these facilities. This situation requires an organised system of healthcare waste management to curb public health risks as well as occupational hazards among healthcare workers as a result of poor waste management. This paper reviews current waste management practices at the healthcare facility level and proposes possible options for improvement in Botswana.

41 CFR 102-37.180 - Does a SASP need special authorization to screen property at Federal facilities?

Science.gov (United States)

2010-07-01

... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Does a SASP need special...) Screening and Requesting Property § 102-37.180 Does a SASP need special authorization to screen property at... do not need a screener-ID card to inspect or remove property previously set aside or approved by GSA...

The cascad spent fuel dry storage facility

International Nuclear Information System (INIS)

Guay, P.; Bonnet, C.

1991-01-01

France has a wide variety of experimental spent fuels different from LWR spent fuel discharged from commercial reactors. Reprocessing such fuels would thus require the development and construction of special facilities. The French Atomic Energy Commission (CEA) has consequently opted for long-term interim storage of these spent fuels over a period of 50 years. Comparative studies of different storage concepts have been conducted on the basis of safety (mainly containment barriers and cooling), economic, modular design and operating flexibility criteria. These studies have shown that dry storage in a concrete vault cooled by natural convection is the best solution. A research and development program including theoretical investigations and mock-up tests confirmed the feasibility of cooling by natural convection and the validity of design rules applied for fuel storage. A facility called CASCAD was built at the CEA's Cadarache Nuclear Research Center, where it has been operational since mid-1990. This paper describes the CASCAD facility and indicates how its concept can be applied to storage of LWR fuel assemblies

Calculation of displacement and helium production at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF) irradiation facility

International Nuclear Information System (INIS)

Wechsler, M.S.; Davidson, D.R.; Greenwood, L.R.; Sommer, W.F.

1984-01-01

CT: Differential and total displacement and helium production rates are calculated for copper irradiated by spallation neutrons and 760 MeV protons at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF). The calculations are performed using the SPECTER and VNMTC computer codes, the latter being specially designed for spallation radiation damage calculations. For comparison, similar SPECTER calculations are also described for irradiation of copper in EBR-II and RTNS-II. The results indicate substantial contributions to the displacement and helium production rates due to neutrons in the high-energy tail (above 20 MeV) of the LAMPF spallation neutron spectrum. Still higher production rates are calculated for irradiations in the direct proton beam. These results will provide useful background information for research to be conducted at a new irradiation facility at LAMPF

Dosimetry program for characterization of the FMIT facility

International Nuclear Information System (INIS)

Gold, R.; McElroy, W.N.; Fuller, J.L.; Sheen, E.M.; Dierckx, R.

1979-01-01

The environmental characterization program for the Fusion Materials Irradiaton Test (FMIT) facility is presented. Requirements for the development and testing of Magnetic Fusion Energy (MFE) materials together with the complexity of the FMIT (d,Li) generated radiation field warrant a multifaceted dosimetric approach. Specific passive, active and calculational dosimetry efforts comprising this multifaceted approach are described. Special emphasis is given to those dosimetry capabilities uniquely required to characterize FMIT

Audits of radiation sterilization facilities

International Nuclear Information System (INIS)

Kelkar, Prabhakar M.

2001-01-01

Johnson and Johnson is the world leader in sterilization science and technology. A special group of scientists and technologists are engaged in the development of new methods of sterilization, worldwide monitoring of sterilization processes, equipment and approvals for all types of sterilization processes. Kilmer Conference in the alternate year for the benefit of all those involved in improvement in sterilization science is held. Cobalt-60 gamma radiation for sterilization of medical products on commercial scale is used. This kind of mammoth task can only be achieved through systematic method of planning, auditing, expert review and approval of facilities

A requirement for Australian research: access to 'big science' facilities, a report by the Australian National Committee for crystallography

International Nuclear Information System (INIS)

1989-03-01

Two types of 'Big Science' research facility - synchrotron radiation sources and intense neutron beams - are now recognised as essential resources for a wide range of research activities in chemistry, physics and biology. The cost of such facilities and the lack of a sufficiently large user base will probably preclude their construction in Australia in the foreseeable future. The needs of Australian crystallographers for access to such facilities are assessed. In relation to synchrotron radiation sources, the Committee considered only the question of access to such facilities overseas. In relation to neutron beam sources, the Committee's inquiries included not only the question of access to powerful facilities overseas but also the special problems which confront Australian crystallographers as a result of the obsolescence of the HIFAR reactor. The arguments about, and options for, funding Australian use of facilities overseas are presented. The Committee concluded there is a strong case for the purchase of a beam-line at an overseas synchrotron radiation facility and a strong, though less urgent, case for substantial Australian involvement in an overseas neutron beam facility. The Committee recommended that the Australian HIFAR reactor be refurbished in its present shell, retaining the present flux and power levels, and that in the upgrading of the neutron scattering instrumentation at HIFAR special consideration be given to including items which are sufficiently specialised to attract the international neutron scattering community

Evaluation of the CDTN's cementation facility using the results obtained in two different sizes: laboratory and facility

International Nuclear Information System (INIS)

Haucz, Maria Judite A.; Calabria, Jaqueline A. Almeida; Tello, Cledola Cassia O.; Candido, Francisco Donizete; Seles, Sandro Rogerio Novaes

2011-01-01

At CDTN R and D activities generate low-level radioactive wastes, among them the aqueous liquid ones, which need special attention due to their volumes. The usual treatment for these wastes is the volume reduction process using chemicals in order to change the radionuclides of the waste to an insoluble form. The resultant sludge is incorporated into cement in 200-liter drums using an in-line batch mixing system (CDTN Cementation Facility). The process parameters and solidified product quality are evaluated at the Cementation Laboratory (LABCIM), where tests are carried out to determine the viscosity, set time and density of the paste. In addition of the visual examination, compressive strength test and density are also established in the solidified product. In the cementation facility some pastes are also prepared for the immobilization of non-compactable waste, such as dump, scrap metal, wood, and other ones. This paper aims to present the study comparing the results of tests done in the pastes and products prepared in LABCIM and the ones obtained in CDTN's cementation facility, in order to check the efficiency of the cementation system. (author)

Evaluation of the CDTN cementation facility using the results obtained in two different sizes: laboratory and facility

International Nuclear Information System (INIS)

Haucz, Maria Judite A.; Calabria, Jaqueline A. Almeida; Tello, Cledola Cassia O.; Candido, Francisco Donizete; Seles, Sandro Rogerio Novaes

2011-01-01

At CDTN R and D activities generate low-level radioactive wastes, among them the aqueous liquid ones, which need special attention due to their volumes. The usual treatment for these wastes is the volume reduction process using chemicals in order to change the radionuclides of the waste to an insoluble form. The resultant sludge is incorporated into cement in 200-liter drums using an in-line batch mixing system (CDTN Cementation Facility). The process parameters and solidified product quality are evaluated at the Cementation Laboratory (LABCIM), where tests are carried out to determine the viscosity, set time and density of the paste. In addition of the visual examination, compressive strength test and density are also established in the solidified product. In the cementation facility some pastes are also prepared for the immobilization of non-compactable waste, such as dump, scrap metal, wood, and other ones. This paper aims to present the study comparing the results of tests done in the pastes and products prepared in LABCIM and the ones obtained in CDTN's cementation facility, in order to check the efficiency of the cementation system. (author)

Environmental Monitoring Plan, Nevada Test Site and support facilities

International Nuclear Information System (INIS)

1991-11-01

This Operational Area Monitoring Plan for environmental monitoring, is for EG ampersand G Energy Measurements, Inc. (EG ampersand G/EM) which operates several offsite facilities in support of activities at the Nevada Test Site (NTS). These facilities include: (1) Amador Valley Operations (AVO), Pleasanton, California; (2) Kirtland Operations (KO), Kirtland Air Force base, Albuquerque, New Mexico (KAFB); (3) Las Vegas Area Operations (LVAO), Remote Sensing Laboratory (RSL), and North Las Vegas (NLV) Complex at Nellis Air Force Base (NAFB), North Las Vegas, Nevada; (4) Los Alamos Operations (LAO), Los Alamos, New Mexico; (5) Santa Barbara Operations (SBO), Goleta, California; (6) Special Technologies Laboratory (STL), Santa Barbara, California; (7) Washington Aerial Measurements Department (WAMD), Andrews Air Force Base, Maryland; and, (8) Woburn Cathode Ray Tube Operations (WCO), Woburn, Massachusetts. Each of these facilities has an individual Operational Area Monitoring Plan, but they have been consolidated herein to reduce redundancy

105-DR Large Sodium Fire Facility closure plan

International Nuclear Information System (INIS)

1993-05-01

The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, and activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide a means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950's and is located in the 100-D Area of the Hanford Site. The building housed the 105-DR defense reactor, which was shut down in 1964. The LSFF was initially used only for engineering-scale alkali metal reaction studies. In addition, the Fusion Safety Support Studies program sponsored intermediate-size safety reaction tests in the LSFF with lithium and lithium lead compounds. The facility has also been used to store and treat alkali metal waste, therefore the LSFF is subject to the regulatory requirements for the storage and treatment of dangerous waste. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610. This closure plan presents a description of the facility, the history of waste managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected

Greenhouse Facility Management Experts Identification of Competencies and Teaching Methods to Support Secondary Agricultural Education Instructors: A Modified Delphi Study

Science.gov (United States)

Franklin, Edward A.

2011-01-01

In this study the Delphi technique has been used to develop a list of educational competencies for preparing secondary agricultural education instructors to effectively manage their school greenhouse facilities. The use of specialized facilities in agricultural education requires appropriate preparation of agricultural education teachers. The…

YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).

Energy Technology Data Exchange (ETDEWEB)

Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

2010-04-28

The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

A minisum model with forbidden regions for locating a semi-desirable facility in the plane

DEFF Research Database (Denmark)

Brimberg, Jack; Juel, Henrik

-desirable facility which accounts for the service costs by a standard minisum objective with arbitrary travel distance function. The social costs are imputed by specifying around each demand point or population center a convex forbidden region, also defined by an arbitrary distance metric, in which the new facility...... may not be located. A general solution algorithm is suggested, and the methodology applied to circular forbidden regions and special travel distance functions....

Cathodic protection of a nuclear fuel facility

International Nuclear Information System (INIS)

Corbett, R.A.

1989-01-01

This article discusses corrosion on buried process piping and tanks at a nuclear fuel facility and the steps taken to design a system to control underground corrosion. Collected data have indicated that cathodic protection is needed to supplement the regular use of high-integrity, corrosion-resistant coatings; wrapping systems; special backfills; and insulation material. The technical approach discussed in this article is generally applicable to other types of power and/or industrial plants with extensive networks of underground steel piping

TRIGA International, a new TRIGA fuel fabrication facility at CERCA

International Nuclear Information System (INIS)

Harbonnier, G.

1997-01-01

At the time when General Atomics expressed its intention to cease fuel fabrication on its site of San Diego, CERCA has been chosen to carry on the fabrication of TRIGA fuel. After negotiations in 1994 and 1995, a partnership 50%/50% was decided and on July 1995, a new company was founded, with the name TRIGA INTERNATIONAL SAS, head office in Paris and fuel fabrication facility at CERCA in Romans. The intent of this presentation is, after a short reminder about TRIGA fuel design and fabrication to describe the new facility with special emphasis on the safety features associated with the modification of existing fabrication buildings. (author)

Structural design considerations for a radwaste processing facility

International Nuclear Information System (INIS)

Foelber, S.C.; Sabbe, M.A.

1985-01-01

The structural engineer needs to consider several criteria when designing a radioactive-waste processing facility in order to properly balance the requirements of safety and economy. This paper addresses the design criteria and structural design of a vitrification building and the special equipment and supports associated with remote process operations. In addition, approaches to construction, and the role of scale models to aid in engineering design and construction are discussed. 5 figures

Experience with the instrumentation tests in large sodium test facilities

International Nuclear Information System (INIS)

Lauhoff, Th.; Ruppert, E.; Stehle, H.; Vinzens, K.

1976-01-01

A facility is described for fast breeder core components (AKB) to test specially instrumented fuel dummies and blanket elements, and also absorber elements under simulated normal and extreme reactor conditions. In addition to endurance testing of a special sodium and high temperature sub-assembly, instrumentation is provided to investigate thermohydraulic and vibrational behaviour of core elements. During tests of > 3000 h at temperatures above 820 K the main sub-assembly characteristics, e.g. pressure drop, leakage flow, vibration and noise spectra can be reproduced. The use of eddy current flow meters, strain gauges, magnetostrictive noise sensors, pressure transducers, thermocouples, and acoustic surveillance devices, are described. (U.K.)

The test facility for the short prototypes of the LHC superconducting magnets

International Nuclear Information System (INIS)

Delsolaro, W. Venturini; Arn, A.; Bottura, L.; Giloux, C.; Mompo, R.; Siemko, A.; Walckiers, L.

2002-01-01

The LHC development program relies on cryogenic tests of prototype and model magnets. This vigorous program is pursued in a dedicated test facility based on several vertical cryostats working at superfluid helium temperatures. The performance of the facility is detailed. Goals and test equipment for currently performed studies are reviewed: quench analysis and magnet protection studies, measurement of the field quality, test of ancillary electrical equipment like diodes and busbars. The paper covers the equipment available for tests of prototypes and some special series of LHC magnets to come

The test facility for the short prototypes of the LHC superconducting magnets

Science.gov (United States)

Delsolaro, W. Venturini; Arn, A.; Bottura, L.; Giloux, C.; Mompo, R.; Siemko, A.; Walckiers, L.

2002-05-01

The LHC development program relies on cryogenic tests of prototype and model magnets. This vigorous program is pursued in a dedicated test facility based on several vertical cryostats working at superfluid helium temperatures. The performance of the facility is detailed. Goals and test equipment for currently performed studies are reviewed: quench analysis and magnet protection studies, measurement of the field quality, test of ancillary electrical equipment like diodes and busbars. The paper covers the equipment available for tests of prototypes and some special series of LHC magnets to come.

A New Approach for Analyzing the Reliability of the Repair Facility in a Series System with Vacations

Directory of Open Access Journals (Sweden)

Renbin Liu

2012-01-01

Full Text Available Based on the renewal process theory we develop a decomposition method to analyze the reliability of the repair facility in an n-unit series system with vacations. Using this approach, we study the unavailability and the mean replacement number during (0,t] of the repair facility. The method proposed in this work is novel and concise, which can make us see clearly the structures of the facility indices of a series system with an unreliable repair facility, two convolution relations. Special cases and numerical examples are given to show the validity of our method.

Licensing of ''grandfather's'' facilities: Ukrainian experience

International Nuclear Information System (INIS)

Mikolaitchouk, H.; Bogdan, L.; Steinberg, N.

1995-01-01

In the former USSR, unlike most countries, radioactive waste management activities including waste disposal needed no license. But after the USSR breakdown the Ukrainian Parliament -- Verkhovna Rada -- invoked the revised Law on Business activities. According to Article 4 of the Law, in order to treat or to dispose radioactive waste every enterprise has to get a special permission or license. In compliance with the Law, the Cabinet of Ministers by its Ordinance of January 13, 1993, authorized the Ukrainian State Committee for Nuclear and Radiation Safety (UkrSCNRS) to issue special permissions or licenses for waste treatment and disposal. And that requirement was valid not only for future activities but also for existing facilities in operation. Taking into account the undergoing legislative process, SCNRS began to develop its licensing process without waiting for the special nuclear laws to be passed. On the basis of the legislation already in effect, first of all the Law on Enterprises (full responsibility of enterprises for their activities) and Law on Business activities (requirement to have a license for special types of activities), the newly formed national regulatory body had to identify all the enterprises that needed to be licensed, to establish relevant procedures, to develop related regulatory documents, to implement these procedures and documents at operating enterprises, and for each case to make a decision concerning feasibility of issuing a license, period of validity and license conditions

Facilities for in-service control

International Nuclear Information System (INIS)

Werner, H.

1980-01-01

Up to now the efficiency of in-service control had been limited and dependent on special qualifications of the super-intending personnel and was thus neither exact nor transferable. In the meantime a great number of testing and measuring facilities for special application have been developed. Even novel types of testing methods do not grant absolutely precise statements. In most cases, however, there is a possibility of planning repairs by trend control and of avoiding failures of operation with aggravating consequences. Technical designers from all subject fields should be made familiar with the continually increasing spectrum of in-service inspection techniques so that a better application of modern and well-tried testing methods can be planned. Systematic in-service inspections complete the Rules of Technology which are safety-oriented with regard to the nonlinear wear between regular dates of control which has been ignored so far and its implied risks. Components which are not liable to control can be checked much better by novel type methods. (orig./RW) [de

Dosimeter calibration facilities and methods at the Radiation Measurement Laboratory of the Centre d'etudes nucleaires, Grenoble

International Nuclear Information System (INIS)

Choudens, H. de; Herbaut, Y.; Haddad, A.; Giroux, J.; Rouillon, J.; CEA Centre d'Etudes Nucleaires de Grenoble, 38

1975-01-01

At the Centre d'etudes nucleaires, Grenoble, the Radiation Measurement Laboratory, which forms part of the Environmental Protection and Research Department, serves the entire Centre for purposes of dosimetry and the calibration of dose meters. The needs of radiation protection are such that one must have facilities for checking periodically the calibration of radiation-monitoring instruments and developing special dosimetry techniques. It was thought a good idea to arrange for the dosimetry and radiation protection team to assist other groups working at the Centre - in particular, the staff of the biology and radiobiology laboratories - and also bodies outside the framework of the French Commissariat a l'energie atomique. Thus, technical collaboration has been established with, for example, Grenoble's Centre hospitalier universitaire (university clinic), which makes use of the facilities and skills available at the Radiation Measurement Laboratory for solving special dosimetry problems. With the Laboratory's facilities it is possible to calibrate dose meters for gamma, beta and neutron measurements

Development of radiation safety monitoring system at gamma greenhouse gamma facility

International Nuclear Information System (INIS)

Hairul Nizam Idris; Azimawati Ahmad, Ahmad Zaki Hussain; Ahmad Fairuz Mohd Nasir

2009-01-01

This paper is discussing about installation of radiation safety monitoring system at Gamma Greenhouse Gamma facility, Agrotechnology and Bioscience Division (BAB). This facility actually is an outdoor type irradiation facility, which first in Nuclear Malaysia and the only one in Malaysia. Source Cs-137 (801 Curie) was use as radiation source and it located at the centre of 30 metres diameter size of open irradiation area. The radiation measurement and monitoring system to be equipped in this facility were required the proper equipment and devices, specially purpose for application at outside of building. Research review, literature study and discussion with the equipment manufacturers was being carried out, in effort to identify the best system should be developed. Factors such as tropical climate, environment surrounding and security were considered during selecting the proper system. Since this facility involving with panoramic radiation type, several critical and strategic locations have been fixed with radiation detectors, up to the distance at 200 meter from the radiation source. Apart from that, this developed system also was built for capable to provide the online real-time reading (using internet). In general, it can be summarized that the radiation safety monitoring system for outdoor type irradiation facility was found much different and complex compared to the system for indoor type facility. Keyword: radiation monitoring, radiation safety, Gamma Greenhouse, outdoor irradiation facility, panoramic radiation. (Author)

Water, sanitation and hygiene in Jordan's healthcare facilities.

Science.gov (United States)

Khader, Yousef Saleh

2017-08-14

Purpose The purpose of this paper is to determine water availability, sanitation and hygiene (WSH) services, and healthcare waste management in Jordan healthcare facilities. Design/methodology/approach In total, 19 hospitals (15 public and four private) were selected. The WSH services were assessed in hospitals using the WSH in health facilities assessment tool developed for this purpose. Findings All hospitals (100 percent) had a safe water source and most (84.2 percent) had functional water sources to provide enough water for users' needs. All hospitals had appropriate and sufficient gender separated toilets in the wards and 84.2 percent had the same in outpatient settings. Overall, 84.2 percent had sufficient and functioning handwashing basins with soap and water, and 79.0 percent had sufficient showers. Healthcare waste management was appropriately practiced in all hospitals. Practical implications Jordan hospital managers achieved major achievements providing access to drinking water and improved sanitation. However, there are still areas that need improvements, such as providing toilets for patients with special needs, establishing handwashing basins with water and soap near toilets, toilet maintenance and providing sufficient trolleys for collecting hazardous waste. Efforts are needed to integrate WSH service policies with existing national policies on environmental health in health facilities, establish national standards and targets for the various healthcare facilities to increase access and improve services. Originality/value There are limited WSH data on healthcare facilities and targets for basic coverage in healthcare facilities are also lacking. A new assessment tool was developed to generate core WSH indicators and to assess WSH services in Jordan's healthcare facilities. This tool can be used by a non-WSH specialist to quickly assess healthcare facility-related WSH services and sanitary hazards in other countries. This tool identified some areas

A minisum model with forbidden regions for locating a semi-desirable facility in the plane

DEFF Research Database (Denmark)

Juel, Henrik; Brimberg, Jack

1998-01-01

-desirable facility that accounts for the service costs by a standard minisum objective with arbitrary travel distance function. The social costs are imputed by specifying around each demand point or population center a convex forbidden region, also defined by an arbitrary distance metric, in which the new facility...... may not be located. A general solution algorithm is suggested, and the methodology is applied to circular forbidden regions and special travel distance functions....

Detecting New Pedestrian Facilities from VGI Data Sources

Science.gov (United States)

Zhong, S.; Xie, Z.

2017-12-01

Pedestrian facility (e.g. footbridge, pedestrian crossing and underground passage) information is an important basic data of location based service (LBS) for pedestrians. However, timely updating pedestrian facility information challenges due to facilities change frequently. Previous pedestrian facility information collecting and updating tasks are mainly completed by highly trained specialized persons. However, this conventional approach has several disadvantages such as high cost, long update cycle and so on. Volunteered Geographic Information (VGI) has proven efficiency to provide new, free and fast growing spatial data. Pedestrian trajectory, which can be seen as measurements of real pedestrian road, is one of the most valuable information of VGI data. Although the accuracy of the trajectories is not too high, due to the large number of measurements, an improvement of quality of the road information can be achieved. Thus, we develop a method for detecting new pedestrian facilities based on the current road network and pedestrian trajectories. Specifically, 1) by analyzing speed, distance and direction, those outliers of pedestrian trajectories are removed, 2) a road network matching algorithm is developed for eliminating redundant trajectories, and 3) a space-time cluster algorithm is adopted for detecting new walking facilities. The performance of the method is evaluated with a series of experiments conducted on a part of the road network of Heifei and a large number of real pedestrian trajectories, and verified the results by using Tencent Street map. The results show that the proposed method is able to detecting new pedestrian facilities from VGI data accurately. We believe that the proposed method provides an alternative way for general road data acquisition, and can improve the quality of LBS for pedestrians.

Administrative Court Stade, decision of March 22, 1985 (interim storage facility at Gorleben)

International Nuclear Information System (INIS)

Anon.

1985-01-01

This decision deals with the planned interim storage facility of Gorleben (F.R.G.). The provisions introduced by the 4th ammendment to sec. 5 para. 6 and 9a to 9c of the German Atomic Energy Act might contain a definite regulation of the 'Entsorgung' of nuclear power stations. Sec. 6 of the Atomic Energy Act is not applicable to interim storage facilities because irradiated nuclear fuel has a double nature: It is spent fuel and nuclear waste as well. Considering current licensing procedures of construction and operation of nuclear installations in the field of 'Entsorgung', special legal regulations for the construction and operation of an interim storage facility have to be required. (CW)

77 FR 71031 - Office of Hazardous Materials Safety; Actions on Special Permit Applications

Science.gov (United States)

2012-11-28

...-Mart Stores, Inc. 49 CFR part 172, part To authorize the one-time, Bentonville, AR. 173 and part 177...- impaired retail stores impacted by Hurricane Sandy to a temporary warehousing facility for approximately 10... Request by EQ Industrial Services, Inc. Ypsilanti, MI October 4, 2012. To modify the special permit to...

The Easter Seal Directory of Resident Camps for Persons with Special Health Needs.

Science.gov (United States)

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

The directory of resident camps is designed for persons with special health needs (children and adults with physical, mental, social, or emotional handicaps). Published by the National Easter Seal Society for Crippled Children and Adults, the listing contains residential facilities only (day care camp program information is not included). Listed…

Planning for maintenance in radiochemical facilities [Paper No.: VB-2

International Nuclear Information System (INIS)

Balasubramanian, G.R.

1981-01-01

Reprocessing facilities in the earlier stages of development were planned mainly based on the concept of direct maintenance in view of the inherent advantage of man-machine interface and initial savings in the investment costs. With the mechanical processes finding a firm place in head-end operation and increase in down time necessary for elaborate decontamination efforts even for a minor modification has led to the review of the concept. For the same reason, the recent plants are based on the concept of harmonious blend of both direct and remote maintenance. The paper describes the planning needed from consideration of various aspects related to such concepts of maintenance during different phases of such type of facilities, highlighting some of the tools and special equipments to be developed for this purpose. A brief description of recent development in the field of remote maintenance is also given. Though the basic hot facility of reference is the one of reprocessing fast reactor fuels, the concepts and systems discussed are equally applicable to other radiochemical and radiometallurgical facilities also. (author)

The Sandia transportable triggered lightning instrumentation facility

Science.gov (United States)

Schnetzer, George H.; Fisher, Richard J.

1991-01-01

Development of the Sandia Transportable Triggered Lightning Instrumentation Facility (SATTLIF) was motivated by a requirement for the in situ testing of a munitions storage bunker. Transfer functions relating the incident flash currents to voltages, currents, and electromagnetic field values throughout the structure will be obtained for use in refining and validating a lightning response computer model of this type of structure. A preliminary shakedown trial of the facility under actual operational conditions was performed during summer of 1990 at the Kennedy Space Center's (KSC) rocket-triggered lightning test site. A description is given of the SATTLIF, which is readily transportable on a single flatbed truck of by aircraft, and its instrumentation for measuring incident lightning channel currents and the responses of the systems under test. Measurements of return-stroke current peaks obtained with the SATTLIF are presented. Agreement with data acquired on the same flashes with existing KSC instrumentation is, on average, to within approximately 7 percent. Continuing currents were measured with a resolution of approximately 2.5 A. This field trial demonstrated the practicality of using a transportable triggered lightning facility for specialized test applications.

Seismic design criteria for special isotope separation plant structures

International Nuclear Information System (INIS)

Wrona, M.W.; Wuthrich, S.J.; Rose, D.L.; Starkey, J.

1989-01-01

This paper describes the seismic criteria for the design of the Special Isotope Separation (SIS) production plant. These criteria are derived from the applicable Department of Energy (DOE) orders, references and proposed standards. The SIS processing plant consistent of Load Center Building (LCB), Dye Pump Building (DPB), Laser Support Building (LSB) and Plutonium Processing Building (PPB). The facility-use category for each of the SIS building structures is identified and the applicable seismic design criteria and parameters are selected

Microcomputer based shelf system to monitor special nuclear materials in storage

International Nuclear Information System (INIS)

Nicholson, N.; Kuckertz, T.H.; Ethridge, C.D.

1980-01-01

Diversion of special nuclear material has become a matter of grave concern in recent years. Large quantities of this material are kept in long-term storage and must be inventoried periodically, resulting in a time-consuming activity that exposes personnel to additional radiation. A system that provides continuous surveillance of stored special nuclear materials has been developed. A shelf monitor has been designed using a single component microcomputer to collect data from a Geiger Muller tube that monitors gamma emissions and a scale that monitors the total weight of the special nuclear material and its container. A network of these shelf monitors reports their acquired data to a minicomputer for analysis and storage. Because a large number of these monitors is likely to be needed in most storage facilities, one objective of this program has been to develop a low cost but reliable monitor

Control system considerations for the AHF [Advanced Hadron Facility

International Nuclear Information System (INIS)

Butler, H.S.

1989-01-01

This paper identifies some of the more important issues related to the design of a control system for the Advanced Hadron Facility (AHF). It begins with a brief description of the site layout and how the various accelerators operate in tandem to deliver beam to several experimental areas. Then it focuses on the control system by estimating from existing installations the number of data and control channels to be expected for the AHF. The total comes to 50,000. This channel count is converted to manpower and cost estimates for the control system by extrapolating from other accelerator facilities. Finally, special attention is given to two subsystems -- magnets and diagnostic equipment -- and the impact they will have on the control system. 11 refs., 5 figs., 6 tabs

Telemanipulation - a special activity in remotely controlled operations

International Nuclear Information System (INIS)

Rose, K.W.; Andre, Y.

1992-01-01

Work to be done in areas hostile to humans needs special and careful preparation. If short-term entry is possible, groups of men can be trained to do the necessary work. If not, special devices have to be designed, built, and tested on mockups before the real work can be executed. Based on experience gained from maintenance in car production and test programs for a reprocessing facility, it was decided to train a special group of men to do remotely controlled work in hostile areas without endangering them and to use their personal experience as the basis for future work. This is the old-fashioned way of all professions. Some needs to be able to do that remotely controlled work with normally existing operational means and combinations of them like cranes, mechanical and electromechanical master slave manipulators (MMSMs and EMSMs), saws, files, hammer, tig-welding equipment, etc., in air as well as underwater. This paper discusses use of a remote operator manipulator (ROM), remote operator welder (ROW), a test of underwater work, and the repair of two activated jets pumps of a boiling water reactor BWR with a fueling machine, reactor crane, EMSM, and conventional tools

Survey of computer codes applicable to waste facility performance evaluations

International Nuclear Information System (INIS)

Alsharif, M.; Pung, D.L.; Rivera, A.L.; Dole, L.R.

1988-01-01

This study is an effort to review existing information that is useful to develop an integrated model for predicting the performance of a radioactive waste facility. A summary description of 162 computer codes is given. The identified computer programs address the performance of waste packages, waste transport and equilibrium geochemistry, hydrological processes in unsaturated and saturated zones, and general waste facility performance assessment. Some programs also deal with thermal analysis, structural analysis, and special purposes. A number of these computer programs are being used by the US Department of Energy, the US Nuclear Regulatory Commission, and their contractors to analyze various aspects of waste package performance. Fifty-five of these codes were identified as being potentially useful on the analysis of low-level radioactive waste facilities located above the water table. The code summaries include authors, identification data, model types, and pertinent references. 14 refs., 5 tabs

A systematic approach to assessing indoor air quality of long term care facilities

NARCIS (Netherlands)

te Kulve, M.; Loomans, M.G.L.C.; Huisman, E.R.C.M.; Kort, H.S.M.

2018-01-01

Not much is known about the favourable indoor air quality in long term care facilities (LTCFs), where older adults suffering from dementia live. Older adults, especially those who suffer from dementia, are more sensible to the indoor environment. However, no special requirements for the indoor air

Use of base isolation techniques for the design of high-level waste storage facility enclosure at INEL

International Nuclear Information System (INIS)

Vallenas, J.M.; Wong, Chun K.; Beer, M.J.

1993-08-01

Current Department of Energy criteria for facilities subjected to natural hazards provide guidelines to place facilities or portions of facilities into usage categories. Usage categories are based on characteristics such as mission dependence, type of hazardous materials involved, and performance goals. Seismic requirements are significantly more stringent for facilities falling into higher ''hazard facility use categories''. A special problem arises in cases where a facility or portion of a facility is dependent on another facility of lower ''hazard facility use category'' for support or protection. Creative solutions can minimize the cost Unpact of ensuring that the lower category item does not compromise the performance of the higher category item. In this paper, a base isolation solution is provided for a ''low hazard facility use category'' weather enclosure designed so it will not collapse onto a ''high hazard facility use category'' high level waste storage facility at INEL. This solution is compared to other more conventional procedures. Details, practical limitations, licensing and regulatory considerations, and cost comparisons are provided

Design and study of Engineering Test Facility - Helium Circulator

International Nuclear Information System (INIS)

Jiang Huijing; Ye Ping; Zhao Gang; Geng Yinan; Wang Jie

2015-01-01

Helium circulator is one of the key equipment of High-temperature Gas-cooled Reactor Pebble-bed Module (HTR-PM). In order to simulate most normal and accident operating conditions of helium circulator in HTR-PM, a full scale, rated flow rate and power, engineering test loop, which was called Engineering Test Facility - Helium Circulator (ETF-HC), was designed and established. Two prototypes of helium circulator, which was supported by Active Magnetic Bearing (AMB) or sealed by dry gas seals, would be tested on ETF-HC. Therefore, special interchangeable design was under consideration. ETF-HC was constructed compactly, which consisted of eleven sub-systems. In order to reduce the flow resistance of the circuit, special ducts, elbows, valves and flowmeters were selected. Two stages of heat exchange loops were designed and a helium - high pressure pure water heat exchanger was applied to ensure water wouldn't be vaporized while simulating accident conditions. Commissioning tests were carried out and operation results showed that ETF-HC meets the requirement of helium circulator operation. On this test facility, different kinds of experiments were supposed to be held, including mechanical and aerodynamic performance tests, durability tests and so on. These tests would provide the features and performance of helium circulator and verify its feasibility, availability and reliability. (author)

Clean-out and Reuse of GCEP Facilities at Portsmouth

International Nuclear Information System (INIS)

Franz, William; Hickman, Mark; Wiehle, Kristi

2008-01-01

PORTS began operations in 1956 to enrich uranium for both civilian and military use. It operated under Goodyear Atomic Corporation and Lockheed-Martin as a government-owned contractor-operated facility until the formation of the United States Enrichment Corporation (USEC) as a government corporation in 1993. In 1998, USEC was privatized as a publicly traded corporation. USEC leases the Portsmouth and Paducah GDPs from the U.S. Department of Energy (DOE). Enrichment operations were terminated at Portsmouth in 2001, although USEC continues to lease and maintain the Portsmouth GDP in Cold Shutdown and conduct some DOE projects there. LPP found that removal of old equipment to allow reuse of a facility can present unexpected challenges. Classified components create significant logistics issues. In this case, teamwork and attention to detail by USEC, LATA/Parallax, and DOE resulted in solutions and success. Lessons learnt: - Transportation logistics are particularly important when shipping waste streams with special requirements. - Investment in extra equipment yields tangible benefits where other resources (cleared drivers) are scarce. - An early start to providing specially qualified drivers, in this case providing security clearances, is essential. Availability is limited, and the time required to qualify new drivers may be lengthy. - A dedicated communications station, rather than reliance on existing resources (shift superintendent), is invaluable

Master slave manipulator maintenance at the Defense Waste Processing Facility

International Nuclear Information System (INIS)

Lethco, A.J.; Beasley, K.M.

1991-01-01

Equipment has been developed and tested to provide transport, installation, removal, decontamination, and repair for the master slave manipulators that are required for thirty-five discrete work locations in the 221-S Vitrification Building of the Defense Waste Processing Facility at the Westinghouse Savannah River Company. This specialized equipment provides a standardized scheme for work locations at different elevations with two types of manipulators

NSC confirms principles for safety review on Radioactive Waste Burial Facilities

International Nuclear Information System (INIS)

Anon.

1988-01-01

The Nuclear Safety Commission authorized the scope of Principles for Safety Examination on Radioactive Waste Burial Facilities as suitable, the draft report for which was established by the Special Committee on Safety Standards of Radioactive Waste (Chairman Prof. Masao Sago, Science University of Tokyo) and reported on March 10 to the NSC. The principles include the theory that the facility must be controlled step by step, corresponding to the amount of radioactivity over 300 to 400 years after the burial of low-level solid radioactive waste with site conditions safe even in the event of occurrence of a natural disaster. The principles will be used for administrative safety examination against the application of the business on low-level radioactive waste burial facility which Japan Nuclear Fuel Industries, Inc. is planning to install at Rokkashomura, Aomori Prefecture. (author)

An alternative format for Category I fuel cycle facility physical protection plans

International Nuclear Information System (INIS)

Dwyer, P.A.

1992-06-01

This document provides an alternative format for physical protection plans designed to meet the requirements of Title 10 of the Code of Federal Regulations, Sections 73.20, 73.45, and 73.46. These requirements apply to licensees who operate Category I fuel cycle facilities. Such licensees are authorized to use or possess a formula quantity of strategic special nuclear material. The format described is an alternative to that found under Regulatory Guide 5.52, Rev. 2 ''Standard Format and Content of a Licensee Physical Protection Plan for Strategic Special Nuclear Material at Fixed Sites (Other than Nuclear Power Plants).''

Gas detection for alternate-fuel vehicle facilities.

Science.gov (United States)

Ferree, Steve

2003-05-01

Alternative fuel vehicles' safety is driven by local, state, and federal regulations in which fleet owners in key metropolitan [table: see text] areas convert much of their fleet to cleaner-burning fuels. Various alternative fuels are available to meet this requirement, each with its own advantages and requirements. This conversion to alternative fuels leads to special requirements for safety monitoring in the maintenance facilities and refueling stations. A comprehensive gas and flame monitoring system needs to meet the needs of both the user and the local fire marshal.

Methods of Verification, Accountability and Control of Special Nuclear Material

International Nuclear Information System (INIS)

Stewart, J.E.

1999-01-01

This session demonstrates nondestructive assay (NDA) measurement, surveillance and analysis technology required to protect, control and account (MPC and A) for special nuclear materials (SNM) in sealed containers. These measurements, observations and analyses comprise state-of-the art, strengthened, SNM safeguards systems. Staff member specialists, actively involved in research, development, training and implementation worldwide, will present six NDA verification systems and two software tools for integration and analysis of facility MPC and A data

1976 Hanford americium-exposure incident: decontamination and treatment facility

International Nuclear Information System (INIS)

Berry, J.R.; McMurray, B.J.; Jech, J.J.; Breitenstein, B.D.; Quigley, E.J.

1982-01-01

An injured worker, contaminated with over 6 mCi of americium-241, required special treatment and housing for 4 months. This paper is a description of the design and management of the facility in which most of the treatment and housing occurred. The problems associated with contamination control, waste handling, supplies, and radiological concerns during the two-stage transfer of the patient from a controlled situation to his normal living environment are discussed in detail

Correlation plot facility in the SLC control system

International Nuclear Information System (INIS)

Hendrickson, L.; Phinney, N.; Sanchez-Chopitea, L.

1991-05-01

The Correlation Plot facility is a powerful interactive tool for data acquisition and analysis throughout the SLC. A generalized interface allows the user to perform a wide variety of machine physics experiments without the need for specialized software. It has been used extensively during SLC commissioning and operation. The user may step one or two independent parameters such as magnet or feedback setpoints while measuring or calculating up to 160 others. Measured variables include all analog signals available to the control system as well as a variety of derived parameters such as beam size or emittance. Various fitting algorithms and display options are provided for data analysis. A software-callable interface is also provided. Applications based on this facility are used to phase klystrons, measure emittance and dispersion, minimize beam size at the interaction point and maintain beam collisions. 4 refs., 3 figs

Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

Energy Technology Data Exchange (ETDEWEB)

Dwyer, P.A.

1991-10-01

This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material.

Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

International Nuclear Information System (INIS)

Dwyer, P.A.

1991-10-01

This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material

CERN accelerator school: Antiprotons for colliding beam facilities

International Nuclear Information System (INIS)

Bryant, P.; Newman, S.

1984-01-01

This is a specialized course which addresses a wide spectrum of theoretical and technological problems confronting the designer of an antiproton facility for high-energy-physics research. A broad and profound basis is provided by the lecturers' substantial experience gained over many years with CERN's unique equipment. Topics include beam optics, special lattices for antiproton accumulation and storage rings, antiproton production, stochastic cooling, acceleration and storage, r.f. noise, r.f. beam manipulations, beam-beam interaction, beam stability due to ion accumulation, and diagnostics. The SPS (Super Proton Synchrotron) panti p collider, LEAR (the Low Energy Antiproton Ring at CERN), antiprotons in the ISR (Intersecting Storage Rings), the new antiproton collector (ACOL) and gas jet targets are also discussed. A table is included listing the parameters of all CERN's accelerators and storage rings. See hints under the relevant topics. (orig./HSI)

Energy solutions for sports facilities

Energy Technology Data Exchange (ETDEWEB)

Artuso, Paola; Santiangeli, Adriano [CIRPS: Inter-University Research Centre for Sustainable Development, Sapienza University of Rome, Via Eudossiana, 18, Rome (Italy)

2008-06-15

The sports facilities are characterized by special energy needs different from any other user and they are characterized by high heat and electricity loads. For this reason, the aim of this work has been to propose a tool to provide a preliminary estimation of the power and energy required by the sports centres. In addition, the possibility to make the building self-energy sufficient has been considered, thanks to the exploitation of renewable energy sources (RES). The overall work has been performed following three steps: energy needs analysis; local RES availability analysis; energy balance of Sport Centres. Considering that each sport facility is characterized by different energy needs depending on the sport typology itself, the analysis started from the features established by the CONI (National Italian Olympic Committee) standardization. For calculations a program in LabVIEW has been developed to evaluate the energy requirements of the sports centre considering as inputs the sport halls, the playgrounds and the supporting rooms, the level of the sport activity (e.g. agonistic) and the climatic conditions of the area where the facilities are located. The locally available RES are evaluated in order to decide which one can be exploited to feed the Sport Centre. The proposed solution for the energy production refers to a combination of different and innovative technologies which involve, in particular, hydrogen technologies. The energy and costs analysis has been finally carried out for an application case in Dubai. (author)

40 CFR 264.317 - Special requirements for hazardous wastes FO20, FO21, FO22, FO23, FO26, and FO27.

Science.gov (United States)

2010-07-01

... HAZARDOUS WASTE TREATMENT, STORAGE, AND DISPOSAL FACILITIES Landfills § 264.317 Special requirements for... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for hazardous wastes FO20, FO21, FO22, FO23, FO26, and FO27. 264.317 Section 264.317 Protection of Environment...

40 CFR 264.283 - Special requirements for hazardous wastes FO20, FO21, FO22, FO23, FO26, and FO27.

Science.gov (United States)

2010-07-01

... HAZARDOUS WASTE TREATMENT, STORAGE, AND DISPOSAL FACILITIES Land Treatment § 264.283 Special requirements... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Special requirements for hazardous wastes FO20, FO21, FO22, FO23, FO26, and FO27. 264.283 Section 264.283 Protection of Environment...

High Energy Ion Bombardment Simulation Facility at the University of Pittsburgh

International Nuclear Information System (INIS)

McGruer, J.N.; Choyke, W.J.; Doyle, N.J.; Spitznagel, J.A.

1975-01-01

The High Energy Ion Bombardment Simulation (HEIBS) Facility located at the University of Pittsburgh is now operational. The E-22 tandem accelerator of the Nuclear Physics Laboratory, fitted with a UNIS source, provides the heavy high energy ions. An auxiliary Van de Graaff accelerator is used for the simultaneous production of He ions. Special features of the simulation laboratory are reported

Life-Cycle Assessments of Selected NASA Ground-Based Test Facilities

Science.gov (United States)

Sydnor, George Honeycutt

2012-01-01

In the past two years, two separate facility-specific life cycle assessments (LCAs) have been performed as summer student projects. The first project focused on 13 facilities managed by NASA s Aeronautics Test Program (ATP), an organization responsible for large, high-energy ground test facilities that accomplish the nation s most advanced aerospace research. A facility inventory was created for each facility, and the operational-phase carbon footprint and environmental impact were calculated. The largest impacts stemmed from electricity and natural gas used directly at the facility and to generate support processes such as compressed air and steam. However, in specialized facilities that use unique inputs like R-134a, R-14, jet fuels, or nitrogen gas, these sometimes had a considerable effect on the facility s overall environmental impact. The second LCA project was conducted on the NASA Ames Arc Jet Complex and also involved creating a facility inventory and calculating the carbon footprint and environmental impact. In addition, operational alternatives were analyzed for their effectiveness at reducing impact. Overall, the Arc Jet Complex impact is dominated by the natural-gas fired boiler producing steam on-site, but alternatives were provided that could reduce the impact of the boiler operation, some of which are already being implemented. The data and results provided by these LCA projects are beneficial to both the individual facilities and NASA as a whole; the results have already been used in a proposal to reduce carbon footprint at Ames Research Center. To help future life cycle projects, several lessons learned have been recommended as simple and effective infrastructure improvements to NASA, including better utility metering and data recording and standardization of modeling choices and methods. These studies also increased sensitivity to and appreciation for quantifying the impact of NASA s activities.

The Analysis Condition of Special Library for Street Children at UPTD "Kampung Anak Negeri” Institutions

Directory of Open Access Journals (Sweden)

Fitri Mutia

2016-12-01

Full Text Available The existence of special library UPTD the "Kampung Anak Negeri" became one medium that can be used to develop the potential of street children themselves a growing number from year to year. This study conducted descriptive quantitative research that aim to describe the condition of special libraries in UPTD “Kampung Anak Negeri", especially in terms of collections, facilities and infrastructure, library services and human resources (librarian. The four aspects are then compared with the standard of the special library collated by the National Library in 2011. In this study, data collection technique conducted in July 2016 using interview techniques as a primary technique performed on librarians and include interviews with street children as well as staff of Colleagues   staff UPTD.  Based on the data obtained can be concluded that the amount of the book collection of about 752 titles of books, collection development has not reached 5% per year, spacious room just 35m² and has only 2 rack collection. Services available are services in place read, circulation services and information search services, while the librarians who manage only one person with a background in library and information science education. In general, special libraries UPTD condition does not meet the standard, so this affects is not maximized to support learning process as well as in facilities that match the information needs of street children.

Biosafety and biosecurity measures: management of biosafety level 3 facilities.

Science.gov (United States)

Zaki, Adel N

2010-11-01

With the increasing biological threat from emerging infectious diseases and bioterrorism, it has become essential for governments around the globe to increase awareness and preparedness for identifying and containing those agents. This article introduces the basic concepts of laboratory management, laboratory biosafety and laboratory biosecurity. Assessment criteria for laboratories' biorisk should include both biosafety and biosecurity measures. The assessment requires setting specific goals and selecting management approaches. In order to implement technologies at the laboratory working level, a management team should be created whose role is to implement biorisk policies, rules and regulations appropriate for that facility. Rules and regulations required by government authorities are presented, with special emphasis on methods for air control, and liquid and solid waste management. Management and biorisk measures and appropriate physical facilities must keep pace, ensuring efficient facilities that protect workers, the environment, the product (research, diagnostic and/or vaccine) and the biological pathogen. Published by Elsevier B.V.

Fuels and materials testing capabilities in Fast Flux Test Facility

International Nuclear Information System (INIS)

Baker, R.B.; Chastain, S.A.; Culley, G.E.; Ethridge, J.L.; Lovell, A.J.; Newland, D.J.; Pember, L.A.; Puigh, R.J.; Waltar, A.E.

1989-01-01

The Fast Flux Test Facility (FFTF) reactor, which started operating in 1982, is a 400 MWt sodium-cooled fast neutron reactor located in Hanford, Washington State, and operated by Westinghouse Hanford Co. under contract with U.S. Department of Energy. The reactor has a wide variety of functions for irradiation tests and special tests, and its major purpose is the irradiation of fuel and material for liquid metal reactor, nuclear reactor and space reactor projects. The review first describes major technical specifications and current conditions of the FFTF reactor. Then the plan for irradiation testing is outlined focusing on general features, fuel pin/assembly irradiation tests, and absorber irradiation tests. Assemblies for special tests include the material open test assembly (MOTA), fuel open test assembly (FOTA), closed loop in-reactor assembly (CLIRA), and other special fuel assemblies. An interim examination and maintenance cell (FFTF/IEM cell) and other hot cells are used for nondestructive/destructive tests and physical/mechanical properties test of material after irradiation. (N.K.)

Estimation methods for process holdup of special nuclear materials

International Nuclear Information System (INIS)

Pillay, K.K.S.; Picard, R.R.; Marshall, R.S.

1984-06-01

The US Nuclear Regulatory Commission sponsored a research study at the Los Alamos National Laboratory to explore the possibilities of developing statistical estimation methods for materials holdup at highly enriched uranium (HEU)-processing facilities. Attempts at using historical holdup data from processing facilities and selected holdup measurements at two operating facilities confirmed the need for high-quality data and reasonable control over process parameters in developing statistical models for holdup estimations. A major effort was therefore directed at conducting large-scale experiments to demonstrate the value of statistical estimation models from experimentally measured data of good quality. Using data from these experiments, we developed statistical models to estimate residual inventories of uranium in large process equipment and facilities. Some of the important findings of this investigation are the following: prediction models for the residual holdup of special nuclear material (SNM) can be developed from good-quality historical data on holdup; holdup data from several of the equipment used at HEU-processing facilities, such as air filters, ductwork, calciners, dissolvers, pumps, pipes, and pipe fittings, readily lend themselves to statistical modeling of holdup; holdup profiles of process equipment such as glove boxes, precipitators, and rotary drum filters can change with time; therefore, good estimation of residual inventories in these types of equipment requires several measurements at the time of inventory; although measurement of residual holdup of SNM in large facilities is a challenging task, reasonable estimates of the hidden inventories of holdup to meet the regulatory requirements can be accomplished through a combination of good measurements and the use of statistical models. 44 references, 62 figures, 43 tables

Cultivation of university students in radiology using research facilities at KAERI

Energy Technology Data Exchange (ETDEWEB)

Shin, Byung Chul [Nuclear Training and Education Center, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2017-09-15

The purpose of present research is to offer a specialized educational opportunity for potential users, university students in radiology, by developing specific curriculum on site at KAERI, using HANARO research reactor and National radiation research facilities. The specific items of this research accomplished are: First, Development and operation of various curricula for specific research using HANARO and National radiation research facilities to provide university students with opportunities to use the facilities. Second, Operation of the experiment training programs for university students in radiology to foster next generation specialists. Third, through the on-site experiment training for students in radiology, support future potential experts of the radiation research fields, and broaden the base. A textbook and a teaching aid, a questionnaire have been developed to support the program. 714 university students have completed the courses for radiology experiment from 2006 to 2017. It is hoped that these experiments broaden public awareness and acceptance by the present and potential future utilization of the research reactor and national radiation research facilities, thereby bring positive impacts to policy making.

Feedback experience from the decommissioning of Spanish nuclear facilities

International Nuclear Information System (INIS)

Santiago, J.L.

2008-01-01

The Spain has accumulated significant experience in the field of decommissioning of nuclear and radioactive facilities. Relevant projects include the remediation of uranium mills and mines, the decommissioning of research reactors and nuclear research facilities and the decommissioning of gas-graphite nuclear power plants. The decommissioning of nuclear facilities in Spain is undertaken by ENRESA, who is also responsible for the management of radioactive wastes. The two most notable projects are the decommissioning of the Vandellos I nuclear power plant and the decommissioning of the CIEMAT nuclear research centre. The Vandellos I power plant was decommissioned in about five years to what is known as level 2. During this period, the reactor vessel was confined, most plant systems and components were dismantled, the facility was prepared for a period of latency and a large part of the site was restored for subsequent release. In 2005 the facility entered into the phase of dormancy, with minimum operating requirements. Only surveillance and maintenance activities are performed, among which special mention should be made to the five-year check of the leak tightness of the reactor vessel. After the dormancy period (25 - 30 years), level 3 of decommissioning will be initiated including the total dismantling of the remaining parts of the plant and the release of the whole site for subsequent uses. The decommissioning of the CIEMAT Research Centre includes the dismantling of obsolete facilities such as the research reactor JEN-1, a pilot reprocessing plant, a fuel fabrication facility, a conditioning plant for liquid and a liquid waste storage facility which were shutdown in the early eighties. Dismantling works have started in 2006 and will be completed by 2009. On the basis of the experience gained in the above mentioned sites, this paper describes the approaches adopted by ENRESA for large decommissioning projects. (author)

Conference Proceedings - Developing effective petroleum facilities agreements: The new CO and O and beyond

International Nuclear Information System (INIS)

2000-04-01

This conference was held to provide a forum for the discussion of the legal aspects of construction, ownership and operating (CO and O) agreements as they apply to oil and natural gas facilities. A total of 12 papers were presented. The papers discussed various aspects of the subject, including operating production facilities without a CO and O agreement; techniques of drafting CO and O agreement to fit a particular business context; the role of due diligence in facility acquisitions; allocating environmental liabilities within a facilities agreement; ownership of gas gathering systems by midstreamers or financial entities; perspectives applicable to financing midstreamers and to operational midstreamers; the midstream approach as a new business model; and the effect of bankruptcy on CO and O. With few exceptions, speakers were attorneys specializing in contracts, with specific expertise in construction, ownership and operating agreements

Status of proton treatment facility at National Cancer Center, Kashiwa

International Nuclear Information System (INIS)

Tachikawa, T.; Kohmura, I.; Kataoka, S.; Nonaka, H.; Kimura, T.; Sato, T.; Nishio, T.; Shimbo, M.; Ogino, T.; Ikeda, H.

2001-01-01

Proton treatment facility at National Cancer Center Hospital East (Kashiwa) has two rotating gantry ports and one horizontal fixed port. In order to provide the same dose distribution at different gantry angles, the beam optics from the accelerator (235 MeV cyclotron) to the entrance of nozzle is specially tuned. Recently developed automatic tuning method of beam alignment can realize a sequential treatment at three irradiation ports. (author)

Transfer of test samples and wastes between post-irradiation test facilities (FMF, AGF, MMF)

International Nuclear Information System (INIS)

Ishida, Yasukazu; Suzuki, Kazuhisa; Ebihara, Hikoe; Matsushima, Yasuyoshi; Kashiwabara, Hidechiyo

1975-02-01

Wide review is given on the problems associated with the transfer of test samples and wastes between post-irradiation test facilities, FMF (Fuel Monitoring Facility), AGF (Alpha Gamma Facility), and MMF (Material Monitoring Facility) at the Oarai Engineering Center, PNC. The test facilities are connected with the JOYO plant, an experimental fast reactor being constructed at Oarai. As introductory remarks, some special features of transferring irradiated materials are described. In the second part, problems on the management of nuclear materials and radio isotopes are described item by item. In the third part, the specific materials that are envisaged to be transported between JOYO and the test facilities are listed together with their geometrical shapes, dimensions, etc. In the fourth part, various routes and methods of transportation are explained with many block charts and figures. Brief explanation with lists and drawings is also given to transportation casks and vessels. Finally, some future problems are discussed, such as the prevention of diffusive contamination, ease of decontamination, and the identification of test samples. (Aoki, K.)

An Evaluation of Past Special Education Programs and Services Provided to Incarcerated Young Offenders

Science.gov (United States)

Ingalls, Lawrence; Hammond, Helen; Trussell, Robert P.

2011-01-01

This study investigated the past special education programs and services provided to children and youth who later became incarcerated. Participants in this study were inmates from a medium security state correctional facility in the southwest region of the United States. All inmates involved in this study were identified as having a disability and…

Construction and engineering report for advanced nuclear fuel development facility

International Nuclear Information System (INIS)

Cho, S. W.; Park, J. S.; Kwon, S.J.; Lee, K. W.; Kim, I. J.; Yu, C. H.

2003-09-01

The design and construction of the fuel technology development facility was aimed to accommodate general nuclear fuel research and development for the HANARO fuel fabrication and advanced fuel researches. 1. Building size and room function 1) Building total area : approx. 3,618m 2 , basement 1st floor, ground 3th floor 2) Room function : basement floor(machine room, electrical room, radioactive waste tank room), 1st floor(research reactor fuel fabrication facility, pyroprocess lab., metal fuel lab., nondestructive lab., pellet processing lab., access control room, sintering lab., etc), 2nd floor(thermal properties measurement lab., pellet characterization lab., powder analysis lab., microstructure analysis lab., etc), 3rd floor(AHU and ACU Room) 2. Special facility equipment 1) Environmental pollution protection equipment : ACU(2sets), 2) Emergency operating system : diesel generator(1set), 3) Nuclear material handle, storage and transport system : overhead crane(3sets), monorail hoist(1set), jib crane(2sets), tank(1set) 4) Air conditioning unit facility : AHU(3sets), packaged air conditioning unit(5sets), 5) Automatic control system and fire protection system : central control equipment(1set), lon device(1set), fire hose cabinet(3sets), fire pump(3sets) etc

Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information

International Nuclear Information System (INIS)

1995-01-01

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses

Specialization Patterns

DEFF Research Database (Denmark)

Schultz, Ulrik Pagh; Lawall, Julia Laetitia; Consel, Charles

2000-01-01

Design patterns offer many advantages for software development, but can introduce inefficiency into the final program. Program specialization can eliminate such overheads, but is most effective when targeted by the user to specific bottlenecks. Consequently, we propose that these concepts...... are complementary. Program specialization can optimize programs written using design patterns, and design patterns provide information about the program structure that can guide specialization. Concretely, we propose specialization patterns, which describe how to apply program specialization to optimize uses...... of design patterns. In this paper, we analyze the specialization opportunities provided by specific uses of design patterns. Based on the analysis of each design pattern, we define the associated specialization pattern. These specialization opportunities can be declared using the specialization classes...

Annual summary report on surveillance and maintenance activities of the surplus contaminated facilities program at Oak Ridge National Laboratory for period ending September 30, 1991

International Nuclear Information System (INIS)

Cannon, T.R.; Ford, M.K.; Holder, L. Jr.

1991-09-01

The Surplus Contaminated Facilities Program (SCFP) was established at the Oak Ridge National Laboratory (ORNL) in 1985 to provide support for inactive contaminated facilities that were largely abandoned by the programs which they formerly served. This support provides for routine surveillance and maintenance (S ampersand M) and special projects beyond a routine nature when such actions are needed to ensure adequate protection of personnel or the environment. The facilities included in the program had been used for research, technology development, isotope production and processing, and waste management. Support for facilities in the SCFP has previously been provided by the Department of Energy's (DOE's) Office of Energy Research: Multiprogram Energy Laboratories -- Facilities Support (ERKG) because of multiprogram use of the facilities or because of the landlord responsibility of Energy Research. Recently, an integrated Decontamination and Decommissioning (D ampersand D) program within the DOE Office of Environmental Restoration and Waste Management has been established to collectively manage the former Surplus Facilities Management Program, Defense D ampersand D Program, and the KG-funded, ORNL-originated SCFP. This report gives an overview of the S ampersand M planning, routine S ampersand M, and special maintenance project activities which have occurred at the SCFP facilities during the 1991 Fiscal Year

Westinghouse Hanford Company special nuclear material vault storage study

International Nuclear Information System (INIS)

Borisch, R.R.

1996-01-01

Category 1 and 2 Special Nuclear Materials (SNM) require storage in vault or vault type rooms as specified in DOE orders 5633.3A and 6430.1A. All category 1 and 2 SNM in dry storage on the Hanford site that is managed by Westinghouse Hanford Co (WHC) is located in the 200 West Area at Plutonium Finishing Plant (PFP) facilities. This document provides current and projected SNM vault inventories in terms of storage space filled and forecasts available space for possible future storage needs

The BNCT facility at the HFR Petten: Quality assurance for reactor facilities in clinical trials

International Nuclear Information System (INIS)

Moss, R.; Watkins, P.; Vroegindeweij, C.; Stecher-Rasmussen, F.; Huiskamp, R.; Ravensberg, K.; Appelman, K.; Sauerwein, W.; Hideghety, K.; Gabel, D.

2001-01-01

The first clinical trial in Europe of Boron Neutron Capture Therapy (BNCT) for the treatment of glioblastoma was opened in July 1997. The trial is a Phase I study with the principal aim to establish the maximum tolerated radiation dose and the dose limiting toxicity under defined conditions. It is the first time that a clinical application could be realised on a completely multi-national scale. The treatment takes place at the High Flux Reactor (HFR) in Petten, the Netherlands, is operated by an international team of experts under the leadership of a German radiotherapist, and treats patients coming from different European countries. It has therefore been necessary to create a very specialised organisation and contractual structure with the support of administrations from different countries, who had to find and adapt solutions within existing laws that had never foreseen such a situation. Furthermore, the treatment does not take place in an hospital environment and even more so, the facility is at a nuclear research reactor. Hence, special efforts were made on quality assurance, in order that the set-up at the facility and the personnel involved complied, as closely as possible, with similar practices in conventional radiotherapy departments. (author)

Acoustics in Research Facilities--Control of Wanted and Unwanted Sound. Laboratory Design Notes.

Science.gov (United States)

Newman, Robert B.

Common and special acoustics problems are discussed in relation to the design and construction of research facilities. Following a brief examination of design criteria for the control of wanted and unwanted sound, the technology for achieving desired results is discussed. Emphasis is given to various design procedures and materials for the control…

105-DR Large Sodium Fire Facility closure plan. Revision 1

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, and activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide a means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950`s and is located in the 100-D Area of the Hanford Site. The building housed the 105-DR defense reactor, which was shut down in 1964. The LSFF was initially used only for engineering-scale alkali metal reaction studies. In addition, the Fusion Safety Support Studies program sponsored intermediate-size safety reaction tests in the LSFF with lithium and lithium lead compounds. The facility has also been used to store and treat alkali metal waste, therefore the LSFF is subject to the regulatory requirements for the storage and treatment of dangerous waste. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610. This closure plan presents a description of the facility, the history of waste managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected.

Materials and construction techniques for cryogenic wind tunnel facilities for instruction/research use

Science.gov (United States)

Morse, S. F.; Roper, A. T.

1975-01-01

The results of the cryogenic wind tunnel program conducted at NASA Langley Research Center are presented to provide a starting point for the design of an instructional/research wind tunnel facility. The advantages of the cryogenic concept are discussed, and operating envelopes for a representative facility are presented to indicate the range and mode of operation. Special attention is given to the design, construction and materials problems peculiar to cryogenic wind tunnels. The control system for operation of a cryogenic tunnel is considered, and a portion of a linearized mathematical model is developed for determining the tunnel dynamic characteristics.

Facility stabilization project, fiscal year 1998 Multi-Year Workplan (MYWP) for WBS 1.4

International Nuclear Information System (INIS)

Floberg, W.C.

1997-01-01

The primary Facility Stabilization mission is to provide minimum safe surveillance and maintenance of facilities and deactivate facilities on the Hanford Site, to reduce risks to workers, the public and environment, transition the facilities to a low cost, long term surveillance and maintenance state, and to provide safe and secure storage of special nuclear materials, nuclear materials, and nuclear fuel. Facility Stabilization will protect the health and safety of the public and workers, protect the environment and provide beneficial use of the facilities and other resources. Work will be in accordance with the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), local, national, international and other agreements, and in compliance with all applicable Federal, state, and local laws. The stakeholders will be active participants in the decision processes including establishing priorities, and in developing a consistent set of rules, regulations, and laws. The work will be leveraged with a view of providing positive, lasting economic impact in the region. Effectiveness, efficiency, and discipline in all mission activities will enable Hanford Site to achieve its mission in a continuous and substantive manner. As the mission for Facility Stabilization has shifted from production to support of environmental restoration, each facility is making a transition to support the Site mission. The mission goals include the following: (1) Achieve deactivation of facilities for transfer to EM-40, using Plutonium Uranium Extraction (PUREX) plant deactivation as a model for future facility deactivation; (2) Manage nuclear materials in a safe and secure condition and where appropriate, in accordance with International Atomic Energy Agency (IAEA) safeguards rules; (3) Treat nuclear materials as necessary, and store onsite in long-term interim safe storage awaiting a final disposition decision by US Department of Energy; (4) Implement nuclear materials

Special Purpose Materials annual progress report, October 1, 1979

International Nuclear Information System (INIS)

1980-04-01

The scope of Special Purpose Materials covers fusion reactor materials problems other than the first-wall and blanket structural materials, which are under the purview of the ADIP, DAFS, and PMI task groups. Components that are considered as special purpose materials include breeding materials, coolants, neutron multipliers, barriers for tritium control, materials for compression and OH coils and waveguides, graphite and SiC, heat-sink materials, ceramics, and materials for high-field (> 10-T) superconducting magnets. It is recognized that there will be numerous materials problems that will arise during the design and construction of large magnetic-fusion energy devices such as the Engineering Test Facility (ETF) and Demonstration Reactor (DEMO). Most of these problems will be specific to a particular design or project and are the responsibility of the project, not the Materials and Radiation Effects Branch. Consequently, the Task Group on Special Purpose Materials has limited its concern to crucial and generic materials problems that must be resolved if magnetic-fusion devices are to succeed. Important areas specifically excluded include low-field (8-T) superconductors, fuels for hybrids, and materials for inertial-confinement devices. These areas may be added in the future when funding permits

Waste Analysis Plan for the Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

TRINER, G.C.

1999-01-01

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for dangerous, mixed, and radioactive waste accepted for confirmation, nondestructive examination (NDE) and nondestructive assay (NDA), repackaging, certification, and/or storage at the Waste Receiving and Processing Facility (WRAP). Mixed and/or radioactive waste is treated at WRAP. WRAP is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

The centrifuge facility - A life sciences research laboratory for Space Station Freedom

Science.gov (United States)

Fuller, Charles A.; Johnson, Catherine C.; Hargens, Alan R.

1991-01-01

The paper describes the centrifugal facility that is presently being developed by NASA for studies aboard the Space Station Freedom on the role of gravity, or its absence, at varying intensities for varying periods of time and with multiple model systems. Special attention is given to the design of the centrifuge system, the habitats designed to hold plants and animals, the glovebox system designed for experimental manipulations of the specimens, and the service unit. Studies planned for the facility will include experiments in the following disciplines: cell and developmental biology, plant biology, regulatory physiology, musculoskeletal physiology, behavior and performance, neurosciences, cardiopulmonary physiology, and environmental health and radiation.

A conceptual model for barrier free facilities planning.

Science.gov (United States)

Bittencourt, R S; de M Guimarães, L B

2012-01-01

This paper presents the proposal of a model for planning a barrier free industrial facilities, considering the demands that inclusion requires, ranging from outside the factory (social environment), to the needs of the production system and the workstation. Along with literature review, the demands were identified in a shoe manufacturer that employs people with disabilities, and organized taxonomically in agreement with the structure for planning facilities. The results show that the problems are not primarily related to eliminating architectural barriers and factors aimed at preventing risks to people's health and safety but, rather, are related to the company's cultural environment, because the main hazards are managerial. In special cases, it is suggested there is a need to adjust those parts of tasks that the worker cannot do, or even to re-schedule work so as to make it possible for employees with disabilities to perform their tasks.

Economic feasibility of artificial islands for cluster-siting of offshore energy facilities

International Nuclear Information System (INIS)

Baram, M.S.; Spencer, J.; Munson, J.S.

1977-04-01

The study presents a general first-order cost feasibility analysis of the artificial island concept and its usefulness for the offshore siting of multiple energy facilities. The results of the study include a recommended method of cost-feasibility assessment; the collection and organization of the most useful information presently available; and a series of conclusions on feasibility for generic comparison purposes. These conclusions can be summarized as follows: (1) artificial islands to the outer bound of the continental shelf are technologically feasible; (2) offshore nuclear power plants appear to be competitive with onshore plants from a cost standpoint; (3) offshore deepwater ports appear to be more economical than proposed onshore deepwater ports, existing facilities or facilities presently under construction; (4) offshore oil refineries, except under special circumstantces, will probably be more costly than onshore counterparts; (5) the cluster-siting of facilities on an artificial island has definite cost-effectiveness potential; (6) a joint public-private financial venture with a strong federal agency lead role appears essential for the multi-facility island concept to be realized; and (7) artificial island siting of energy complexes appears to be a concept worth pursuing in terms of further site and facility-specific research, and possibly in terms of a demonstration project

Emission Facilities - Erosion & Sediment Control Facilities

Data.gov (United States)

NSGIC Education | GIS Inventory — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

National Ignition Facility Site Management Plan

International Nuclear Information System (INIS)

Roberts, V.

1997-01-01

The purpose of the NIF Site Management Plan is to describe the roles, responsibilities, and interfaces for the major NIF Project organizations involved in construction of the facility, installation and acceptance testing of special equipment, and the NIF activation. The plan also describes the resolution of priorities and conflicts. The period covered is from Critical Decision 3 (CD3) through the completion of the Project. The plan is to be applied in a stepped manner. The steps are dependent on different elements of the project being passed from the Conventional Facilities (CF) Construction Manager (CM), to the Special Equipment (SE) CMs, and finally to the Activation/ Start-Up (AS) CM. These steps are defined as follows: The site will be coordinated by CF through Project Milestone 310, end of conventional construction. The site is defined as the fenced area surrounding the facility and the CF laydown and storage areas. The building utilities that are installed by CF will be coordinated by CF through the completion of Project Milestone 310, end of conventional construction. The building utilities are defined as electricity, compressed air, de-ionized water, etc. Upon completion of the CF work, the Optics Assembly Building/Laser and Target Area Building (OAB/LTAB) will be fully operational. At that time, an Inertial Confinement Fusion (ICF) Program building coordinator will become responsible for utilities and site activities. * Step 1. Mid-commissioning (temperature stable, +1 degree C) of an area (e.g., Laser Bay 2, OAB) will precipitate the turnover of that area (within the four walls) from CF to SE. * Step 2. Interior to the turned-over space, SE will manage all interactions, including those necessary by CF. * Step 3. As the SE acceptance testing procedures (ATPS) are completed, AS will take over the management of the area and coordinate all interactions necessary by CF and SE. For each step, the corresponding CMs for CF, SE, or AS will be placed in charge of

National Ignition Facility Site Management Plan

Energy Technology Data Exchange (ETDEWEB)

Roberts, V.

1997-09-01

The purpose of the NIF Site Management Plan is to describe the roles, responsibilities, and interfaces for the major NIF Project organizations involved in construction of the facility, installation and acceptance testing of special equipment, and the NIF activation. The plan also describes the resolution of priorities and conflicts. The period covered is from Critical Decision 3 (CD3) through the completion of the Project. The plan is to be applied in a stepped manner. The steps are dependent on different elements of the project being passed from the Conventional Facilities (CF) Construction Manager (CM), to the Special Equipment (SE) CMs, and finally to the Activation/ Start-Up (AS) CM. These steps are defined as follows: The site will be coordinated by CF through Project Milestone 310, end of conventional construction. The site is defined as the fenced area surrounding the facility and the CF laydown and storage areas. The building utilities that are installed by CF will be coordinated by CF through the completion of Project Milestone 310, end of conventional construction. The building utilities are defined as electricity, compressed air, de-ionized water, etc. Upon completion of the CF work, the Optics Assembly Building/Laser and Target Area Building (OAB/LTAB) will be fully operational. At that time, an Inertial Confinement Fusion (ICF) Program building coordinator will become responsible for utilities and site activities. * Step 1. Mid-commissioning (temperature stable, +1{degree}C) of an area (e.g., Laser Bay 2, OAB) will precipitate the turnover of that area (within the four walls) from CF to SE. * Step 2. Interior to the turned-over space, SE will manage all interactions, including those necessary by CF. * Step 3. As the SE acceptance testing procedures (ATPS) are completed, AS will take over the management of the area and coordinate all interactions necessary by CF and SE. For each step, the corresponding CMs for CF, SE, or AS will be placed in charge of

Safeguards considerations related to the decontamination and decommissioning of former nuclear weapons facilities

International Nuclear Information System (INIS)

Crawford, D.

1995-01-01

In response to the post-Cold War environment and the changes in the U. S. Department of Energy defense mission, many former nuclear operations are being permanently shut down. These operations include facilities where nuclear materials production, processing, and weapons manufacturing have occurred in support of the nation's defense industry. Since defense-related operations have ceased, many of the classification and sensitive information concerns do not exist. However, nuclear materials found at these sites are of interest to the DOE from environmental, safety and health, and materials management perspectives. Since these facilities played a role in defense activities, the nuclear materials found at these facilities are considered special nuclear materials, primarily highly enriched uranium and/or plutonium. Consequently, these materials pose significant diversion, theft, and sabotage threats, and significant nuclear security issues exist that must be addressed. This paper focuses on the nuclear materials protection issues associated with facility decommissioning and decontamination, primarily safeguards

Compressed Gas Safety for Experimental Fusion Facilities

Energy Technology Data Exchange (ETDEWEB)

Lee C. Cadwallader

2004-09-01

Experimental fusion facilities present a variety of hazards to the operators and staff. There are unique or specialized hazards, including magnetic fields, cryogens, radio frequency emissions, and vacuum reservoirs. There are also more general industrial hazards, such as a wide variety of electrical power, pressurized air, and cooling water systems in use, there are crane and hoist loads, working at height, and handling compressed gas cylinders. This paper outlines the projectile hazard assoicated with compressed gas cylinders and mthods of treatment to provide for compressed gas safety. This information should be of interest to personnel at both magnetic and inertial fusion experiments.

DWPF remotable television and cell lighting facilities

International Nuclear Information System (INIS)

Heckendorn, F.M. II.

1984-01-01

The Defense Waste Processing Facility (DWPF) for radioactive waste vitrification at the Savannah River Plant (SRP) is now under construction. Development of specialized low cost television (TV) viewing equipment for in-cell and within-melter applications is now complete. High resolution TV cameras not originally designed for high radiation environments have been demonstrated in crane remotable packages to be well suited to the DWPF. High intensity in-cell lighting has also been demonstrated in crane remotable assemblies. These dual 1000 W units (2000 W total) are used to support the multiplicity of TV and cell window viewing requirements. 8 figures

Progress report concerning safety research for nuclear reactor facilities

International Nuclear Information System (INIS)

1978-01-01

Examination and evaluation of safety research results for nuclear reactor facilities have been performed, as more than a year has elapsed since the plan had been initiated in April, 1976, by the special sub-committee for the safety of nuclear reactor facilities. The research is carried out by being divided roughly into 7 items, and seems to be steadily proceeding, though it does not yet reach the target. The above 7 items include researches for (1) criticality accident, (2) loss of coolant accident, (3) safety for light water reactor fuel, (4) construction safety for reactor facilities, (5) reduction of release of radioactive material, (6) safety evaluation based on the probability theory for reactor facilities, and (7) aseismatic measures for reactor facilities. With discussions on the progress and the results of the research this time, research on the behaviour on fuel in abnormal transients including in-core and out-core experiments has been added to the third item, deleting the power-cooling mismatch experiment in Nuclear Safety Research Reactor of JAERI. Also it has been decided to add two research to the seventh item, namely measured data collection, classification and analysis, and probability assessment of failures due to an earthquake. For these 7 items, the report describes the concrete contents of research to be performed in fiscal years of 1977 and 1978, by discussing on most rational and suitable contents conceivable at present. (Wakatsuki, Y.)

Facility for the separation of krypton and recuperation of xenon

International Nuclear Information System (INIS)

Boell-Djoa, S.H.

1977-01-01

A facility is described by means of which the fission inert gases krypton 85 and xenon from spent fuel particles can be separated by fractionated freezing-out and subsequent distillation to such an extent that the xenon contains less than 1 ppb krypton 85. Then, in accordance with the stringent regulations, the krypton can be conveyed to definitive storage in special bottles, whereas the xenon can be released for industrial uses. (orig.) [de

324 Building special-case waste assessment in support of the 324 Building closure (TPA milestone M-89-05)

International Nuclear Information System (INIS)

Hobart, R.L.

1998-01-01

Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement Milestone M-89-05 requires US Department of Energy, Richland Operations Office to complete a 324 Building Special Case Waste Assessment in Support of the 324 Building Closure. This document has been prepared with the intent of meeting this regulatory commitment. Alternatives for the Special Case Wastes located in the 324 Building were defined and analyzed. Based on the criteria of safety, environmental, complexity of interfaces, risk, cost, schedule, and long-term operability and maintainability, the best alternative was chosen. Waste packaging and transportation options are also included in the recommendations. The waste disposition recommendations for the B-Cell dispersibles/tank heels and High-Level Vault packaged residuals are to direct them to the Plutonium Uranium Extraction Facility (PUREX) Number 2 storage tunnel

Defense waste processing facility at Savannah River Plant. Instrument and power jumpers

International Nuclear Information System (INIS)

Heckendorm, F.M. II.

1983-06-01

The Defense Waste Processing Facility (DWPF) for waste vitrification at the Savannah River Plant is in the final design stage. Development of equipment interconnecting devices or jumpers for use within the remotely operated processing canyon is now complete. These devices provide for the specialized instrument and electrical requirements of the DWPF process for low-voltage, high-frequency, and high-power interconnections

User Facilities of the Office of Basic Energy Sciences: A National Resource for Scientific Research

Energy Technology Data Exchange (ETDEWEB)

None

2009-01-01

The BES user facilities provide open access to specialized instrumentation and expertise that enable scientific users from universities, national laboratories, and industry to carry out experiments and develop theories that could not be done at their home institutions. These forefront research facilities require resource commitments well beyond the scope of any non-government institution and open up otherwise inaccessible facets of Nature to scientific inquiry. For approved, peer-reviewed projects, instrument time is available without charge to researchers who intend to publish their results in the open literature. These large-scale user facilities have made significant contributions to various scientific fields, including chemistry, physics, geology, materials science, environmental science, biology, and biomedical science. Over 16,000 scientists and engineers.pdf file (27KB) conduct experiments at BES user facilities annually. Thousands of other researchers collaborate with these users and analyze the data measured at the facilities to publish new scientific findings in peer-reviewed journals.

Program specialization

CERN Document Server

Marlet, Renaud

2013-01-01

This book presents the principles and techniques of program specialization - a general method to make programs faster (and possibly smaller) when some inputs can be known in advance. As an illustration, it describes the architecture of Tempo, an offline program specializer for C that can also specialize code at runtime, and provides figures for concrete applications in various domains. Technical details address issues related to program analysis precision, value reification, incomplete program specialization, strategies to exploit specialized program, incremental specialization, and data speci

Radiological Considerations in the Desgin of Synchrotron Radiation Facilities

Energy Technology Data Exchange (ETDEWEB)

Ipe, Nisy E.

1999-01-06

As synchrotron radiation (SR) facilities are rapidly being designed and built all over the world, the radiological considerations should be weighed carefully at an early stage in the design of the facility. This necessitates the understanding and identification of beam losses in the machines, especially the storage ring. The potential sources of radiation are photons and neutrons from loss of injected or stored beam, gas bremsstrahlung and synchrotron radiation. Protection against radiation is achieved through the adequate design of the shielding walls of the storage ring and the synchrotron radiation beam lines. In addition safety systems such as stoppers and shutters provide protection in the forward direction for entry into the experimental enclosures. Special care needs to be exercised in the design of SR experimental enclosures to minimize radiation leakage through penetrations and gaps between doors and walls, and doors and floors.

The Holifield Radioactive Ion Beam Facility at the Oak Ridge National Laboratory: Present status and future plans

International Nuclear Information System (INIS)

Alton, G.D.; Beene, J.R.

1998-01-01

The Holifield Radioactive Ion Beam Facility (HRIBF) is a first generation national user facility for nuclear physics and nuclear astrophysics research with radioactive ion beams (RIBs). The reconfiguration, construction, and equipment commissioning phases have been completed and the beam development program is in progress. In this article, descriptions of the facility and newly implemented experimental equipment for use in the nuclear and astrophysics programs will be given and an outline of the initial experimental program will be presented. Special target ion source related problems, endemic to the production of specific short lived RIBs will be discussed. In addition, plans, which involve either a 200 MeV or a 1 GeV proton linac driver for a second generation ISOL facility, will be presented

Corrosion testing facilities in India

International Nuclear Information System (INIS)

Viswanathan, R.; Subramanian, Venu

1981-01-01

Major types of corrosion tests, establishment of specifications on corrosion testing and scope of their application in practice are briefly described. Important organizations in the world which publish specifications/standards are listed. Indian organizations which undertake corrosion testing and test facilities available at them are also listed. Finally in an appendix, a comprehensive list of specifications relevant to corrosion testing is given. It is arranged under the headings: environmental testing, humidity tests, salt spray/fog tests, immersion tests, specification corrosion phenomena, (tests) with respect to special corrosion media, (tests) with respect to specific corrosion prevention methods, and specific corrosion tests using electrical and electrochemical methods (principles). Each entry in the list furnishes information about: nature of the test, standard number, and its specific application. (M.G.B.)

Constructed wetland with a polyculture of ornamental plants for wastewater treatment at a rural tourism facility

DEFF Research Database (Denmark)

Calheiros, Cristina S C; Bessa, Vânia S.; Mesquita, Raquel B R

2015-01-01

Sewage management in remote rural and mountain areas constitutes a challenge because of the lack of adequate infrastructure and economical capability. Tourism facilities, in particular, possess a special challenge because of huge variability in sewage production and composition as a consequence o...

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

International Nuclear Information System (INIS)

GOLDBERG, H.J.

1999-01-01

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

Nuclear Facilities Decommissioning and site remedial actions: a selected bibliography. Vol. 2

International Nuclear Information System (INIS)

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

1981-10-01

This bibliography of 643 references represents the second in a series on nuclear facility decommissioning and site remedial actions to be produced by the Radiation Effects Information Center (REIC) within the Information Center Complex, Information Division, Oak Ridge National Laboratory. The bibliography contains scientific, technical, economic, and regulatory information pertaining to the US Department of Energy's Remedial Action Program. Major chapters are: Surplus Facilities Management Program; Nuclear Facilities Decommissioning; Formerly Utilized Sites Remedial Action Program; and Uranium Mill Tailings Management. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by title. Indexes are provided for: (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. The bibliography was compiled from a specialized data base established and maintained by REIC to provide information support for the US Department of Energy's Remedial Action Program, under the cosponsorship of its four major components: Surplus Facilities Management Program; Formerly Utilized Sites Remedial Action Program; Uranium Mill Tailings Remedial Action Program; and the Grand Junction Remedial Action Program

Radiation protection of workers from uranium mines and of the public living nearby uranium mining and milling facilities

International Nuclear Information System (INIS)

Kiselev, Mikhail; Romanov, Vladimir; Shandala, Nataliya; Gneusheva, Galina; Titov, Alex; Novikova, Natalia; Smith, Graham

2008-01-01

As part of the program of nuclear power development, the Russia Federation plans to increase uranium production and to improve supply from existing uranium mining and milling facilities. Moreover, development of new uranium ore deposits is also envisaged. A corollary of these developments is the placing of a high priority on environmental and human health protection Special attention should be paid to assurance of health protection both of workers and of the public living nearby such facilities. This paper reviews the status and development of understanding of facilities in the Russian Federation from a regulatory perspective. (author)

Special nuclear material inventory sampling plans

International Nuclear Information System (INIS)

Vaccaro, H.; Goldman, A.

1987-01-01

Since their introduction in 1942, sampling inspection procedures have been common quality assurance practice. The U.S. Department of Energy (DOE) supports such sampling of special nuclear materials inventories. The DOE Order 5630.7 states, Operations Offices may develop and use statistically valid sampling plans appropriate for their site-specific needs. The benefits for nuclear facilities operations include reduced worker exposure and reduced work load. Improved procedures have been developed for obtaining statistically valid sampling plans that maximize these benefits. The double sampling concept is described and the resulting sample sizes for double sample plans are compared with other plans. An algorithm is given for finding optimal double sampling plans that assist in choosing the appropriate detection and false alarm probabilities for various sampling plans

Existing facilities and past practices: Lessons learned

International Nuclear Information System (INIS)

Huizenga, D.; Tonkay, D.W.; Owens, K.

2000-01-01

Article 12 of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) requires parties to the Joint Convention to review the safety of existing radioactive waste management facilities 'to ensure that, if necessary, all reasonably practicable improvements are made to upgrade the safety of such a facility'. Also required is a review of the results of past practices to determine 'whether any intervention is needed for reasons of radiation protection' and to consider whether the benefits of the intervention or remediation are sufficient, with regard to the costs and the impact on workers, the public and the environment. This paper discusses the experience of the United States Department of Energy in terms of the lessons learned from operating radioactive waste management facilities and from undertaking intervention or remedial action, and from decision making in an international context. Overarching safety principles are discussed, including integrating safety into all work practices and minimizing the generation of waste. Safety review lessons learned with existing facilities are discussed with respect to: applying new requirements to old facilities, taking a life-cycle perspective of waste management, improving high level waste facility management, and blending current and past practices with respect to the process used to arrive at decisions for intervention. Special emphasis is placed on the need to provide for early and substantive input from the involved regulatory agencies, Native American tribes, and those citizens and groups with an interest in the decisions. Examples of intervention decisions are discussed, including examples taken from uranium mill tailings operations, from cleanup of a former uranium processing plant site, from evaluation of pre-1970 buried 'transuranic waste' sites, and from decommissioning or closure of high level waste storage tanks. The paper concludes that on the

Conceptual design report: Nuclear materials storage facility renovation. Part 7, Estimate data

International Nuclear Information System (INIS)

1995-01-01

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment III-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VII - Estimate Data, contains the project cost estimate information

Conceptual design report: Nuclear materials storage facility renovation. Part 7, Estimate data

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-14

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment III-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VII - Estimate Data, contains the project cost estimate information.

Conceptual design report: Nuclear materials storage facility renovation. Part 6, Alternatives study

International Nuclear Information System (INIS)

1995-01-01

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for material and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment 111-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VI - Alternatives Study, presents a study of the different storage/containment options considered for NMSF

Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-14

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses.

Evalution of NDA techniques and instruments for assay of nuclear waste at a waste terminal storage facility

International Nuclear Information System (INIS)

Blakeman, E.D.; Allen, E.J.; Jenkins, J.D.

1978-05-01

The use of Nondestructive Assay (NDA) instrumentation at a nuclear waste terminal storage facility for purposes of Special Nuclear Material (SNM) accountability is evaluated. Background information is given concerning general NDA techniques and the relative advantages and disadvantages of active and passive NDA methods are discussed. The projected characteristics and amounts of nuclear wastes that will be delivered to a waste terminal storage facility are presented. Wastes are divided into four categories: High Level Waste, Cladding Waste, Intermediate Level Waste, and Low Level Waste. Applications of NDA methods to the assay of these waste types is discussed. Several existing active and passive NDA instruments are described and, where applicable, results of assays performed on wastes in large containers (e.g., 55-gal drums) are given. It is concluded that it will be difficult to routinely achieve accuracies better than approximately 10--30% with ''simple'' NDA devices or 5--20% with more sohpisticated NDA instruments for compacted wastes. It is recommended that NDA instruments not be used for safeguards accountability at a waste storage facility. It is concluded that item accountability methods be implemented. These conclusions and recommendations are detailed in a concurrent report entitled ''Recommendations on the Safeguards Requirements Related to the Accountability of Special Nuclear Material at Waste Terminal Storage Facilities'' by J.D. Jenkins, E.J. Allen and E.D. Blakeman

Multicriteria analysis of thermal and energy systems for tourist facilities

International Nuclear Information System (INIS)

Raguzin, I.

1999-01-01

The introductory part of the paper briefly presents the technological, economic and environmental optimisation procedure of thermal and energy systems for tourist facilities with the multicriteria ranging method when choosing an optimum solution. The procedure described includes a systematic analysis of the system's structure, energy-mass balance, balance of costs, environmental impact analysis and the choice of an optimum solution. Special attention was paid to criteria quantification for the choice of solution and the most appropriate ranging method.The procedure's application has been illustrated on an example of a potential tourist facility on the Island of Loinj, i.e. the locality with a potential highest category tourist development. This example includes (a) consumers (heating of rooms, preparation of hot water, heating of swimming pool water and cooling of rooms), and (b) producers (boiler room, cooling engine-rooms, a cogeneration plant and heat pumps). The data have been supplied from the project documentation for the reconstruction of the existing facilities mainly preliminary designs. The multicriteria ranging was conducted based on an appropriate computer programme for problem solution. (author)

The MOX Demonstration Facility - the stepping stone to commercial MOX production

International Nuclear Information System (INIS)

Macdonald, A.G.

1994-01-01

The paper provides an insight into MOX fuel and the economic benefits of its use in pressurized water reactors (PWRs). BNFL and AEA are collaborating in the design, construction and operation of a thermal MOX Demonstration Facility (MDF) on the AEA Windscale site in Cumbria. The process flowsheet and equipment employed in MDF are discussed and the special precautions required to handle plutonium bearing materials are highlighted. The process flowsheet includes the short binderless route which has been specially developed for use in MDF and results in fuel pellets with an homogeneous structure. MDF is the forerunner to the design and construction of a larger scale Sellafield MOX Plant and hence is the stepping-stone to commercial MOX production. (author)

Special isotope separation project, Idaho National Engineering Laboratory, Idaho Falls, Idaho

International Nuclear Information System (INIS)

1988-02-01

Construction and operation of a Special Isotope Separation (SIS) project using the Atomic Vapor Laser Isotope Separation (AVLIS) process technology at the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho are proposed. The SIS project would process fuel-grade plutonium administered by the Department of Energy (DOE) into weapon-grade plutonium using AVLIS and supporting chemical processes. The SIS project would require construction and operation of a Laser Support Facility to house the laser system and a Plutonium Processing Facility. The SIS project would be integrated with existing support and waste management facilities at the selected site. The SIS project would provide DOE with the capability of segregating the isotopes of DOE-owned plutonium into specific isotopic concentrations. This capability would provide redundancy in production capacity, technological diversity, and flexibility in DOE's production of nuclear materials for national defense. Use of the INEL site would impact 151,350 square meters (37.4 acres) of land, of which more than 70% has been previously disturbed. During construction, plant and animal habitat associated with a sagebrush vegetation community would be lost. During operation of the SIS facilities, unavoidable radiation exposures would include occupational exposures and exposures to the public from normal atmospheric releases of radioactive materials that would be minimal compared to natural background radiation

Physical protection of special nuclear material in the commercial fuel cycle. Volume I. Executive summary

International Nuclear Information System (INIS)

1976-04-01

This is the summary of the work and recommendations resulting from Sandia's participation in the Special Safeguards Study, which covered three areas: protection of SNM at fixed facilities, protection of SNM while in transit, and relocation and recovery of lost SNM. The results are published in full in five other volumes. 6 tables, 4 fig

Process-Specialized Technologies Using in Agricultural Robotics

Directory of Open Access Journals (Sweden)

I. V. Rubtsov

2018-01-01

Full Text Available The article presents the main results of the analysis of the agriculture automation level in Russia and in the world. The results of the research of the foreign market, structures and compositions of foreign-made unmanned mobile energy vehicles are presented. The main direction of development of foreign companies is the creation of new models of navigation and orientation equipment for agricultural machinery aimed to the implementation of autonomous moving and mission equipment control. Technics automatization is possible due to refitting of already existing samples with specialized attachments. According to this analysis, foreign agricultural machinery is far ahead of domestic manufacturers for the production of crew-unmanned facilities of mechanization for the agricultural sector, and the material intensity of the existing agricultural production in Russia is 3-4 times higher than that of foreign countries. The need for this kind of analysis is explained by the result of a comparison labor productivity: this index in Russia's agriculture is by 2.4 times lower than European one and 3.5 times lower than that of the USA. The Russian agriculture development retard can be eliminate through the use of modern achievements in the field of robotic systems for special purposes. The authors proved the possibility of double use of technologies because of similarity of schemes and structure of robotic systems for the solution of specialized tasks of both directions. The unmanned mobile energy vehicles can be used at sequential and parallel autonomous driving.

Regulatory system for control of nuclear facilities in Bangladesh

International Nuclear Information System (INIS)

Mollah, A.S.

2005-01-01

All human activities have associated risks. Nuclear programme is no exception. The Bangladesh Atomic Energy Commission (BAEC), constituted in February 1973 through the promulgation of the Presidential order 15 of 1973. Functions of BAEC include research and development in peaceful application of atomic energy, generation of electricity and promotion of international relations congenial to implementation of its programmes and projects. In 1993 the Government of Bangladesh promulgated the law on Nuclear Safety and Radiation Control. Considering the human resources, expertise and facilities needed for implementation of the provisions of the NSRC law, BAEC was entrusted with the responsibility to enforce it. The responsibilities of the BAEC cover nuclear and radiological safety within the installations of BAEC and radiological safety in the manifold applications of radioisotopes and radiation sources within the country. An adequate and competent infrastructure has been built to cater to the diverse nuclear and radiation protection requirements of all nuclear facilities in Bangladesh, arising at different stages from site selection to day-to-day operation. In addition, periodic inspections of the nuclear facilities are carried out. The licensing and regulatory inspection systems for controlling of nuclear installations and radiation sources are established. The paper describes the legal provisions, responsibilities and organization of BAEC with special emphasis on nuclear safety and radiation protection of nuclear facilities in Bangladesh. (author)

Record keeping for the decommissioning of nuclear facilities: Guidelines and experience

International Nuclear Information System (INIS)

2002-01-01

This report covers record keeping for the decommissioning of nuclear facilities. Nuclear facilities include large commercial facilities such as nuclear power plants or chemical nuclear facilities (e.g. for fabrication and reprocessing), but also include smaller facilities such as research reactors and medical, industrial and other research facilities. Special attention may be needed for these small facilities owing to factors such as the low priority given to decommissioning by research teams and the possibility of poorly recorded structural and operational changes. A focus on research reactors is also important because of their widespread distribution. Two IAEA TECDOCs address record keeping for radioactive waste management and disposal facilities, and therefore these areas are not covered in this report. The objective of this report is to provide information, experience and assistance on how to identify, update as needed and maintain records to assist in the decommissioning of nuclear facilities, including for the decommissioning plan. This report is intended to be useful to policy makers, regulators, owners, operators, decommissioning contractors and other interested parties. Record keeping is an integral part of overall QA or quality management programmes, and this is emphasized in this report. This report also indicates the possible consequences of not maintaining adequate records. This report describes the needs and the sources of the records for decommissioning (Section 3) and the process of identifying and selecting these records (Section 4). Section 5 considers the records from the decommissioning process itself and their retention, while Section 6 deals with QA, organization and responsibilities. The Records Management System (RMS) is dealt with in Section 7 and the management of new records in Section 8. A summary of observations is included in Section 9. The report is complemented by an appendix and annexes that describe case histories

Using the Labour of Special Squads in the Stalingrad Region in 1942-1945

Directory of Open Access Journals (Sweden)

Sergey G. Sidorov

2018-02-01

Full Text Available Special purpose camps for the NKVD of the USSR were established in 1941 to carry out a special inspection of former Red Army servicemen emerging from captivity or encirclement. In 1942 the labour of special squads started to be carried out at certain economic facilities of the country. The article deals with the issues related to the use of special forces in the Stalingrad region during the Great Patriotic War. The case of the Stalingrad region is interesting due to the fact that it showcases the overall evolution of the system of special camps, beginning with the creation of the first camps on December 28, 1941 by the Order of the NKVD of the USSR, and till their liquidation, which began in 1945. The Kamyshinsky special camp, which provided the workforce fo railway construction, was one of the first special camps in which forced labour of the special squads was used. Later, camp no. 018, which provided the workforce for restoration of the destroyed enterprises, was established in the region. The camp’s personnel worked mainly on the restoration of the Stalingrad Tractor Plant. The authors also study other regional objects on which special squads’ labour was used, as well as their organization and effectiveness. It is noted that the labour of highly qualified special squads was in demand in various sectors of the economy. The variable composition of special camps located on the territory of the Stalingrad region made a significant contribution to the restoration of the city and its major plants. This was promoted by the increasing literacy of labour organization, and by the improvement of the material supply of special camps. Special attention is paid to the transfer of the special squads to the permanent staff of industry. V.V. Shevchenko compiled the necessary sources and wrote the paper. S.G. Sidorov revealed some relevant sources, pointed out the conception and accomplished academic editing of the paper.

FLUX SENSOR EVALUATIONS AT THE ATR CRITICAL FACILITY

International Nuclear Information System (INIS)

Unruh, Troy; Rempe, Joy; Nigg, David; Imel, George; Harris, Jason; Bonebrake, Eric

2010-01-01

The Advanced Test Reactor (ATR) and the ATR Critical (ATRC) facilities lack real-time methods for detecting thermal neutron flux and fission reaction rates for irradiation capsules. Direct measurements of the actual power deposited into a test are now possible without resorting to complicated correction factors. In addition, it is possible to directly measure minor actinide fission reaction rates and to provide time-dependent monitoring of the fission reaction rate or fast/thermal flux during transient testing. A joint Idaho State University/Idaho National Laboratory ATR National Scientific User Facility (ATR NSUF) project was recently initiated to evaluate new real-time state-of-the-art in-pile flux detection sensors. Initially, the project is comparing the accuracy, response time, and long duration performance of French Atomic Energy Commission (CEA)-developed miniature fission chambers, specialized self-powered neutron detectors (SPNDs) by the Argentinean National Energy Commission (CNEA), specially developed commercial SPNDs, and back-to-back fission (BTB) chambers developed by Argonne National Laboratory (ANL). As discussed in this paper, specialized fixturing and software was developed by INL to facilitate these joint ISU/INL evaluations. Calculations were performed by ISU to assess the performance of and reduce uncertainties in flux detection sensors and compare data obtained from these sensors with existing integral methods employed at the ATRC. Ultimately, project results will be used to select the detector that can provide the best online regional ATRC power measurement. It is anticipated that project results may offer the potential to increase the ATRC's current power limit and its ability to perform low-level irradiation experiments. In addition, results from this effort will provide insights about the viability of using these detectors in the ATR. Hence, this effort complements current activities to improve ATR software tools, computational protocols

Calibration of high-dose radiation facilities (Handbook)

International Nuclear Information System (INIS)

Gupta, B.L.; Bhat, R.M.

1986-01-01

In India at present several high intensity radiation sources are used. There are 135 teletheraphy machines and 65 high intensity cobalt-60 sources in the form of gamma chambers (2.5 Ci) and PANBIT (50 Ci). Several food irradiation facilities and a medical sterilization plant ISOMED are also in operation. The application of these high intensity sources involve a wide variation of dose from 10 Gy to 100 kGy. Accurate and reproducible radiation dosimetry is essential in the use of these sources. This handbook is especially compiled for calibration of high-dose radiation facilities. The first few chapters discuss such topics as interaction of radiation with matter, radiation chemistry, radiation processing, commonly used high intensity radiation sources and their special features, radiation units and dosimetry principles. In the chapters which follow, chemical dosimeters are discussed in detail. This discussion covers Fricke dosimeter, FBX dosimeter, ceric sulphate dosimeter, free radical dosimetry, coloured indicators for irrdiation verification. A final chapter is devoted to practical hints to be followed in calibration work. (author)

Special waste form lysimeters-arid. Annual report, 1985

International Nuclear Information System (INIS)

Walter, M.B.; Graham, M.J.

1985-09-01

The Special Waste Form Lysimeters-Arid program was initiated to determine typical source terms generated by commercial solidified low-level nuclear waste in an arid climate. Waste-form leaching tests are being conducted at a field facility at the Hanford site near Richland, Washington. A similar program is being conducted at a humid site. The field facility consists of 10 lysimeters placed around a central instrument caisson. The waste samples from boiling water and pressurized water reactors were emplaced in 1984, and the lysimeters are being monitored for movement of contaminants and water. Solidifying agents being tested include vinyl ester-styrene, bitumen, and cement. Laboratory leaching and geochemical modeling studies are being conducted to predict expected leach rates at the field site and to aid field-data interpretation. Small samples of the solidified waste forms were made for use in the laboratory leaching studies that include standard leach tests and leaching of solidified waste forms in soil columns. Complete chemical and radionuclide analyses are being conducted on the solid and liquid portions of the wastes. 2 refs

Special Waste Form Lysimeters-Arid: annual report 1985

International Nuclear Information System (INIS)

Walter, M.B.; Graham, M.J.

1986-01-01

The Special Waste Form Lysimeters-Arid program was initiated to determine typical source terms generated by commercial solidified low-level nuclear waste in an arid climate. Waste-form leaching tests are being conducted at a field facility at the Hanford site near Richland, Washington. A similar program is being conducted at a humid site. The field facility consists of 10 lysimeters placed around a central instrument caisson. The waste samples from boiling water and pressurized water reactors were emplaced in 1984, and the lysimeters are being monitored for movement of contaminants and water. Solidifying agents being tested include vinyl ester-styrene, bitumen, and cement. Laboratory leaching and geochemical modeling studies are being conducted to predict expected leach rates at the field site and to aid field-data interpretation. Small samples of the solidified waste forms were made for use in the laboratory leaching studies that include standard leach tests and leaching of solidified waste forms in soil columns. Complete chemical and radionuclide analyses are being conducted on the solid and liquid portions of the wastes

Model of Providing Assistive Technologies in Special Education Schools.

Science.gov (United States)

Lersilp, Suchitporn; Putthinoi, Supawadee; Chakpitak, Nopasit

2015-05-14

Most students diagnosed with disabilities in Thai special education schools received assistive technologies, but this did not guarantee the greatest benefits. The purpose of this study was to survey the provision, use and needs of assistive technologies, as well as the perspectives of key informants regarding a model of providing them in special education schools. The participants were selected by the purposive sampling method, and they comprised 120 students with visual, physical, hearing or intellectual disabilities from four special education schools in Chiang Mai, Thailand; and 24 key informants such as parents or caregivers, teachers, school principals and school therapists. The instruments consisted of an assistive technology checklist and a semi-structured interview. Results showed that a category of assistive technologies was provided for students with disabilities, with the highest being "services", followed by "media" and then "facilities". Furthermore, mostly students with physical disabilities were provided with assistive technologies, but those with visual disabilities needed it more. Finally, the model of providing assistive technologies was composed of 5 components: Collaboration; Holistic perspective; Independent management of schools; Learning systems and a production manual for users; and Development of an assistive technology center, driven by 3 major sources such as Government and Private organizations, and Schools.

Compressed Natural Gas Vehicle Maintenance Facility Modification Handbook

Energy Technology Data Exchange (ETDEWEB)

Kelly, Kay L. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Ramsden, Margo M. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Gonzales, John E. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Lynch, Lauren [National Renewable Energy Lab. (NREL), Golden, CO (United States); Coale, Bob [Gladstein, Neandross & Associates, Santa Monica, CA (United States); Kohout, Jarrod [Gladstein, Neandross & Associates, Santa Monica, CA (United States)

2017-09-28

gas detectors and control systems, or specialized space heating, which are not needed in facilities servicing liquid-fuel vehicles. This handbook covers maintenance facilities that service CNG-fueled vehicles. Although similar requirements are mandated for liquefied natural gas (LNG) or liquefied petroleum gas (LPG) fueled vehicles, LNG and LPG are not covered in this handbook.

Revisited. Euratom's ownership of special fissile materials

International Nuclear Information System (INIS)

Pelzer, Norbert

2015-01-01

Among all Treaties on the Foundation of the European Community, seemingly, the Euratom Treaty ist the most unobtrusive one having even nearly been declared dead occasionally. For the opponents of nuclear energy the treaty is a thorn in their side because it aims for the peaceful exploitation of nuclear energy. Actually, the treaty likewise aims for the protection of dangers of nuclear energy and encloses a bundle of collective control instruments. The protective purpose provides the community with a strong position in numerous fields towards nuclear energy users including the right to intervene in the operations of nuclear facilities. The communitie's position is further strengthened by the communitie's ownership on special fissile materials. The EAEC Treaty determines: 'Special fissile materials are owned by the community'. The material content of Euratom's ownership is limited by Article 87 of the EAEC Treaty: Unlimited right of use and consumption is granted to the properly possessors unless obligations of the Euratom Treaty oppose. Inherently, the community does not have these rights. It was asked what would be left to the owner Euratom if the properly possessor is entitled to unlimited right of use and even right of consumption.

Autonomous underwater handling system for service, measurement and cutting tasks for the decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Hahn, M.; Haferkamp, H.; Bach, W.; Rose, N.

1992-01-01

For about 10 years the Institute for Material Science at the Hanover University has worked on projects of underwater cutting and welding. Increasing tasks to be done in nuclear facilities led to the development of special handling systems to support and handle the cutting tools. Also sensors and computers for extensive and complex tasks were integrated. A small sized freediving handling system, equipped with 2 video cameras, ultrasonic and radiation sensors and a plasma cutting torch for inspection and decommissioning tasks in nuclear facilities is described in this paper. (Author)

Particular intervention plan of the Areva La Hague facility - 2012 edition

International Nuclear Information System (INIS)

2012-01-01

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Areva NC La Hague fuel reprocessing plant (located on the territories of Beaumont-Hague, Digulleville, Herqueville, Jobourg and Omonville-la-Petite towns, Manche, France) which comprises the totally decommissioned UP2 400 unit, and the UP2 800 production unit still in operation

78 FR 18350 - Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2013-03-26

... Supply Company in Fort Wayne, Indiana, as an addition to the Special Exposure Cohort (SEC) under the... Employees who worked for Joslyn Manufacturing and Supply Company at the covered facility in Fort Wayne, Indiana, from March 1, 1943, through December 31, 1947, for a number of work days aggregating at least 250...

Checking the special professional qualification of selected personnel of Czechoslovak nuclear power facilities

International Nuclear Information System (INIS)

Kovar, P.; Bahnova, V.

1990-01-01

The system of examinations of selected staff members of Czechoslovak nuclear power plants for their special professional quanlification is described in detail. This selected personnel includes secondary circuit operators, primary circuit operators, graduate shift leaders as well as reactor unit managers. Attention is paid to the structure, methodology, contents and criteria of evaluation of the written, oral and practical parts of the examination, which is sat for before the State Examination Commission. Based on the results of the examinations, the Czechoslovak Atomic Energy Commission grants, prolongs or cancels licenses for the particular functions. Over the period from 1985 to March 1989, 394 new licenses were issued, 93 licenses were prolonged and 4 were withdrawn. (Z.M.). 7 figs., 3 tabs., 3 refs

The Sight Distance Issues with Retrofitted Single-Lane HOV Facilities

Directory of Open Access Journals (Sweden)

Zhongren Wang

2013-06-01

Full Text Available It is well-known that obstruction inside a highway horizontal curve will lead to impaired sight distance. Highway alignment design standards in terms of the minimum horizontal curve radius are specified to allow for adequate stopping sight distance at given design speeds. For a single-lane HOV facility, inside curve obstruction may occur no matter when the facility curves to the left (per travel direction or right. A unique situation that calls for special attention is that the adjacent mixed-flow lane traffic, once queued, may become sight obstruction. Calculations indicated that such obstruction may govern the minimum curve radius design as long as the left shoulder is not less than 0.92 m, when the HOV lane is contiguous to the mixed-flow lanes. Such governance may necessitate design speed reduction, horizontal and cross-section design adjustment, or both.

Semi-annual report on strategic special nuclear material inventory differences

International Nuclear Information System (INIS)

1979-01-01

This report provides and explains the generally small differences between the amounts of nuclear materials charged to DOE facilities and the amounts that could be physically inventoried. This report covers data for the period from October 1, 1977, through March 31, 1978, and includes accounting corrections for data from earlier periods. The data and explanations, together with the absence of physical indications of any theft attempt, support a finding that during this period no theft or diversion of a significant amount of strategic special nuclear material has occurred

Recycling entire DOE facilities: The National Conversion Pilot Project

International Nuclear Information System (INIS)

Floyd, D.R.

1996-01-01

The Mission of the National Conversion Pilot Project - to demonstrate, at the Rocky Flats Site, the feasibility of economic conversion of DOE Sites - is succeeding. Contaminated facilities worth $92 million are being cleaned and readied for reuse by commercial industry to manufacture products needed in the DOE cleanup and elsewhere. Former Rocky Flats workers have been hired, recultured, are conducting the cleanup and are expected to perform the future manufacturing by recycling DOE RSM and other metals requiring special environmental controls. Stakeholder sway over project activities is welcome and strong

Specialized science.

Science.gov (United States)

Casadevall, Arturo; Fang, Ferric C

2014-04-01

As the body of scientific knowledge in a discipline increases, there is pressure for specialization. Fields spawn subfields that then become entities in themselves that promote further specialization. The process by which scientists join specialized groups has remarkable similarities to the guild system of the middle ages. The advantages of specialization of science include efficiency, the establishment of normative standards, and the potential for greater rigor in experimental research. However, specialization also carries risks of monopoly, monotony, and isolation. The current tendency to judge scientific work by the impact factor of the journal in which it is published may have roots in overspecialization, as scientists are less able to critically evaluate work outside their field than before. Scientists in particular define themselves through group identity and adopt practices that conform to the expectations and dynamics of such groups. As part of our continuing analysis of issues confronting contemporary science, we analyze the emergence and consequences of specialization in science, with a particular emphasis on microbiology, a field highly vulnerable to balkanization along microbial phylogenetic boundaries, and suggest that specialization carries significant costs. We propose measures to mitigate the detrimental effects of scientific specialism.

Facility effluent monitoring plan determinations for the 400 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-09-01

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

Systematic approach to remote maintenance in the fuels and materials examination facility

International Nuclear Information System (INIS)

Frandsen, G.B.; Nash, C.R.; Divona, C.J.; May, R.F.

1979-01-01

The Fuels and Materials Examination Facility (FMEF) is systematically analyzed from a remote maintenance standpoint using functional analysis methods. From the analysis the remote maintainability of equipment is ascertained, required tooling lists are formed, and maintenance downtimes are established. These techniques identify deficiencies or inefficiencies in the early design stage where changes have a minimum impact on cost. Special tooling and fixture requirements are minimized by standardizing remote maintenance design features

[Anesthesia practice in Catalan hospitals and other health care facilities].

Science.gov (United States)

Villalonga, Antonio; Sabaté, Sergi; Campos, Juan Manuel; Fornaguera, Joan; Hernández, Carmen; Sistac, José María

2006-05-24

training programs. The numbers of postoperative admissions to critical care units and of specialized analgesic techniques performed were higher in ICS hospitals, in facilities with over 500 beds, and in teaching hospitals. The complexity of both anesthesia and surgical practice and the severity of patient condition increased with hospital size and public funding status.

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

International Nuclear Information System (INIS)

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

1985-12-01

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

Quality assurance project plan for the UMTRA technical assistance contractor hydrochemistry facility. Final report

International Nuclear Information System (INIS)

1993-07-01

The Uranium Mill Tailings Remedial Action (UMTRA) hydrochemistry facility is used to perform a limited but important set of services for the UMTRA Project. Routine services include support of field-based hydrological and geochemical operations and water sampling activities. Less commonly, the hydrology and geochemistry staff undertake special studies and site characterization studies at this facility. It is also used to train hydrologists, geochemists, and groundwater sampling crews. A review of this Quality Assurance Project Plan (QAPP) shall be accomplished once each calendar year. This review will be targeted to be accomplished not sooner than 6 months and not later than 18 months after the last review

Implementation of remove monitoring in facilities under safeguards with unattended systems

International Nuclear Information System (INIS)

Beddingfield, David H.; Nordquist, Heather A.; Umebayaashi, Eiji

2009-01-01

Remote monitoring is being applied by the International Atomic Energy Agency (IAEA) at nuclear facilities around the world. At the Monju Reactor in Japan we have designed, developed and implemented a remote monitoring approach that can serve as a model for applying remote monitoring to facilities that are already under full-scope safeguards using unattended instrumentation. Remote monitoring implementations have historically relied upon the use of specialized data collection hardware and system design features that integrate remote monitoring into the safeguards data collection system. The integration of remote monitoring and unattended data collection increases the complexity of safeguards data collection systems. This increase in complexity necessarily produces a corresponding reduction of system reliability compared to less-complex unattended monitoring systems. At the Monju facility we have implemented a remote monitoring system that is decoupled from the activity of safeguards data collection. In the completed system the function of remote data transfer is separated from the function of safeguards data collection. As such, a failure of the remote monitoring function cannot produce an associated loss of safeguards data, as is possible with integrated remote-monitoring implementations. Currently, all safeguards data from this facility is available to the IAEA on a 24/7 basis. This facility employs five radiation-based unattended systems, video surveillance and numerous optical seal systems. The implementation of remote monitoring at this facility, while increasing the complexity of the safeguards system, is designed to avoid any corresponding reduction in reliability of the safeguards data collection systems by having decoupled these functions. This design and implementation can serve as a model for implementation of remote monitoring at nuclear facilities that currently employ unattended safeguards systems.

Training practices to support decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Bourassa, J.; Clark, C.R.; Kazennov, A.; Laraia, M.; Rodriguez, M.; Scott, A.; Yoder, J.

2006-01-01

Adequate numbers of competent personnel must be available during any phase of a nuclear facility life cycle, including the decommissioning phase. While a significant amount of attention has been focused on the technical aspects of decommissioning and many publications have been developed to address technical aspects, human resource management issues, particularly the training and qualification of decommissioning personnel, are becoming more paramount with the growing number of nuclear facilities of all types that are reaching or approaching the decommissioning phase. One of the keys to success is the training of the various personnel involved in decommissioning in order to develop the necessary knowledge and skills required for specific decommissioning tasks. The operating organisations of nuclear facilities normally possess limited expertise in decommissioning and consequently rely on a number of specialized organisations and companies that provide the services related to the decommissioning activities. Because of this there is a need to address the issue of assisting the operating organisations in the development and implementation of human resource management policies and training programmes for the facility personnel and contractor personnel involved in various phases of decommissioning activities. The lessons learned in the field of ensuring personnel competence are discussed in the paper (on the basis of information and experiences accumulated from various countries and organizations, particularly, through relevant IAEA activities). Particularly, the following aspects are addressed: transition of training from operational to decommissioning phase; knowledge management; target groups, training needs analysis, and application of a systematic approach to training (SAT); content of training for decommissioning management and professional staff, and for decommissioning workers; selection and training of instructors; training facilities and tools; and training as

Design and realization on function of pre-forming and continuous winding for HT-7U special winding machine

International Nuclear Information System (INIS)

Yu Jie; Gao Daming; Wen Jun; Zhu Wenhua; Cheng Leping; Tao Yuming

2000-05-01

The winding machine is one of the critical facilities for R and D of HT-7U construction. The machine mainly consists of five parts, CICC pay-off spool, a four-rollers straightening assembly, a four-roller forming/bending assembly, continuous winding structure and CNC control system with three-axis CNC control. The facility is needed for CICC magnet fabrication of HT-7U. The main requirements of the winding machine are: continuous winding to reduce number of joints inside the coils; pre-forming CICC conductor to avoid winding with tension; suitable for all TF and PF coils within the scope of various coil shape and dimension limit; improving the configuration tolerance, specially flatness of the CICC conductor. The author emphasizes on the design and realization on function of Pre-forming and Continuous Winding for HT-7U special winding machine. The winding machine with high accuracy has just been developed and applied to the construction of HT-7U model coils

Consideration on Preventive and Protective Measures Against Insider Threats at R.O.K. Nuclear Facilities

International Nuclear Information System (INIS)

Lee, Seung Min; Lee, Jung Ho; Koh, Moon Sung

2016-01-01

This paper focuses on the current status of measures used to prevent, detect and respond to potential insiders at nuclear facilities in the Republic of KOREA. Measures against insiders are then analyzed based on IAEA guidelines. Insiders are able to take advantage of their access rights and knowledge of a facility to bypass dedicated security measures. They can also threaten cyber security, safety measures, and material control and accountancy (MC and A). Insiders are likely to have the time to plan their actions. In addition, they may work with an external adversary who shares their objectives. An insider threat is a great risk to a security system because of the access, authority, and special knowledge that someone within a facility possesses. Therefore, it is imperative that effective measures be taken to prevent insider incidents. A combination of preventive and protective measures offers the best solution to mitigating rogue elements within a facility

Consideration on Preventive and Protective Measures Against Insider Threats at R.O.K. Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Seung Min; Lee, Jung Ho; Koh, Moon Sung [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2016-05-15

This paper focuses on the current status of measures used to prevent, detect and respond to potential insiders at nuclear facilities in the Republic of KOREA. Measures against insiders are then analyzed based on IAEA guidelines. Insiders are able to take advantage of their access rights and knowledge of a facility to bypass dedicated security measures. They can also threaten cyber security, safety measures, and material control and accountancy (MC and A). Insiders are likely to have the time to plan their actions. In addition, they may work with an external adversary who shares their objectives. An insider threat is a great risk to a security system because of the access, authority, and special knowledge that someone within a facility possesses. Therefore, it is imperative that effective measures be taken to prevent insider incidents. A combination of preventive and protective measures offers the best solution to mitigating rogue elements within a facility.

Biosafety Procedure for Safe Handling of Genetically Modified Plant Materials in Bio Design Facility

International Nuclear Information System (INIS)

Zaiton Ahmad; Shuhaimi Shamsudin; Mohamed Najli Mohamed Yasin; Affrida Abu Hassan; Mohd Zaid Hassan; Rusli Ibrahim

2015-01-01

Bio Design Facility is the specifically designed glass house for propagation, screening and analysis of high quality plant varieties developed through biotechnology or a combination of nuclear technology and biotechnology. High quality plant varieties especially genetically modified plants (GMO) require a special glass house facility for propagation and screening to isolate them from cross-pollinating with wild type varieties in surrounding ecosystem, and for carrying out evaluation of possible risks of the plants to human, animal and environment before they are proven safe for field trials or commercial release. This facility which was developed under the Ninth Malaysia Plan is classified as the Plant Containment Level 2 and is compliance with the bio safety regulations and guidance for the safe release of GMO according to Malaysian Bio safety Act 2007. Bio Design Facility is fully operational since 2010 and in 2012, it has also been certified as the glass house for post-entry quarantine by The Department of Agriculture. This paper summarizes the bio safety procedure for a safe, controlled and contained growing and evaluation of GMO in Bio Design Facility. This procedure covers the physical (containment and equipment's) and operational (including responsibility, code of practice, growing, decontamination and disposal of plant materials, emergency and contingency plan) aspects of the facility. (author)

Towards a Unified Environmental Monitoring, Control and Data Management System for Irradiation Facilities: the CERN IRRAD Use Case

CERN Document Server

Gkotse, Blerina; Jouvelot, Pierre; Matli, Emanuele; Pezzullo, Giuseppe; Ravotti, Federico

2017-01-01

The qualification of materials, electronic components and equipment for the CERN High Energy Physics experiments and beyond requires testing against possible radiation effects. These quite complex tests are performed by specialized teams working in irradiation facilities such as IRRAD, the Proton Irradiation Facility at CERN. Building upon the details of the overall irradiation control, monitoring, and logistical systems of IRRAD as a use case, we introduce the motivations for and general architecture of its new data management framework, currently under development at CERN. This infrastructure is intended to allow for the seamless and comprehensive handling of IRRAD irradiation experiments and to help manage all aspects of the facility. Its architecture, currently focused on the specific requirements of the IRRAD facility, is intended to be upgraded to a general framework that could be used in other irradiation facilities within the radiation effects community, as well as for other applications.

75 FR 57859 - Specially Adapted Housing and Special Home Adaptation

Science.gov (United States)

2010-09-23

... Home Adaptation AGENCY: Department of Veterans Affairs. ACTION: Final rule. SUMMARY: The Department of... specially adapted housing and special home adaptation grants. This final rule incorporates certain... regulations pertaining to eligibility for specially adapted housing (SAH) grants and special home adaptation...

Incorporating functional requirements into the structural design of the Defense Waste Processing Facility

International Nuclear Information System (INIS)

Hsiu, F.J.; Ng, C.K.; Almuti, A.M.

1986-01-01

Vitrification Building-type structures have unique features and design needs. The structural design requires new concepts and custom detailing. The above special structural designs have demonstrated the importance of the five design considerations listed in the introduction. Innovative ideas and close coordination are required to achieve the design objectives. Many of these innovations have been applied to the DWPF facility which is a first of a kind

40 CFR 122.24 - Concentrated aquatic animal production facilities (applicable to State NPDES programs, see § 123...

Science.gov (United States)

2010-07-01

... NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM Permit Application and Special NPDES Program Requirements... 40 Protection of Environment 21 2010-07-01 2010-07-01 false Concentrated aquatic animal production facilities (applicable to State NPDES programs, see § 123.25). 122.24 Section 122.24 Protection of...

Report of conceptual design for TRU solid waste facilities adjacent to 200H Area: Savannah River Plant

International Nuclear Information System (INIS)

1978-02-01

Facilities for consolidating Savannah River Plant solid transuranic (TRU) waste and placing in long-term safe, retrievable storage have been designed conceptually. A venture guidance appraisal of cost for the facilities has been prepared. The proposed site of the new processing area is adjacent to existing H Area facilities. The scopes of work comprising the conceptual design describe facilities for: exhuming high-level TRU waste from buried and pad-stored locations in the plant burial ground; opening, emptying, and sorting waste containers and their contents within shielded, regulated enclosures; volume-reducing the noncombustibles by physical processes and decontaminating the metal waste; burning combustibles; fixing the consolidated waste forms in a concrete matrix within a double-walled steel container; placing product containers in a retrievable surface storage facility adjacent to the existing plant burial ground; and maintaining accountability of all special nuclear materials. Processing, administration, and auxiliary service buildings are to be located adjacent to existing H Area facilities where certain power and waste liquid services will be shared

Active neutron technique for detecting attempted special nuclear material diversion

International Nuclear Information System (INIS)

Smith, G.W.; Rice, L.G. III.

1979-01-01

The identification of special nuclear material (SNM) diversion is necessary if SNM inventory control is to be maintained at nuclear facilities. (Special nuclear materials are defined for this purpose as either 235 U of 239 Pu.) Direct SNM identification by the detection of natural decay or fission radiation is inadequate if the SNM is concealed by appropriate shielding. The active neutron interrogation technique described combines direct SNM identification by delayed fission neutron (DFN) detection with implied SNM detection by the identification of materials capable of shielding SNM from direct detection. This technique is being developed for application in an unattended material/equipment portal through which items such as electronic instruments, packages, tool boxes, etc., will pass. The volume of this portal will be 41-cm wide, 53-cm high and 76-cm deep. The objective of this technique is to identify an attempted diversion of at least 20 grams of SNM with a measurement time of 30 seconds

Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

International Nuclear Information System (INIS)

1995-06-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage

Strategies for energy benchmarking in cleanrooms and laboratory-type facilities

International Nuclear Information System (INIS)

Sartor, Dale; Piette, Mary Ann; Tschudi, William; Fok, Stephen

2000-01-01

Buildings with cleanrooms and laboratories are growing in terms of total floor area and energy intensity. This building type is common in institutions such as universities and in many industries such as microelectronics and biotechnology. These buildings, with high ventilation rates and special environmental considerations, consume from 4 to 100 times more energy per square foot than conventional commercial buildings. Owners and operators of such facilities know they are expensive to operate, but have little way of knowing if their facilities are efficient or inefficient. A simple comparison of energy consumption per square foot is of little value. A growing interest in benchmarking is also fueled by: A new U.S. Executive Order removing the exemption of federal laboratories from energy efficiency goals, setting a 25% savings target, and calling for baseline guidance to measure progress; A new U.S. EPA and U.S. DOE initiative, Laboratories for the 21st Century, establishing voluntary performance goals and criteria for recognition; and A new PG and E market transformation program to improve energy efficiency in high tech facilities, including a cleanroom energy use benchmarking project. This paper identifies the unique issues associated with benchmarking energy use in high-tech facilities. Specific options discussed include statistical comparisons, point-based rating systems, model-based techniques, and hierarchical end-use and performance-metrics evaluations

Final generic environmental impact statement on decommissioning of nuclear facilities

International Nuclear Information System (INIS)

1988-08-01

This final generic environmental impact statement was prepared as part of the requirement for considering changes in regulations on decommissioning of commercial nuclear facilities. Consideration is given to the decommissioning of pressurized water reactors, boiling water reactors, research and test reactors, fuel reprocessing plants (FRPs) (currently, use of FRPs in the commercial sector is not being considered), small mixed oxide fuel fabrication plants, uranium hexafluoride conversion plants, uranium fuel fabrication plants, independent spent fuel storage installations, and non-fuel-cycle facilities for handling byproduct, source and special nuclear materials. Decommissioning has many positive environmental impacts such as the return of possibly valuable land to the public domain and the elimination of potential problems associated with increased numbers of radioactively contaminated facilities with a minimal use of resources. Major adverse impacts are shown to be routine occupational radiation doses and the commitment of nominally small amounts of land to radioactive waste disposal. Other impacts, including public radiation doses, are minor. Mitigation of potential health, safety, and environmental impacts requires more specific and detailed regulatory guidance than is currently available. Recommendations are made as to regulatory decommissioning particulars including such aspects as decommissioning alternatives, appropriate preliminary planning requirements at the time of commissioning, final planning requirements prior to termination of facility operations, assurance of funding for decommissioning, environmental review requirements. 26 refs., 7 figs., 68 tabs

2010 Annual Wastewater Reuse Report for the Idaho National Laboratory Site's Central Facilities Area Sewage Treatment Plant

Energy Technology Data Exchange (ETDEWEB)

Mike lewis

2011-02-01

This report describes conditions, as required by the state of Idaho Wastewater Reuse Permit (#LA-000141-03), for the wastewater land application site at Idaho National Laboratory Site’s Central Facilities Area Sewage Treatment Plant from November 1, 2009, through October 31, 2010. The report contains the following information: • Site description • Facility and system description • Permit required monitoring data and loading rates • Status of special compliance conditions • Discussion of the facility’s environmental impacts. During the 2010 permit year, approximately 2.2 million gallons of treated wastewater was land-applied to the irrigation area at Central Facilities Area Sewage Treatment plant.

Study on Nuclear Facility Cyber Security Awareness and Training Programs

International Nuclear Information System (INIS)

Lee, Jung-Woon; Song, Jae-Gu; Lee, Cheol-Kwon

2016-01-01

Cyber security awareness and training, which is a part of operational security controls, is defined to be implemented later in the CSP implementation schedule. However, cyber security awareness and training is a prerequisite for the appropriate implementation of a cyber security program. When considering the current situation in which it is just started to define cyber security activities and to assign personnel who has responsibilities for performing those activities, a cyber security awareness program is necessary to enhance cyber security culture for the facility personnel to participate positively in cyber security activities. Also before the implementation of stepwise CSP, suitable education and training should be provided to both cyber security teams (CST) and facility personnel who should participate in the implementation. Since such importance and urgency of cyber security awareness and training is underestimated at present, the types, trainees, contents, and development strategies of cyber security awareness and training programs are studied to help Korean nuclear facilities to perform cyber security activities more effectively. Cyber security awareness and training programs should be developed ahead of the implementation of CSP. In this study, through the analysis of requirements in the regulatory standard RS-015, the types and trainees of overall cyber security training programs in nuclear facilities are identified. Contents suitable for a cyber security awareness program and a technical training program are derived. It is suggested to develop stepwise the program contents in accordance with the development of policies, guides, and procedures as parts of the facility cyber security program. Since any training programs are not available for the specialized cyber security training in nuclear facilities, a long-term development plan is necessary. As alternatives for the time being, several cyber security training courses for industrial control systems by

Study on Nuclear Facility Cyber Security Awareness and Training Programs

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung-Woon; Song, Jae-Gu; Lee, Cheol-Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Cyber security awareness and training, which is a part of operational security controls, is defined to be implemented later in the CSP implementation schedule. However, cyber security awareness and training is a prerequisite for the appropriate implementation of a cyber security program. When considering the current situation in which it is just started to define cyber security activities and to assign personnel who has responsibilities for performing those activities, a cyber security awareness program is necessary to enhance cyber security culture for the facility personnel to participate positively in cyber security activities. Also before the implementation of stepwise CSP, suitable education and training should be provided to both cyber security teams (CST) and facility personnel who should participate in the implementation. Since such importance and urgency of cyber security awareness and training is underestimated at present, the types, trainees, contents, and development strategies of cyber security awareness and training programs are studied to help Korean nuclear facilities to perform cyber security activities more effectively. Cyber security awareness and training programs should be developed ahead of the implementation of CSP. In this study, through the analysis of requirements in the regulatory standard RS-015, the types and trainees of overall cyber security training programs in nuclear facilities are identified. Contents suitable for a cyber security awareness program and a technical training program are derived. It is suggested to develop stepwise the program contents in accordance with the development of policies, guides, and procedures as parts of the facility cyber security program. Since any training programs are not available for the specialized cyber security training in nuclear facilities, a long-term development plan is necessary. As alternatives for the time being, several cyber security training courses for industrial control systems by

Data used for safety assessment of reprocessing facilities

International Nuclear Information System (INIS)

Nomura, Yasushi; Suzuki, Atsuyuki; Kanagawa, Akira

1990-08-01

For safety assessment of a reprocessing facility, it is important to know performance of radioactive materials in their accidental release and transfer. Accordingly, it is necessary to collect and prepare data for use in analyses for their performance. In JAERI, experiments such as for data acquisition, for source-term evaluation and for radioactive material transfer, are now planned to be performed. Prior to these experiments, it is decided to investigate data in use for accidental safety assessment of reprocessing plants and their based experimental data, thus to make it possible to recommend reasonable values for safety analysis parameters by evaluating the investigated results, to select the experimental items, to edit a safety assessment handbook and so on. In this line of objectives, JAERI rewarded a two-year contract of investigation to Nuclear Safety Research Association, to make a working group under a special committee on data investigation for reprocessing facility safety assessment. This report is a collection of results reviewed and checked by the working group. The contents consist of two parts, one for investigation and review of data used for safety assessment of domestic or oversea reprocessing facilities, and the other for investigation, review and evaluation of ANSI recommended American standard data reported by E. Walker together with their based experimental data resorting to the original referred reports. (author)

Affordable rejuvenation: a prototype facility in action.

Science.gov (United States)

Prokopov, Arkadi F; Reinmuth, Juergen

2010-01-01

The Strategies for Engineered Negligible Senescence (SENS) agenda contemplates specialized centers that offer a periodic rejuvenation and biogerontological maintenance for their clients. Although high-tech interventions are still in an early research phase, well-proven natural techniques, such as various forms of caloric/nutritional restriction, physical training, and preconditioning treatments, are not unanimously embraced due to poor adherence of patients. The practicability of such interventions can be significantly improved by "engineering" them for higher efficiency and better user friendliness. We describe practical experience in developing and running a prototype facility that uses rejuvenative treatment protocols, derived from two natural life span-prolonging strategies: Intermittent calorie/nutritive restriction (ICR) and intermittent oxygen restriction (IOR).

Remote mixed oxide fabrication facility development. Volume 2. State-of-the-art review of remote maintenance system technology

International Nuclear Information System (INIS)

Horgos, R.M.; Masch, M.L.

1979-06-01

This report provides a state-of-the-art review of remote systems technology, which includes manipulators, process connectors, vision systems and specialized process systems. A proposed mixed oxide fuel fabrication facility was reviewed and evaluated for identification of major remote maintenance and repair tasks. The technological areas were evaluated on the basis of their suitability or applicability for remote maintenance and repair of a proposed fully remote operating mixed oxide fuel fabrication facility. A technological base exists from which the design criteria for a reliable, remote operating facility can be established. Commercially available systems and components, along with those remote technologies now in development, will require modifications to adapt them to specific plant designs and requirements

Cost (non)-recovery by platform technology facilities in the Bio21 Cluster.

Science.gov (United States)

Gibbs, Gerard; Clark, Stella; Quinn, Julieanne; Gleeson, Mary Joy

2010-04-01

Platform technologies (PT) are techniques or tools that enable a range of scientific investigations and are critical to today's advanced technology research environment. Once installed, they require specialized staff for their operations, who in turn, provide expertise to researchers in designing appropriate experiments. Through this pipeline, research outputs are raised to the benefit of the researcher and the host institution. Platform facilities provide access to instrumentation and expertise for a wide range of users beyond the host institution, including other academic and industry users. To maximize the return on these substantial public investments, this wider access needs to be supported. The question of support and the mechanisms through which this occurs need to be established based on a greater understanding of how PT facilities operate. This investigation was aimed at understanding if and how platform facilities across the Bio21 Cluster meet operating costs. Our investigation found: 74% of platforms surveyed do not recover 100% of direct operating costs and are heavily subsidized by their home institution, which has a vested interest in maintaining the technology platform; platform managers play a major role in establishing the costs and pricing of the facility, normally in a collaborative process with a management committee or institutional accountant; and most facilities have a three-tier pricing structure recognizing internal academic, external academic, and commercial clients.

Atomics International environmental monitoring and facility effluent annual report, 1976

International Nuclear Information System (INIS)

Moore, J.D.

1977-01-01

Environmental and facility effluent radioactivity monitoring at Atomics International (AI) is performend by the Radiation and Nuclear Safety Unit of the Health, Safety, and Radiation Services Department. Soil, vegetation, and surface water are routinely sampled to a distance of 10 miles from AI sites. Continuous ambient air sampling and thermoluminescent dosimetry are performed on site for monitoring airborne radioactivity and site ambient radiation levels. Radioactivity in effluents discharged to the atmosphere from AI facilities is continuously sampled and monitored to ensure that levels released to unrestricted areas are within appropriate limits, and to identify processes which may require additional engineering safeguards to minimize radioactivity levels in such effluents. In addition, selected nonradioactive constituents in surface water discharged to unrestricted areas are determined. This report summarizes and discusses monitoring results for 1976. The results of a special soil plutonium survey performed during the year are also summarized

New development for the reverse time of flight analysis of spectra measured using Fourier Diffractometer Facilities

CERN Document Server

Maayouf, R M A

2002-01-01

The present work introduces a new design to replace the (Finnish make) reverse time of flight (RTOF) analyzer used for the Fourier diffractometer facilities. The new design applies a data acquisition system, a special interface card and software program installed in a PC computer, to perform the cross-correlation functions between signals received from the chopper-decoder and detector. It has been found from test measurements performed with the Cairo Fourier diffractometer facility (CFDF) and the similar high resolution one at JINR (Dubna-Russia) that the new design can successfully replace the Finnish make RTOF analyzer.

Planning, Coordinating, and Managing Off-Site Storage is an Area of Increasing, Professional Responsibility for Special Collections Departments

Directory of Open Access Journals (Sweden)

Melissa Goertzen

2016-03-01

Full Text Available Objective – To measure the use of off-site storage for special collections materials and to examine how this use impacts core special collections activities. Design – Survey questionnaire containing both structured and open ended questions. Follow-up interviews were also conducted. Setting – Association of Research Libraries (ARL member institutions in the United States of America. Subjects – 108 directors of special collections. Methods – Participants were recruited via email; contact information was compiled through professional directories, web searches, and referrals from professionals at ARL member libraries. The survey was sent out on October 31, 2013, and two reminder emails were distributed before it closed three weeks later. The survey was created and distributed using Qualtrics, a research software that supports online data collection and analysis. All results were analyzed using Microsoft Excel and Qualtrics. Main Results – The final response rate was 58% (63 out of 108. The majority (51 participants, or 81% reported use of off-site storage for library collections. Of this group, 91% (47 out of 51 house a variety of special collections in off-site storage. The criteria most frequently utilized to designate these materials to off-site storage are use (87%, size (66%, format (60%, and value (57%. The authors found that special collections directors are most likely to send materials to off-site storage facilities that are established and in use by other departments at their home institution; access to established workflows, especially those linked to transit and delivery, and space for expanding collections are benefits. In regard to core special collections activities, results indicated that public service was most impacted by off-site storage. The authors discussed challenges related to patron use and satisfaction. In regard to management and processing, directors faced challenges using the same level of staff to maintain

Design of a Facility to Test the Advanced Stirling Radioisotope Generator Engineering Unit

Science.gov (United States)

Lewandowski, Edward J.; Schreiber, Jeffrey G.; Oriti, Salvatore M.; Meer, David W.; Brace, Michael H.; Dugala, Gina

2009-01-01

The Advanced Stirling Radioisotope Generator (ASRG) is being considered to power deep space missions. An engineering unit, the ASRG-EU, was designed and fabricated by Lockheed Martin under contract to the Department of Energy. This unit is currently on an extended operation test at NASA Glenn Research Center to generate performance data and validate the life and reliability predictions for the generator and the Stirling convertors. A special test facility was designed and built for testing the ASRG-EU. Details of the test facility design are discussed. The facility can operate the convertors under AC bus control or with the ASRG-EU controller. It can regulate input thermal power in either a fixed temperature or fixed power mode. An enclosure circulates cooled air around the ASRG-EU to remove heat rejected from the ASRG-EU by convection. A custom monitoring and data acquisition system supports the test. Various safety features, which allow 2417 unattended operation, are discussed.

Dance Facilities.

Science.gov (United States)

Ashton, Dudley, Ed.; Irey, Charlotte, Ed.

This booklet represents an effort to assist teachers and administrators in the professional planning of dance facilities and equipment. Three chapters present the history of dance facilities, provide recommended dance facilities and equipment, and offer some adaptations of dance facilities and equipment, for elementary, secondary and college level…

Facilities inventory protection for nuclear facilities

International Nuclear Information System (INIS)

Schmitt, F.J.

1989-01-01

The fact that shut-down applications have been filed for nuclear power plants, suggests to have a scrutinizing look at the scopes of assessment and decision available to administrations and courts for the protection of facilities inventories relative to legal and constitutional requirements. The paper outlines the legal bases which need to be observed if purposeful calculation is to be ensured. Based on the different actual conditions and legal consequences, the author distinguishes between 1) the legal situation of facilities licenced already and 2) the legal situation of facilities under planning during the licencing stage. As indicated by the contents and restrictions of the pertinent provisions of the Atomic Energy Act and by the corresponding compensatory regulation, the object of the protection of facilities inventor in the legal position of the facility owner within the purview of the Atomic Energy Act, and the licensing proper. Art. 17 of the Atomic Energy Act indicates the legislators intent that, once issued, the licence will be the pivotal point for regulations aiming at protection and intervention. (orig./HSCH) [de

Special geometry

International Nuclear Information System (INIS)

Strominger, A.

1990-01-01

A special manifold is an allowed target manifold for the vector multiplets of D=4, N=2 supergravity. These manifolds are of interest for string theory because the moduli spaces of Calabi-Yau threefolds and c=9, (2,2) conformal field theories are special. Previous work has given a local, coordinate-dependent characterization of special geometry. A global description of special geometries is given herein, and their properties are studied. A special manifold M of complex dimension n is characterized by the existence of a holomorphic Sp(2n+2,R)xGL(1,C) vector bundle over M with a nowhere-vanishing holomorphic section Ω. The Kaehler potential on M is the logarithm of the Sp(2n+2,R) invariant norm of Ω. (orig.)

Research studies performed using the Cairo Fourier Diffractometer Facility

International Nuclear Information System (INIS)

Maayouf, R.M.A.; Ridikas, D.

2009-12-01

This report represents the results of the research studies performed using the Cairo Fourier Diffractometer Facility (CFDF), within 10 years after it was installed and put into operation at the beginning of 1996. The main components of the CFDF were supplied by the IAEA according to the technical assistance project EGY/1/022 'Upgrading of Research Reactor Utilization'. The present report is the second published INDC report, while the first one, published at the beginning of 1997, was about the performance of the CFDF and its main characteristic parameters. Plenty of measurements were performed since then, yielding several publications both in local and international scientific periodicals and resulting in 8 M.Sc. and Ph.D. degrees from Egyptian Universities. In addition, a new approach for the analysis of the neutron spectra was implemented using the CFDF. Specially designed interface card with proper software program was applied instead of the reverse time of flight (RTOF) and Finnish made analyzer originally attached to the facility. It has been verified that the new approach can successfully replace the RTOF analyzer, significantly decreasing the time of measurement and saving the reactor's operation time. Besides, a special fault diagnostic system program was developed and tested for caring and handling the possible failures of the CFDF. Moreover, measurements were carried out for the diffraction spectra emitted at different points of one of the samples. The latter was scanned across the neutron beam of the CFDF, for studying the stress after welding; used in industrial applications. (author)

Nuclear Safety Co-Ordination within Oak Ridge Operations Facilities

Energy Technology Data Exchange (ETDEWEB)

Johnson, W. A.; Pryor, W. A. [Research and Development Division, United States Atomic Energy Commission, Oak Ridge, TN (United States)

1966-05-15

The Oak Ridge Operations Office of the USAEC has within its jurisdiction multiple contractors and facilities for research and for the production of fissile materials for the atomic energy programme. Among these facilities are gaseous diffusion plants for the production of {sup 235}U-enriched uranium hexafluoride, plants for the fabrication of special components and fuel for research and production reactors, and laboratories for pilot plant studies and basic research in nuclear technology. One research laboratory is also actively engaged in criticality experimental programmes and has been a major contributor of criticality data for safety applications. These diversified programmes include the processing, fabrication and transport of practically all forms and isotopic enrichments of uranium in quantities commensurate with both laboratory and volume production requirements. Consequently, adequate nuclear safety control with reasonable economy for operations of this magnitude demands not only co-ordination and liaison between contractor and USAEC staffs, but a continuing reappraisal of safety applications in light of the most advanced information. This report outlines the role of the Oak Ridge Operations Office in these pursuits and describes as examples some specific problems in which this office co-ordinated actions necessary for their resolution. Other examples are given of parametric and procedural applications in plant processes and fissile shipments emphasizing the use of recent experimental or calculated data. These examples involve the use of mass and geometric variables, neutron absorbers and moderation control. Departures from limits specified in existing nuclear safety guides are made to advantage in light of new data, special equipment design, contingencies and acceptable risks. (author)

Special Education and Juvenile Justice: An Overview and Analysis of Prevention and Intervention Policy and Program Developments

Science.gov (United States)

Ohio Coalition for the Education of Children with Disabilities, 2006

2006-01-01

There is a serious overpopulation of special needs youth in Ohio's juvenile justice system. This study raises policy questions relating to gaining a deeper understanding of the reasons why there is an overpopulation of children with disabilities in youth correctional facilities and what can be done to reduce the need for future incarcerations.…

Soft x-ray scattering facility at the Advanced Light Source with real-time data processing and analysis

Science.gov (United States)

Gann, E.; Young, A. T.; Collins, B. A.; Yan, H.; Nasiatka, J.; Padmore, H. A.; Ade, H.; Hexemer, A.; Wang, C.

2012-04-01

We present the development and characterization of a dedicated resonant soft x-ray scattering facility. Capable of operation over a wide energy range, the beamline and endstation are primarily used for scattering from soft matter systems around the carbon K-edge (˜285 eV). We describe the specialized design of the instrument and characteristics of the beamline. Operational characteristics of immediate interest to users such as polarization control, degree of higher harmonic spectral contamination, and detector noise are delineated. Of special interest is the development of a higher harmonic rejection system that improves the spectral purity of the x-ray beam. Special software and a user-friendly interface have been implemented to allow real-time data processing and preliminary data analysis simultaneous with data acquisition.

Soft x-ray scattering facility at the Advanced Light Source with real-time data processing and analysis

International Nuclear Information System (INIS)

Gann, E.; Collins, B. A.; Ade, H.; Young, A. T.; Nasiatka, J.; Padmore, H. A.; Hexemer, A.; Wang, C.; Yan, H.

2012-01-01

We present the development and characterization of a dedicated resonant soft x-ray scattering facility. Capable of operation over a wide energy range, the beamline and endstation are primarily used for scattering from soft matter systems around the carbon K-edge (∼285 eV). We describe the specialized design of the instrument and characteristics of the beamline. Operational characteristics of immediate interest to users such as polarization control, degree of higher harmonic spectral contamination, and detector noise are delineated. Of special interest is the development of a higher harmonic rejection system that improves the spectral purity of the x-ray beam. Special software and a user-friendly interface have been implemented to allow real-time data processing and preliminary data analysis simultaneous with data acquisition.

Coordinated safeguards for materials management in a mixed-oxide fuel facility

International Nuclear Information System (INIS)

Shipley, J.P.; Cobb, D.D.; Dietz, R.J.; Evans, M.L.; Schelonka, E.P.; Smith, D.B.; Walton, R.B.

1977-02-01

A coordinated safeguards system is described for safeguarding strategic quantities of special nuclear materials in mixed-oxide recycle fuel fabrication facilities. The safeguards system is compatible with industrial process requirements and combines maximum effectiveness consistent with modest cost and minimal process interference. It is based on unit process accounting using a combination of conventional and state-of-the-art NDA measurement techniques. The effectiveness of the system against single and multiple thefts is evaluated using computer modeling and simulation techniques

Coordinated safeguards for materials management in a mixed-oxide fuel facility

Energy Technology Data Exchange (ETDEWEB)

Shipley, J.P.; Cobb, D.D.; Dietz, R.J.; Evans, M.L.; Schelonka, E.P.; Smith, D.B.; Walton, R.B.

1977-02-01

A coordinated safeguards system is described for safeguarding strategic quantities of special nuclear materials in mixed-oxide recycle fuel fabrication facilities. The safeguards system is compatible with industrial process requirements and combines maximum effectiveness consistent with modest cost and minimal process interference. It is based on unit process accounting using a combination of conventional and state-of-the-art NDA measurement techniques. The effectiveness of the system against single and multiple thefts is evaluated using computer modeling and simulation techniques.

High resolution electron scattering facility at the Darmstadt Linear Accelerator (DALINAC). Pt. 4

International Nuclear Information System (INIS)

Foh, J.; Frey, R.; Schneider, R.; Schuell, D.; Schwierczinski, A.; Theissen, H.; Titze, O.

1977-11-01

The computer system installed for the electron scattering facility and its usage is described. For on-line control a dedicated system of two tightly coupled computers (PDP 11/20, H116) is used wheras a PDP 11/45 is provided for all other data processing work resulting from the experiments. Special interfaces, graphic terminals, system software and a complete set of application programs have been developed. (orig.) [de

Facility location decisions with environmental considerations. A case study from the petrochemical industry

OpenAIRE

Treitl, Stefan; Jammernegg, Werner

2014-01-01

The recently growing concerns of customers and governments about environmental protection and greenhouse gas reduction have forced companies to integrate the topic of environmental sustainability into their decision making. Facility location decisions are of special relevance in this respect because of their strategic nature. Furthermore, many different trade-offs must be considered, for example between operational costs and customer service. But as soon as environmental issues are concerned,...

Seniors' experiences of living in special housing accommodation

Science.gov (United States)

Hellberg, Ingela; Augustsson, Veronica; Hellström Muhli, Ulla

2011-01-01

This article presents a hermeneutic phenomenological analysis of interview material in which 12 seniors living in Special Housing Accommodation (SHA) facilities reflect on the experience of living in such facilities. Of particular interest in the analysis is living in a SHA as a phenomenon. The finding shows that the phenomenon of lived experience in a SHA seems to be a state of ambiguity regarding one's existence, which is made up of several constituents (elements of meaning). The analysis contributes to the understanding of how the phenomenon of SHA living is coming into existence as a need, due to an individual's failing health; however, the SHA is not considered to be a true home. Accordingly, this has consequences to the subject position for the seniors in that they have to navigate between existing and not existing. The seniors learn to cope with living in the SHA by lowering their expectations of life and existence while the SHA provides the prerequisites for their existence. An implication for promoting care is to support the seniors to enable a full existence of life within SHA living. PMID:21412446

Setting up and running an advanced light microscopy and imaging facility.

Science.gov (United States)

Sánchez, Carlos; Muñoz, Ma Ángeles; Villalba, Maite; Labrador, Verónica; Díez-Guerra, F Javier

2011-07-01

During the last twenty years, interest in light microscopy and imaging techniques has grown in various fields, such as molecular and cellular biology, developmental biology, and neurobiology. In addition, the number of scientific articles and journals using these techniques is rapidly increasing. Nowadays, most research institutions require sophisticated microscopy systems to cover their investigation demands. In general, such instruments are too expensive and complex to be purchased and managed by a single laboratory or research group, so they have to be shared with other groups and supervised by specialized personnel. This is the reason why microscopy and imaging facilities are becoming so important at research institutions nowadays. In this unit, we have gathered and presented a number of issues and considerations from our own experience that we hope will be helpful when planning or setting up a new facility.

Summary: special waste form lysimeters - arid program

International Nuclear Information System (INIS)

Skaggs, R.L.; Walter, M.B.

1987-01-01

The purpose of the Special Waste Form Lysimeters - Arid Program is to determine the performance of solidified commercial low-level waste forms using a field-scale lysimeter facility constructed for measuring the release and migration of radionuclides from the waste forms. The performance of these waste forms, as measured by radionuclide concentrations in lysimeter effluent, will be compared to that predicted by laboratory characterization of the waste forms. Waste forms being tested include nuclear power reactor waste streams that have been solidified in cement, Dow polymer, and bitumen. To conduct the field leaching experiments a lysimeter facility was built to measure leachate under actual environmental conditions. Field-scale samples of waste were buried in lysimeters equipped to measure water balance components, effluent radionuclide concentrations, and to a limited extent, radionuclide concentrations in lysimeter soil samples. The waste forms are being characterized by standard laboratory leach tests to obtain estimates of radionuclide release. These estimates will be compared to leach rates observed in the field. Adsorption studies are being conducted to determine the amount of contaminant available for transport after the release. Theoretical solubility calculations will also be performed to investigate whether common solid phases could be controlling radionuclide release. 4 references, 8 figures, 1 table

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

Science.gov (United States)

2010-07-01

... mining and reclamation operations which include the operation of coal processing plants and support... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 947.827 Section 947.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT...

30 CFR 912.827 - Special performance standards-coal processing plants and support facilities not located at or...

Science.gov (United States)

2010-07-01

... mining and reclamation operations which includes the operation of coal processing plants and support... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 912.827 Section 912.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT...

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

Science.gov (United States)

2010-07-01

... mining and reclamation operations which include the operation of coal processing plants and support... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 922.827 Section 922.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT...

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

Science.gov (United States)

2010-07-01

... mining and reclamation operations which include the operation of coal processing plants and support... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 937.827 Section 937.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT...

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

Science.gov (United States)

2010-07-01

... mining and reclamation operations which includes the operation of coal processing plants and support... plants and support facilities not located at or near the minesite or not within the permit area for a mine. 910.827 Section 910.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT...

Alaska Synthetic Aperture Radar (SAR) Facility science data processing architecture

Science.gov (United States)

Hilland, Jeffrey E.; Bicknell, Thomas; Miller, Carol L.

1991-01-01

The paper describes the architecture of the Alaska SAR Facility (ASF) at Fairbanks, being developed to generate science data products for supporting research in sea ice motion, ice classification, sea-ice-ocean interaction, glacier behavior, ocean waves, and hydrological and geological study areas. Special attention is given to the individual substructures of the ASF: the Receiving Ground Station (RGS), the SAR Processor System, and the Interactive Image Analysis System. The SAR data will be linked to the RGS by the ESA ERS-1 and ERS-2, the Japanese ERS-1, and the Canadian Radarsat.

Seismic fragility of reinforced concrete structures in nuclear facilities

International Nuclear Information System (INIS)

Gergely, P.

1985-01-01

The failure and fragility analyses of reinforced concrete structures and elements in nuclear reactor facilities within the Seismic Safety Margins Research Program (SSMRP) at the Lawrence Livermore National Laboratory are evaluated. Uncertainties in material modeling, behavior of low shear walls, and seismic risk assessment for nonlinear response receive special attention. Problems with ductility-based spectral deamplification and prediction of the stiffness of reinforced concrete walls at low stress levels are examined. It is recommended to use relatively low damping values in connection with ductility-based response reductions. The study of static nonlinear force-deflection curves is advocated for better nonlinear dynamic response predictions

MC ampersand A policy issues for international inspections at DOE nuclear facilities

International Nuclear Information System (INIS)

Crawford, D.W.; Zack, N.R.

1994-01-01

Recent initiatives and executive decisions within the US have included an offer to place certain special nuclear materials from the former weapons stockpile under international safeguards inspections. The nuclear materials at issue are excess materials; other materials characterized as strategic reserve will not be subject to these international activities. Current Department of Energy requirements and procedures to account for and control these nuclear materials may need to be modified to accommodate these inspections. Safeguards issues, such as physical inventory frequency and verification requirements, may rise from the collateral safeguards activities in support of both domestic and international safeguards. This paper will discuss Office of Safeguards and Security policy and views on these international inspection activities at former nuclear weapons facilities, including implications for current domestic safeguards approaches currently implemented at these facilities

A Strategy for Quantifying Radioactive Material in a Low-Level Waste Incineration Facility

International Nuclear Information System (INIS)

Hochel, R.C.

1997-03-01

One of the methods proposed by the U.S. Department of Energy (DOE) for the volume reduction and stabilization of a variety of low-level radioactive wastes (LLW) is incineration. Many commercial incinerators are in operation treating both non-hazardous and hazardous wastes. These can obtain volume reductions factors of 50 or more for certain wastes, and produce a waste (ash) that can be easily stabilized if necessary by vitrification or cementation. However, there are few incinerators designed to accommodate radioactive wastes. One has been recently built at the Savannah River Site (SRS) near Aiken, SC and is burning non-radioactive hazardous waste and radioactive wastes in successive campaigns. The SRS Consolidated Incineration Facility (CIF) is RCRA permitted as a Low Chemical Hazard, Radiological facility as defined by DOE criteria (Ref. 1). Accordingly, the CIF must operate within specified chemical, radionuclide, and fissile material inventory limits (Ref. 2). The radionuclide and fissile material limits are unique to radiological or nuclear facilities, and require special measurement and removal strategies to assure compliance, and the CIF may be required to shut down periodically in order to clean out the radionuclide inventory which builds up in various parts of the facility

Consolidated Laser-Induced Fluorescence Diagnostic Systems for the NASA Ames Arc Jet Facilities

Science.gov (United States)

Grinstead, Jay; Wilder, Michael C.; Porter, Barry; Brown, Jeff; Yeung, Dickson; Battazzo, Steve; Brubaker, Tim

2016-01-01

The spectroscopic diagnostic technique of two photon absorption laser-induced fluorescence (TALIF) of atomic species for non-intrusive arc jet flow property measurement was first implemented at NASA Ames in the mid-1990s. Use of TALIF expanded at NASA Ames and to NASA Johnsons arc jet facility in the late 2000s. In 2013-2014, NASA combined the agency's large-scale arc jet test capabilities at NASA Ames. Concurrent with that effort, the agency also sponsored a project to establish two comprehensive LIF diagnostic systems for the Aerodynamic Heating Facility (AHF) and Interaction Heating Facility (IHF) arc jets. The scope of the project enabled further engineering development of the existing IHF LIF system as well as the complete reconstruction of the original AHF LIF system. The updated LIF systems are identical in design and capability. They represent the culmination of over 20 years of development experience in transitioning a specialized laboratory research tool into a measurement system for large-scale, high-demand test facilities. This paper documents the overall system design from measurement requirements to implementation. Representative data from the redeveloped AHF and IHF LIF systems are also presented.

Pilot-benchmarking of the WENRA safety reference levels for the spent fuel intermediate storage facility Ahaus

International Nuclear Information System (INIS)

Lorenz, Bernd; Roeder, Markus; Brandt, Klaus-Dieter

2008-01-01

Full text: The Western European Nuclear Regulator's Association (WENRA) has 2007 issued the draft of the 'Waste and Spent Fuel Storage Safety Reference Levels'. The objective of WENRA is to strive for a harmonized safety level of nuclear facilities within the European Community and these Reference Levels are a benchmark method to demonstrate the achieved level for the regulatory system and the implementation as well. Safety Reference Levels exist at the moment for Reactor Safety, Waste Storage and Decommissioning in different stages of development. ENISS, the European Nuclear Installations Safety Standards Initiative, a FORATOM based special organisation of nuclear operators, has discussed these Safety Reference Levels very intensively with WENRA and the agreement was to make a implementation benchmark-exercise for the storage facilities before the authorities finally agree on the Reference Levels. This benchmark was scheduled for the year 2008. Because of the special situation in Germany where a large number of storage facilities is in operation the German authorities felt that it would be useful to initiate a Pilot-Benchmark to get first results on the feasibility of the Reference Levels and the burden imposed to authorities and operators by these benchmark-exercises. GNS, a subsidiary company of the utilities, agreed to step into this process on a voluntary basis with its storage facility for spent fuel in Ahaus. The exercise was done in a very efficient way and in good co-operation between the authorities, local and federal, and the operator. The results in terms of safety assessments have been very satisfactory showing the high degree of safety. Although the facility was for the first time licensed already in 1987 the compliance with nearly all Reference Levels from 2007 could be demonstrated. It became also clear that newer facilities would fulfil the desired safety standard too. Nevertheless, in spite of the good results the exercise revealed some weak

Facility effluent monitoring plan determinations for the 200 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-11-01

The following facility effluent monitoring plan determinations document the evaluations conducted for the Westinghouse Hanford Company 200 Area facilities (chemical processing, waste management, 222-S Laboratory, and laundry) on the Hanford Site in south central Washington State. These evaluations determined the need for facility effluent monitoring plans for the 200 Area facilities. The facility effluent monitoring plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438 (WHC 1991). The Plutonium/Uranium Extraction Plant and UO 3 facility effluent monitoring plan determinations were prepared by Los Alamos Technical Associates, Richland, Washington. The Plutonium Finishing Plant, Transuranic Waste Storage and Assay Facility, T Plant, Tank Farms, Low Level Burial Grounds, and 222-S Laboratory determinations were prepared by Science Applications International Corporation of Richland, Washington. The B Plant Facility Effluent Monitoring Plan Determination was prepared by ERCE Environmental Services of Richland, Washington

Structures to Resist the Effects of Accidental Explosions. Volume 6. Special Considerations in Explosive Facility Design

Science.gov (United States)

1985-04-01

addition to their Inherent advantages with respect to fire protection, acoustical and thermal insulation, structural mass and resistance to flying...suspended from a monorail system. The panel is inside the shield and is not rigidly attached to the column members. Special consideration was given to...characteristic pulse emitted by an explosion to prevent actuation by other sources such as lightning, fires , etc., **ich cay occur with flash sensors. ■112

Medical and radiological aspects of emergency preparedness and response at SevRAO facilities.

Science.gov (United States)

Savkin, M N; Sneve, M K; Grachev, M I; Frolov, G P; Shinkarev, S M; Jaworska, A

2008-12-01

Regulatory cooperation between the Norwegian Radiation Protection Authority and the Federal Medical Biological Agency (FMBA) of the Russian Federation has the overall goal of promoting improvements in radiation protection in Northwest Russia. One of the projects in this programme has the objectives to review and improve the existing medical emergency preparedness capabilities at the sites for temporary storage of spent nuclear fuel and radioactive waste. These are operated by SevRAO at Andreeva Bay and in Gremikha village on the Kola Peninsula. The work is also intended to provide a better basis for regulation of emergency response and medical emergency preparedness at similar facilities elsewhere in Russia. The purpose of this paper is to present the main results of that project, implemented by the Burnasyan Federal Medical Biophysical Centre. The first task was an analysis of the regulatory requirements and the current state of preparedness for medical emergency response at the SevRAO facilities. Although Russian regulatory documents are mostly consistent with international recommendations, some distinctions lead to numerical differences in operational intervention criteria under otherwise similar conditions. Radiological threats relating to possible accidents, and related gaps in the regulation of SevRAO facilities, were also identified. As part of the project, a special exercise on emergency medical response on-site at Andreeva Bay was prepared and carried out, and recommendations were proposed after the exercise. Following fruitful dialogue among regulators, designers and operators, special regulatory guidance has been issued by FMBA to account for the specific and unusual features of the SevRAO facilities. Detailed sections relate to the prevention of accidents, and emergency preparedness and response, supplementing the basic Russian regulatory requirements. Overall it is concluded that (a) the provision of medical and sanitary components of emergency

Scientific Infrastructure To Support Manned And Unmanned Aircraft, Tethered Balloons, And Related Aerial Activities At Doe Arm Facilities On The North Slope Of Alaska

Science.gov (United States)

Ivey, M.; Dexheimer, D.; Hardesty, J.; Lucero, D. A.; Helsel, F.

2015-12-01

The U.S. Department of Energy (DOE), through its scientific user facility, the Atmospheric Radiation Measurement (ARM) facilities, provides scientific infrastructure and data to the international Arctic research community via its research sites located on the North Slope of Alaska. DOE has recently invested in improvements to facilities and infrastructure to support operations of unmanned aerial systems for science missions in the Arctic and North Slope of Alaska. A new ground facility, the Third ARM Mobile Facility, was installed at Oliktok Point Alaska in 2013. Tethered instrumented balloons were used to make measurements of clouds in the boundary layer including mixed-phase clouds. A new Special Use Airspace was granted to DOE in 2015 to support science missions in international airspace in the Arctic. Warning Area W-220 is managed by Sandia National Laboratories for DOE Office of Science/BER. W-220 was successfully used for the first time in July 2015 in conjunction with Restricted Area R-2204 and a connecting Altitude Reservation Corridor (ALTRV) to permit unmanned aircraft to operate north of Oliktok Point. Small unmanned aircraft (DataHawks) and tethered balloons were flown at Oliktok during the summer and fall of 2015. This poster will discuss how principal investigators may apply for use of these Special Use Airspaces, acquire data from the Third ARM Mobile Facility, or bring their own instrumentation for deployment at Oliktok Point, Alaska. The printed poster will include the standard DOE funding statement.

Facilities & Leadership

Data.gov (United States)

Department of Veterans Affairs — The facilities web service provides VA facility information. The VA facilities locator is a feature that is available across the enterprise, on any webpage, for the...

Facility model for the Los Alamos Plutonium Facility

International Nuclear Information System (INIS)

Coulter, C.A.; Thomas, K.E.; Sohn, C.L.; Yarbro, T.F.; Hench, K.W.

1986-01-01

The Los Alamos Plutonium Facility contains more than sixty unit processes and handles a large variety of nuclear materials, including many forms of plutonium-bearing scrap. The management of the Plutonium Facility is supporting the development of a computer model of the facility as a means of effectively integrating the large amount of information required for material control, process planning, and facility development. The model is designed to provide a flexible, easily maintainable facility description that allows the faciltiy to be represented at any desired level of detail within a single modeling framework, and to do this using a model program and data files that can be read and understood by a technically qualified person without modeling experience. These characteristics were achieved by structuring the model so that all facility data is contained in data files, formulating the model in a simulation language that provides a flexible set of data structures and permits a near-English-language syntax, and using a description for unit processes that can represent either a true unit process or a major subsection of the facility. Use of the model is illustrated by applying it to two configurations of a fictitious nuclear material processing line

Methods for developing seismic and extreme wind-hazard models for evaluating critical structures and equipment at US Department of Energy facilities and commercial plutonium facilities in the United States

International Nuclear Information System (INIS)

Coats, D.W.; Murray, R.C.; Bernreuter, D.L.

1981-01-01

Lawrence Livermore National Laboratory (LLNL) is developing seismic and wind hazard models for the US Department of Energy (DOE). The work is part of a three-phase effort to establish building design criteria developed with a uniform methodology for seismic and wind hazards at the various DOE sites throughout the United States. In Phase 1, LLNL gathered information on the sites and their critical facilities, including nuclear reactors, fuel-reprocessing plants, high-level waste storage and treatment facilities, and special nuclear material facilities. Phase 2 - development of seismic and wind hazard models - is discussed in this paper, which summarizes the methodologies used by seismic and extreme-wind experts and gives sample hazard curves for the first sites to be modeled. These hazard models express the annual probability that the site will experience an earthquake (or windspeed) greater than some specified magnitude. In the final phase, the DOE will use the hazards models and LLNL-recommended uniform design criteria to evaluate critical facilities. The methodology presented in this paper also was used for a related LLNL study - involving the seismic assessment of six commercial plutonium fabrication plants licensed by the US Nuclear Regulatory Commission (NRC). Details and results of this reassessment are documented in reference

Integrated safeguards and security for the INEL Special Isotope Separation Plant

International Nuclear Information System (INIS)

Warner, G.F.; Zack, N.R.

1990-01-01

This paper describes the development of the safeguards and security system that was to be used for the Special Isotope Separation (SIS) Production Plant. The US Department of Energy has postponed the construction of the SIS Plant that was to be built at the Idaho National Engineering Laboratory (INEL) site near Idaho Falls, Idaho. The Plant was designed to produce weapons grade plutonium from DOE owned fuel grade plutonium by converting off-spec. plutonium dioxide into metal buttons that would meet required chemical and isotopic specifications. Because this was to be a completely new facility there was a unique opportunity to provide an in-depth, ''state-of-the- art'' safeguards and security system without attempting to overlay upon an existing, older system. This facility was being designed to be in complete compliance with the new DOE Orders by integrating safeguards and security into the plant operating system and by providing graded protection to the areas of varying sensitivity within the plant

Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

International Nuclear Information System (INIS)

1978-12-01

The present decommissioning regulations contained in Sections 50.33(f) and 50.82 of 10 CFR part 50 require applicants for power reactor operating licenses to demonstrate that they can obtain the funds needed to meet both operating costs and estimated costs of shutdown and decommissioning. The development of detailed, specific decommissioning plans for nuclear power plants is not currently required until the licensee seeks to terminate his operating license. Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase the need for future decommissionings, the NRC staff began an in-depth review and reevaluation of NRC's regulatory approach to decommissioning in 1975. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. In response to comments from the public and states, and to information gained during the initial stage of execution of the plan, several modifications of the plan are now required. The revised overall report sets forth in detail the current NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

Location model of specialized terminals for soybe an exports in Brazil

Directory of Open Access Journals (Sweden)

Alessandra Fraga Dubke

2011-04-01

Full Text Available The purpose of this work is the development of a location model for specialized terminals used as transshipment points in the supply chain of soybeans. The theoretical basis of the study relies on the association of a transshipment model with a multi-commodity, multi-facility capacitated location model. The shipping ports might be seen as specialized terminals that add value to the exported products by transforming raw soy grains into soy oil and soy meal. The proposed model also considers service activities in each terminal and the capacity of the maritime ports. Using representative data from the year 2004, the model is illustrated by a small case study, which considers six points of production in inland Brazil, all served by railways, one maritime port on the north and five on the east coast, and three destination ports in Europe and Asia. The study includes a rough sensitivity analysis regarding volumes, capacities, prices, and transportation costs

Feasibility study for a transportation operations system cask maintenance facility

Energy Technology Data Exchange (ETDEWEB)

Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1991-01-01

The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a waste management program for the disposition of spent nuclear fuel (SNF) and high-level waste (HLW). The program will include a transportation system for moving the nuclear waste from the sources to a geologic repository for permanent disposal. Specially designed casks will be used to safely transport the waste. The cask systems must be operated within limits imposed by DOE, the Nuclear Regulatory Commission (NRC), and the Department of Transportation (DOT). A dedicated facility for inspecting, testing, and maintaining the cask systems was recommended by the General Accounting Office (in 1979) as the best means of assuring their operational effectiveness and safety, as well as regulatory compliance. In November of 1987, OCRWM requested a feasibility study be made of a Cask Maintenance Facility (CMF) that would perform the required functions. 46 refs., 16 figs., 13 tabs.

Feasibility study for a transportation operations system cask maintenance facility

International Nuclear Information System (INIS)

Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1991-01-01

The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a waste management program for the disposition of spent nuclear fuel (SNF) and high-level waste (HLW). The program will include a transportation system for moving the nuclear waste from the sources to a geologic repository for permanent disposal. Specially designed casks will be used to safely transport the waste. The cask systems must be operated within limits imposed by DOE, the Nuclear Regulatory Commission (NRC), and the Department of Transportation (DOT). A dedicated facility for inspecting, testing, and maintaining the cask systems was recommended by the General Accounting Office (in 1979) as the best means of assuring their operational effectiveness and safety, as well as regulatory compliance. In November of 1987, OCRWM requested a feasibility study be made of a Cask Maintenance Facility (CMF) that would perform the required functions. 46 refs., 16 figs., 13 tabs

Early test facilities and analytic methods for radiation shielding: Proceedings

International Nuclear Information System (INIS)

Ingersoll, D.T.; Ingersoll, J.K.

1992-11-01

This report represents a compilation of eight papers presented at the 1992 American Nuclear Society/European Nuclear Society International Meeting. The meeting is of special significance since it commemorates the fiftieth anniversary of the first controlled nuclear chain reaction. The papers contained in this report were presented in a special session organized by the Radiation Protection and Shielding Division in keeping with the historical theme of the meeting. The paper titles are good indicators of their content and are: (1) The origin of radiation shielding research: The Oak Ridge experience, (2) Shielding research at the hanford site, (3) Aircraft shielding experiments at General Dynamics Fort Worth, 1950-1962, (4) Where have the neutrons gone?, a history of the tower shielding facility, (5) History and evolution of buildup factors, (6) Early shielding research at Bettis atomic power laboratory, (7) UK reactor shielding: then and now, (8) A very personal view of the development of radiation shielding theory

Overview of the Defense Programs Research and Technology Development Program for fiscal year 1993. Appendix II research laboratories and facilities

Energy Technology Data Exchange (ETDEWEB)

1993-09-30

This document contains summaries of the research facilities that support the Defense Programs Research and Technology Development Program for FY 1993. The nine program elements are aggregated into three program clusters as follows: (1) Advanced materials sciences and technologies; chemistry and materials, explosives, special nuclear materials (SNM), and tritium. (2) Design sciences and advanced computation; physics, conceptual design and assessment, and computation and modeling. (3) Advanced manufacturing technologies and capabilities; system engineering science and technology, and electronics, photonics, sensors, and mechanical components. Section I gives a brief summary of 23 major defense program (DP) research and technology facilities and shows how these major facilities are organized by program elements. Section II gives a more detailed breakdown of the over 200 research and technology facilities being used at the Laboratories to support the Defense Programs mission.

Special-purpose materials for magnetically confined fusion reactors. Third annual progress report

International Nuclear Information System (INIS)

1981-11-01

The scope of Special Purpose Materials covers fusion reactor materials problems other than the first-wall and blanket structural materials, which are under the purview of the ADIP, DAFS, and PMI task groups. Components that are considered as special purpose materials include breeding materials, coolants, neutron multipliers, barriers for tritium control, materials for compression and OH coils and waveguides, graphite and SiC, heat-sink materials, ceramics, and materials for high-field (>10-T) superconducting magnets. It is recognized that there will be numerous materials problems that will arise during the design and construction of large magnetic-fusion energy devices such as the Engineering Test Facility (ETF) and Demonstration Reactor (DEMO). Most of these problems will be specific to a particular design or project and are the responsibility of the project, not the Materials and Radiation Effects Branch. Consequently, the Task Group on Special Purpose Materials has limited its concern to crucial and generic materials problems that must be resolved if magnetic-fusion devices are to succeed. Important areas specifically excluded include low-field (8-T) superconductors, fuels for hybrids, and materials for inertial-confinement devices. These areas may be added in the future when funding permits

Treatment of skin damage due to irradiation and post-irradiation skin tumours, at the Hornheide special clinic

International Nuclear Information System (INIS)

Drepper, H.

1987-01-01

A short precis of 54 years of history of the Hornheide special clinic for tumours, tuberculosis, and plastic surgery of face and skin is followed by a description of the current tasks of the clinic as an interdisciplinary center for plastic surgery and rehabilitation with facilities for tumour surgery, radiotherapy, skin and tissue pathology, and psychotherapy. Important special areas of this interdisciplinary cooperation are the treatment of skin disorders due to radiation and of tumours on irradiated skin, as well as treatment and plastic surgery after removal of tumours by irradiation in order to make the affected areas fit for renewed irradiation. (TRV) [de

Environmental Monitoring Report - United States Department of Energy, Oak Ridge Facilities, Calendar Year 1984

Energy Technology Data Exchange (ETDEWEB)

Jordan, R.G.

1999-01-01

Each year since 1972, a report has been prepared on the environmental monitoring activities for the DOE facilities in oak Ridge, Tennessee, for the previous calendar year. previously, the individual facilities published quarterly and annual progress reports that contained some environmental monitoring data. The environmental monitoring program for 1984 includes sampling and analysis of air, water from surface streams, groundwater, creek sediment, biota, and soil for both radioactive and nonradioactive (including hazardous) materials. Special environmental studies that have been conducted in the Oak Ridge area are included in this report, primarily as abstracts or brief summaries. The annual report for 1984 on environmental monitoring and surveillance of the Oak Ridge community by Oak Ridge Associated Universities (ORAU) is included as an appendix. A brief description of the topography and climate of the Oak Ridge area and a short description of the three DOE facilities are provided below to enhance the reader's understanding of the direction and contents of the environmental monitoring program for Oak Ridge.

Protection of High Ceiling Nuclear Facilities Using Photoelectric Sensors and Infrared Fire Detectors

International Nuclear Information System (INIS)

Wadoud, A.A.; El Eissawi, H.M.; Saleh, A.A.

2017-01-01

A variety of different security systems and components are commercially available and widely used. Before implementing a security system, it is important to understand the characteristics and requirements of the facility area to be protected. Technology and manufacturers of security devices are rapidly changing. It is necessary to use optimal security equipment suitable for the surrounding environment of the facility to be protected. Several security sensors can be used to protect the nuclear facilities, such as passive infrared detectors and glass breakage sensors, vibration detectors, and microwave sensors. This work introduces technical specifications, operation and method of installation for these detectors in nuclear facilities. Also a comparative study of different security sensors or equipment is provided. The photoelectric detectors and infrared fire beam smoke detectors are reliable, suitable and advanced security equipment. They can be used in special cases because of their advantages, this includes their long ranges and accuracy in performance. This paper presents a new concept for adapting the use infrared optical fire beam smoke detector as intrusion detection equipment in high ceiling buildings or towering height facilities. This is in addition to their main function, namely fire detection.The paper also provides a study for their types and installation method. Focus is made on the installation and operation method for two advanced security systems, and wireless control circuit for the overall system operation

Training development in Juzbado's Fuel Cycle Facility

International Nuclear Information System (INIS)

Perez, A.; Cunado, E.; Ortiz, D.

2003-01-01

In Juzbado's fuel cycle facility, because of the special activities developed, training is a very important issues. Training has been evolved, due to changes on the standards applicable each moment, and also due to the technological resources available. Both aspects have resulted in an evolution of the documents referred to training, such as training programs procedures, Radiation Protection Manual as well as the teaching methods. In the report we are going to present, we will show more precisely the changes that take place, referring to the different training methods used, present training sanitations, and the improvements already planned in training subjects as well as tools used, accomplishing with the legislation and improving in our effort of a better assimilation of the necessary knowledge. (Author)

Experts stress both wellness and amenity aspects of food and nutrition services in assisted living facilities for older adults.

Science.gov (United States)

Chao, Shirley Y; Dwyer, Johanna T; Houser, Robert F; Jacques, Paul; Tennstedt, Sharon

2008-10-01

There has been no consensus on best practices in food and nutrition services in assisted living facilities for older adults. We documented experts' views on optimal food and nutrition services emphases in assisted living facilities, and factors affecting their views. One hundred thirty-five national experts specializing in health, aging, nutrition and assisted living facilities completed a survey consisting four scenarios (ie, home-style, restaurant/hotel, and health/medical, and a combination of these three) in six food and nutrition services areas: dining room environment, meal services, meal quality, nutrition services, employees' qualifications, and therapeutic nutrition services. Sixty-three percent of experts favored the combination scenario. Dietetics education and experts' beliefs that assisted living facilities should be health promotion and maintenance facilities were significant predictors of emphases, including wellness considerations. Experts' personal views exerted a powerful influence. Experts chose food and nutrition service quality indicators that emphasized a focus on both wellness and amenities as their ideal scenarios for optimal food and nutrition services in assisted living facilities.

Soft x-ray scattering facility at the Advanced Light Source with real-time data processing and analysis.

Science.gov (United States)

Gann, E; Young, A T; Collins, B A; Yan, H; Nasiatka, J; Padmore, H A; Ade, H; Hexemer, A; Wang, C

2012-04-01

We present the development and characterization of a dedicated resonant soft x-ray scattering facility. Capable of operation over a wide energy range, the beamline and endstation are primarily used for scattering from soft matter systems around the carbon K-edge (∼285 eV). We describe the specialized design of the instrument and characteristics of the beamline. Operational characteristics of immediate interest to users such as polarization control, degree of higher harmonic spectral contamination, and detector noise are delineated. Of special interest is the development of a higher harmonic rejection system that improves the spectral purity of the x-ray beam. Special software and a user-friendly interface have been implemented to allow real-time data processing and preliminary data analysis simultaneous with data acquisition. © 2012 American Institute of Physics

More co-morbid depression in patients with Type 2 diabetes with multiple complications. An observational study at a specialized outpatient clinic

NARCIS (Netherlands)

van Steenbergen-Weijenburg, K.M.; van Puffelen, A.L.; Horn, E.K.; v.d. Nuyen, J.; van Dam, P.S.; van Benthem, T.B.; Beekman, A.T.F.; Rutten, F.F.H.; Hakkaart-van Roijen, L.; van der Feltz-Cornelis, C.

2011-01-01

Aims: The impact of depression on patients with chronic medical illnesses such as diabetes is well documented. Depression is relatively common in diabetes patients with diabetes-related complications and they are more likely to be referred to specialized outpatient facilities. Only a few studies

Technical and economic assessment for asbestos abatement within Facility 20470, Wright-Patterson Air Force Base, Ohio

International Nuclear Information System (INIS)

Gibson, S.M.; Ogle, R.B.

1988-03-01

This report presents the results of a technical and economic assessment of available alternatives for asbestos abatement within Facility 20470 at the Wright-Patterson Air Force Base in Dayton, Ohio. Each alternative was screened on the basis of technical feasibility, environmental impact, economics, and fulfillment of the IRP goals. Four alternatives for study are: establishing a special operations and maintenance program; enclosure; encapsulation with sealants; and removal, disposal, and replacement. Each of these alternatives was assessed for capability to control the release of asbestos fibers within Facility 20470. Alternatives 1 and 4 were determined to be acceptable, while Alternatives 2 and 3 were found to be unacceptable. 2 refs., 6 figs

Project of Particular intervention plan of the Belleville-sur-Loire NPP. Special provisions of the ORSEC plan

International Nuclear Information System (INIS)

2015-01-01

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the project of Particular intervention plan for the Belleville-sur-Loire Nuclear Power Plant (Cher, France)

Animal facilities

International Nuclear Information System (INIS)

Fritz, T.E.; Angerman, J.M.; Keenan, W.G.; Linsley, J.G.; Poole, C.M.; Sallese, A.; Simkins, R.C.; Tolle, D.

1981-01-01

The animal facilities in the Division are described. They consist of kennels, animal rooms, service areas, and technical areas (examining rooms, operating rooms, pathology labs, x-ray rooms, and 60 Co exposure facilities). The computer support facility is also described. The advent of the Conversational Monitor System at Argonne has launched a new effort to set up conversational computing and graphics software for users. The existing LS-11 data acquisition systems have been further enhanced and expanded. The divisional radiation facilities include a number of gamma, neutron, and x-ray radiation sources with accompanying areas for related equipment. There are five 60 Co irradiation facilities; a research reactor, Janus, is a source for fission-spectrum neutrons; two other neutron sources in the Chicago area are also available to the staff for cell biology studies. The electron microscope facilities are also described

Facilities Performance Indicators Report 2013-14: Tracking Your Facilities Vital Signs

Science.gov (United States)

APPA: Association of Higher Education Facilities Officers, 2015

2015-01-01

This paper features an expanded Web-based "Facilities Performance Indicators (FPI) Report." The purpose of APPA: Association of Higher Education Facilities Officers (APPA's) Facilities Performance Indicators is to provide a representative set of statistics about facilities in educational institutions. "The Facilities Performance…

Calculation of MUF for the Pyro-processing Facility

Energy Technology Data Exchange (ETDEWEB)

Jeong, Yon Hong; Kim, Woo Jin; Han, Jae Jun; Chang, Sun Young; Hwang, Yong Soo

2016-05-15

The IAEA safeguards system is divided into DIQ (Design Information Questionnaire), nuclear material accountancy, and additional measure such as C/S (Containment and Surveillance). As the detailed requirements for judging the diversion of nuclear materials, the IAEA suggests SQ (Significant Quantity) about SNM (Special Nuclear Materials), such as U and Pu, and the timeliness goal of detection about the diversion of nuclear materials. To operate facilities, it is required to accomplish these goals. In particular, in the case of the treatment facilities of spent nuclear fuel that has a high Pu content, it is very important to meet the requirements to judge the diversion of nuclear materials. However, given that item counting is impossible in bulk facilities, MUF (Material Unaccounted For) occurs inevitably in the process of nuclear material accountancy. Therefore, to meet the requirements, it is necessary to make evaluation in advance. To reduce such a MUF, the effects on a total MUF were analyzed. As a result, the error arising in a particular process such as U/TRU ingot and Porous Pellets was significant. Therefore, it is necessary to reduce measurement error in the process. MUF is one of requirements to judge the diversion of nuclear materials, and the requirement should be met. Nevertheless, it is required to come up with additional measures to prevent the exclusive use and reduce MUF, such as containment, surveillance, or multi-channel based processing design.

Device Assembly Facility (DAF) Glovebox Radioactive Waste Characterization

International Nuclear Information System (INIS)

Dominick, J L

2001-01-01

The Device Assembly Facility (DAF) at the Nevada Test Site (NTS) provides programmatic support to the Joint Actinide Shock Physics Experimental Research (JASPER) Facility in the form of target assembly. The target assembly activities are performed in a glovebox at DAF and include Special Nuclear Material (SNM). Currently, only activities with transuranic SNM are anticipated. Preliminary discussions with facility personnel indicate that primarily two distributions of SNM will be used: Weapons Grade Plutonium (WG-Pu), and Pu-238 enhanced WG-Pu. Nominal radionuclide distributions for the two material types are included in attachment 1. Wastes generated inside glove boxes is expected to be Transuranic (TRU) Waste which will eventually be disposed of at the Waste Isolation Pilot Plant (WIPP). Wastes generated in the Radioactive Material Area (RMA), outside of the glove box is presumed to be low level waste (LLW) which is destined for disposal at the NTS. The process knowledge quantification methods identified herein may be applied to waste generated anywhere within or around the DAF and possibly JASPER as long as the fundamental waste stream boundaries are adhered to as outlined below. The method is suitable for quantification of waste which can be directly surveyed with the Blue Alpha meter or swiped. An additional quantification methodology which requires the use of a high resolution gamma spectroscopy unit is also included and relies on the predetermined radionuclide distribution and utilizes scaling to measured nuclides for quantification

Specialization Patterns

OpenAIRE

Schultz , Ulrik Pagh; Lawall , Julia ,; Consel , Charles

1999-01-01

Design patterns offer numerous advantages for software development, but can introduce inefficiency into the finished program. Program specialization can eliminate such overheads, but is most effective when targeted by the user to specific bottlenecks. Consequently, we propose to consider program specialization and design patterns as complementary concepts. On the one hand, program specialization can optimize object-oriented programs written using design patterns. On the other hand, design pat...

State Environmental Policy Act (SEPA) Checklist for the 105-DR Large Sodium Fire Facility Closure Plan

Energy Technology Data Exchange (ETDEWEB)

1990-09-01

The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950's and is located in the 100-D Area of the Hanford Site. The building housed the DR defense reactor, which was shut down in 1964. The LSFF is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Clean closure is the proposed method of closure for the LSFF. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989). This closure plan presents a description of the facility, the history of wastes managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected.

Communication grounding facility

International Nuclear Information System (INIS)

Lee, Gye Seong

1998-06-01

It is about communication grounding facility, which is made up twelve chapters. It includes general grounding with purpose, materials thermal insulating material, construction of grounding, super strength grounding method, grounding facility with grounding way and building of insulating, switched grounding with No. 1A and LCR, grounding facility of transmission line, wireless facility grounding, grounding facility in wireless base station, grounding of power facility, grounding low-tenton interior power wire, communication facility of railroad, install of arrester in apartment and house, install of arrester on introduction and earth conductivity and measurement with introduction and grounding resistance.

Construction and operational experiences of engineered barrier test facility for near surface disposal of LILW

International Nuclear Information System (INIS)

Park, Jin Beak; Park, Se Moon; Kim, Chang Lak

2003-01-01

Engineered barrier test facility is specially designed to demonstrate the performance of engineered barrier system for the near-surface disposal facility under the domestic environmental conditions. Comprehensive measurement systems are installed within each test cell. Long-and short-term monitoring of the multi-layered cover system can be implemented according to different rainfall scenarios with artificial rainfall system. Monitoring data on the water content, temperature, matric potential, lateral drainage and percolation of cover-layer system can be systematically managed by automatic data acquisition system. The periodic measurement data are collected and will be analyzed by a dedicated database management system, and provide a basis for performance verification of the disposal cover design

Control of the radiation environment and the worker in high-energy facilities

International Nuclear Information System (INIS)

Stevenson, G.R.

1993-01-01

The philosophy behind the prediction, measurement, monitoring and limitation by access control of the radiation hazard in high-energy accelerator facilities is compared with that which could be employed for controlling similar hazards due to cosmic radiation in civil aircraft flights. Special mention is made of computer simulations of the radiation environment as a means of predicting necessary control measures, of the reliability and integration of radiation measuring devices into control procedures and of the relevance of different access control procedures. (author)

Special software for computing the special functions of wave catastrophes

Directory of Open Access Journals (Sweden)

Andrey S. Kryukovsky

2015-01-01

Full Text Available The method of ordinary differential equations in the context of calculating the special functions of wave catastrophes is considered. Complementary numerical methods and algorithms are described. The paper shows approaches to accelerate such calculations using capabilities of modern computing systems. Methods for calculating the special functions of wave catastrophes are considered in the framework of parallel computing and distributed systems. The paper covers the development process of special software for calculating of special functions, questions of portability, extensibility and interoperability.

Comparison and discussion of two types of threat (Hazard) categorization method for nuclear facilities

International Nuclear Information System (INIS)

Tang, Rongyao; Xu, Xiaoxiao; Zhang, Jiangang; Zhao, Bin

2008-01-01

The emergency threat categorization method suggested by international atomic energy agency (IAEA) and hazard categorization standard by the Department of Energy of United States (USDOE) for nuclear facilities are compared and discussed in this paper. The research shows the two types of categorization method for nuclear facility are similar, though each has its own speciality. The categorization method suggested by IAEA is quite completed and sound in scientific basis. The thresholds of radioactive material are connected with the quantity of dangerous source, and the latest radiobiological effect research results are taken in setting the thresholds. While the main purpose is put on emergency management, some of the categorization criteria do not fit for safety surveillance of nuclear facilities. The categorization method of DOE is advanced in its operability, and it fits for safety surveillance. The disadvantage is that the thresholds of radioactive material need to be updated because the parameters used in calculation is outdated, and also the threshold of category 3 is somewhat disputable for many reasons. We should take advantage of both methods and adjust the standards according to the application purpose while establishing the categorization standard of nuclear facilities in China. (author)

Power Burst Facility Severe Fuel Damage test series

International Nuclear Information System (INIS)

Buescher, B.J.; Osetek, D.J.; Ploger, S.A.

1982-01-01

The Severe Fuel Damage (SFD) tests planned for the Power Burst Facility (PBF) are described. Bundles containing 32 zircaloy-clad, PWR-type fuel rods will be subjected to severe overheating transients in a high-pressure, superheated-steam environment. Cladding temperatures are expected to reach 2400 0 K, resulting in cladding ballooning and rupture, severe cladding oxidation, cladding melting, fuel dissolution, fuel rod fragmentation, and possibly, rubble bed formation. An experiment effluent collection system is being installed and the PBF fission product monitoring system is being upgraded to meet the special requirements of the SFD tests. Scoping calculations were performed to evaluate performance of the SFD test design and to establish operational requirements for the PBF loop

Facility effluent monitoring plan for the 327 Facility

International Nuclear Information System (INIS)

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

Proceedings of the ninth annual DOE low-level waste management forum: executive summary, technical and special session summaries, attendees

International Nuclear Information System (INIS)

Anon.

1988-01-01

This first volume of proceedings contains summaries of each of six technical sessions as well as three special sessions held during the conference. The six technical sessions were: Disposal technology and facility development (15 papers); Institutional and regulatory issues (10); Performance assessment (14); Waste characterization and verification (7); Site closure and stabilization (6); and Waste treatment (8). The three special sessions were: 1) Review of criteria for guidance on alternative disposal technology; 2) Hazardous waste regulatory update; and 3) Challenges to meeting the 1993 deadline. All papers have been indexed for inclusion on the Energy Data Base

Use of the National Low-Temperature Neutron Irradiation Facility (NLTNIF) for fusion materials research

International Nuclear Information System (INIS)

Coltman, R.R. Jr.; Kerchner, H.R.; Klabunde, C.E.

1986-01-01

In May 1983 the Division of Materials Sciences, Office of Basic Energy Sciences of the Department of Energy authorized the establishment of a National Low-Temperature Neutron Irradiation Facility (NLTNIF) at ORNL's Bulk Shielding Reactor (BSR). The NLTNIF, which will be available for qualified experiments at no cost to users, will provide a combination of high radiation intensities and special environmental and testing conditions that have not been previously available in the US. Since the DOE authorization, work has proceeded on the design and construction of the new facility without interruption. This report describes the present status of the development of NLTNIF and, for the information of new candidate users, a recounting of the major specifications and capabilities is also given

Revealed access to haemodialysis facilities in northeastern Iran: Factors that matter in rural and urban areas.

Science.gov (United States)

Kiani, Behzad; Bagheri, Nasser; Tara, Ahmad; Hoseini, Benyamin; Tabesh, Hamed; Tara, Mahmood

2017-11-07

Poor access to haemodialysis facilities is associated with high mortality and morbidity rates. This study investigated factors affecting revealed access to the haemodialysis facilities considering patients living in rural and urban areas without any haemodialysis facility (Group A) and those living urban areas with haemodialysis facilities (Group B). This study is based on selfreported Actual Access Time (AAT) to referred haemodialysis facilities and other information regarding travel to haemodialysis facilities from patients. All significant variables on univariate analysis were entered into a univariate general linear model in order to identify factors associated with AAT. Both spatial (driving time and distance) and non-spatial factors (sex, income level, caregivers, transportation mode, education level, ethnicity and personal vehicle ownership) influenced the revealed access identified in Group A. The non-spatial factors for Group B patients were the same as for Group A, but no spatial factor was identified in Group B. It was found that accessibility is strongly underestimated when driving time is chosen as accessibility measure to haemodialysis facilities. Analysis of revealed access determinants provides policymakers with an appropriate decision base for making appropriate decisions and finding solutions to decrease the access time for patients under haemodialysis therapy. Driving time alone is not a good proxy for measuring access to haemodialysis facilities as there are many other potential obstacles, such as women's special travel problems, poor other transportation possibilities, ethnicity disparities, low education levels, low caregiver status and low-income.

Opinions of the well-informed persons about the nuclear reactor facility periodical inspection

International Nuclear Information System (INIS)

Aeba, Yoichi; Ishikawa, Michio; Enomoto, Toshiaki; Oomori, Katsuyoshi

2005-01-01

Falsifications of self-inspection records in the shrouds and of leakage rates for containment vessels at TEPCO nuclear power plants destroyed public trust in nuclear safety. The Nuclear Reactor Regulation Law and Electric Utility Law were amended to enhance the nuclear safety regulation system. The major improvements are that operators are legally required to conduct inspection (periodical operator inspection) and recording and keeping inspection results. The operator performs 'periodical operator inspection' regularly, and Nuclear and Industrial Safety Agency (NISA) performs periodical inspection' about particularly important facilities/function in safety. Sixteen opinions of well-informed persons about the nuclear reactor facility periodical inspection were presented in this special number. Interval of periodical inspection less than thirteen months was disputed. Maintenance activities should be more rationalized based on risk information. (T. Tanaka)

Korean clinical practice guidelines for preventing the transmission of infections in hemodialysis facilities

Directory of Open Access Journals (Sweden)

Hayne Cho Park

2018-03-01

Full Text Available Patients receiving hemodialysis are vulnerable to infectious diseases due to their impaired immunity and high risk of exposure to pathogens. To protect patients, staff, and visitors from potential infections, each hemodialysis unit should establish and follow standard infection control and prevention measures. Therefore, clinical practice guidelines were developed by a working group of nephrologists and infection control specialists to provide evidence-based guidance for dialysis physicians and nurses, with the aim of preventing infection transmission and controlling infection sources in hemodialysis facilities. The areas of infection control covered by these guidelines include standard precautions, isolation strategies, vascular access, water treatment, cleaning/disinfecting/sterilizing, and vaccination. This special report summarizes the key recommendations from the Korean clinical practice guidelines for preventing the transmission of infections in hemodialysis facilities.

Use of Savannah River Site facilities for blend down of highly enriched uranium

International Nuclear Information System (INIS)

Bickford, W.E.; McKibben, J.M.

1994-02-01

Westinghouse Savannah River Company was asked to assess the use of existing Savannah River Site (SRS) facilities for the conversion of highly enriched uranium (HEU) to low enriched uranium (LEU). The purpose was to eliminate the weapons potential for such material. Blending HEU with existing supplies of depleted uranium (DU) would produce material with less than 5% U-235 content for use in commercial nuclear reactors. The request indicated that as much as 500 to 1,000 MT of HEU would be available for conversion over a 20-year period. Existing facilities at the SRS are capable of producing LEU in the form of uranium trioxide (UO 3 ) powder, uranyl nitrate [UO 2 (NO 3 ) 2 ] solution, or metal. Additional processing, and additional facilities, would be required to convert the LEU to uranium dioxide (UO 2 ) or uranium hexafluoride (UF 3 ), the normal inputs for commercial fuel fabrication. This study's scope does not include the cost for new conversion facilities. However, the low estimated cost per kilogram of blending HEU to LEU in SRS facilities indicates that even with fees for any additional conversion to UO 2 or UF 6 , blend-down would still provide a product significantly below the spot market price for LEU from traditional enrichment services. The body of the report develops a number of possible facility/process combinations for SRS. The primary conclusion of this study is that SRS has facilities available that are capable of satisfying the goals of a national program to blend HEU to below 5% U-235. This preliminary assessment concludes that several facility/process options appear cost-effective. Finally, SRS is a secure DOE site with all requisite security and safeguard programs, personnel skills, nuclear criticality safety controls, accountability programs, and supporting infrastructure to handle large quantities of special nuclear materials (SNM)

Brazing of special metallic materials and material combinations using a special material

International Nuclear Information System (INIS)

Lison, R.

1981-01-01

The special materials include metals of groups IVa, Va and VIa of the periodic tables and their alloys. Their particular properties have won them applications in many highly specialized industries. For these materials to be used, mastery of thermal joining methods appropriate to their characteristics is necessary. High-temperature brazing is one such method for joining special materials. This paper presents variants of this technique suitable for each individual special material. Compatibility tests between various brazing metals and various special materials have been carried out by simulating the temperature/time cycle involved in brazing procedures. Special materials are relatively expensive, and their special properties are not required at every point in a structure: elsewhere they can be replaced by a different special material or by other metals or alloys. This means that joints must be made between two special materials or between a special material and a conventional material. When certain conditions are fulfilled, such joins can be made by high-temperature brazing. This paper also shows the extent to which the geometry of the join determines the choice of process. Example of applications are also given. (orig.)

A laser heating facility for energy-dispersive X-ray absorption spectroscopy

DEFF Research Database (Denmark)

Kantor, Innokenty; Marini, C.; Mathon, O.

2018-01-01

A double-sided laser heating setup for diamond anvil cells installed on the ID24 beamline of the ESRF is presented here. The setup geometry is specially adopted for the needs of energy-dispersive X-ray absorption spectroscopic (XAS) studies of materials under extreme pressure and temperature...... conditions. We illustrate the performance of the facility with a study on metallic nickel at 60 GPa. The XAS data provide the temperature of the melting onset and quantitative information on the structural parameters of the first coordination shell in the hot solid up to melting....

Status of CHESS facility and research programs: 2010

Energy Technology Data Exchange (ETDEWEB)

Fontes, Ernest, E-mail: ef11@cornell.edu [Cornell High Energy Synchrotron Source, Cornell University, Ithaca, NY 14853 (United States); Bilderback, Donald H.; Gruner, Sol M. [Cornell High Energy Synchrotron Source, Cornell University, Ithaca, NY 14853 (United States)

2011-09-01

CHESS is a hard X-ray synchrotron radiation national facility located at Cornell University and funded by the National Science Foundation. It is open to all scientists by peer-reviewed proposal and serves 500-1000 visitors each year. The CHESS scientific and technical staff develops forefront research tools and X-ray instrumentation and methods and supports 12 experimental stations delivering high intensity X-ray beams produced at 5.3 GeV and 250 mA. The facility consists of a mix of dedicated and flexible experimental stations that are easily configured for general X-ray diffraction (wide- and small-angle), spectroscopy, imaging applications, etc. Dedicated stations support high-pressure powder X-ray diffraction, pulsed-laser deposition for layer-by-layer growth of surfaces, and three dedicated stations for protein crystallography. Specialized resource groups at the laboratory include: an X-ray detector group; MacCHESS, an NIH-supported research resource for protein crystallography; the G-line division, which primarily organizes graduate students and Cornell faculty members around three X-ray stations; a high-pressure diamond-anvil cell support laboratory; and a monocapillary drawing facility for making microbeam X-ray optics. Research is also ongoing to upgrade CHESS to a first-ever 5 GeV, 100 mA Energy Recovery Linac (ERL) hard X-ray source. This source will provide ultra-high spectral-brightness and <100 fs short-pulse capability at levels well in advance of those possible with existing storage rings. It will produce diffraction-limited X-rays beams of up to 10 keV energy and be capable of providing 1 nm round beams. Prototyping for this facility is under way now to demonstrate critical DC photoelectron injector and superconducting linac technologies needed for the full-scale ERL.

Status of CHESS facility and research programs: 2010

International Nuclear Information System (INIS)

Fontes, Ernest; Bilderback, Donald H.; Gruner, Sol M.

2011-01-01

CHESS is a hard X-ray synchrotron radiation national facility located at Cornell University and funded by the National Science Foundation. It is open to all scientists by peer-reviewed proposal and serves 500-1000 visitors each year. The CHESS scientific and technical staff develops forefront research tools and X-ray instrumentation and methods and supports 12 experimental stations delivering high intensity X-ray beams produced at 5.3 GeV and 250 mA. The facility consists of a mix of dedicated and flexible experimental stations that are easily configured for general X-ray diffraction (wide- and small-angle), spectroscopy, imaging applications, etc. Dedicated stations support high-pressure powder X-ray diffraction, pulsed-laser deposition for layer-by-layer growth of surfaces, and three dedicated stations for protein crystallography. Specialized resource groups at the laboratory include: an X-ray detector group; MacCHESS, an NIH-supported research resource for protein crystallography; the G-line division, which primarily organizes graduate students and Cornell faculty members around three X-ray stations; a high-pressure diamond-anvil cell support laboratory; and a monocapillary drawing facility for making microbeam X-ray optics. Research is also ongoing to upgrade CHESS to a first-ever 5 GeV, 100 mA Energy Recovery Linac (ERL) hard X-ray source. This source will provide ultra-high spectral-brightness and <100 fs short-pulse capability at levels well in advance of those possible with existing storage rings. It will produce diffraction-limited X-rays beams of up to 10 keV energy and be capable of providing 1 nm round beams. Prototyping for this facility is under way now to demonstrate critical DC photoelectron injector and superconducting linac technologies needed for the full-scale ERL.

Algorithmically specialized parallel computers

CERN Document Server

Snyder, Lawrence; Gannon, Dennis B

1985-01-01

Algorithmically Specialized Parallel Computers focuses on the concept and characteristics of an algorithmically specialized computer.This book discusses the algorithmically specialized computers, algorithmic specialization using VLSI, and innovative architectures. The architectures and algorithms for digital signal, speech, and image processing and specialized architectures for numerical computations are also elaborated. Other topics include the model for analyzing generalized inter-processor, pipelined architecture for search tree maintenance, and specialized computer organization for raster

The EOS studies on Luch facility

International Nuclear Information System (INIS)

Bel'kov, S.A.; Voronich, I.N.; Garanin, S.G.; Derkach, V.N.; Kochemasov, G.G.; Litvin, D.N.; Sukharev, S.A.

2010-01-01

Complete text of publication follows. The results of the investigations in the shock compressibility of materials on the 'Luch' facility are presented. The experiments have been performed with impedance mismatch technique applying. The output non-uniformity of the shocks achieved < 10 ps and inaccuracy of their velocity measuring < 3%. The pressures to 30 Mbars were developed in lead and till 50 Mbars with applying of the special-constructed targets for hydrodynamic pressure increasing. Results on the materials shock compressibility have been obtained that accord well with the test results shown on hydrodynamic stands. The work was performed in part under the sponsorship of the RFFI (grants No. 09-02-12157-ofi-m and No. 09-02-97089-r povolzh'ye-a), and grant of the President of the RF to leading scientific schools No. 65192.2010.2.

Air Quality Facilities

Data.gov (United States)

Iowa State University GIS Support and Research Facility — Facilities with operating permits for Title V of the Federal Clean Air Act, as well as facilities required to submit an air emissions inventory, and other facilities...

Facilities Performance Indicators Report, 2004-05. Facilities Core Data Survey

Science.gov (United States)

Glazner, Steve, Ed.

2006-01-01

The purpose of "Facilities Performance Indicators" is to provide a representative set of statistics about facilities in educational institutions. The second iteration of the web-based Facilities Core Data Survey was posted and available to facilities professionals at more than 3,000 institutions in the Fall of 2005. The website offered a printed…

Specialized languages

DEFF Research Database (Denmark)

Mousten, Birthe; Laursen, Anne Lise

2016-01-01

Across different fields of research, one feature is often overlooked: the use of language for specialized purposes (LSP) as a cross-discipline. Mastering cross-disciplinarity is the precondition for communicating detailed results within any field. Researchers in specialized languages work cross...... science fields communicate their findings. With this article, we want to create awareness of the work in this special area of language studies and of the inherent cross-disciplinarity that makes LSP special compared to common-core language. An acknowledgement of the importance of this field both in terms...... of more empirical studies and in terms of a greater application of the results would give language specialists in trade and industry a solid and updated basis for communication and language use....

High-risk facilities. Emergency management in nuclear, chemical and hazardous waste facilities

International Nuclear Information System (INIS)

Kloepfer, Michael

2012-01-01

The book on emergency management in high-risk facilities covers the following topics: Change in the nuclear policy, risk management of high-risk facilities as a constitutional problem - emergency management in nuclear facilities, operational mechanisms of risk control in nuclear facilities, regulatory surveillance responsibilities for nuclear facilities, operational mechanism of the risk control in chemical plants, regulatory surveillance responsibilities for chemical facilities, operational mechanisms of the risk control in hazardous waste facilities, regulatory surveillance responsibilities for hazardous waste facilities, civil law consequences in case of accidents in high-risk facilities, criminal prosecution in case of accidents in high-risk facilities, safety margins as site risk for emission protection facilities, national emergency management - strategic emergency management structures, warning and self-protection of the public in case of CBRN hazards including aspects of the psych-social emergency management.

25 years of Pelletron Linac facility

International Nuclear Information System (INIS)

Shrivastava, A.; Palit, R.

2014-01-01

The DAE-BRNS International Symposium on Nuclear Physics was held in BARC during 2nd to 6th December 2013. A summary of the highlights of this symposium has recently appeared in Physics News. As a part of the symposium, a special session was held to commemorate 25 years of operation of the Mumbai Pelletron Linac Facility (PLF). PLF, being operated jointly by Bhabha Atomic Research Centre and Tata Institute of Fundamental Research, has been a major centre for heavy-ion accelerator based research in India. The Pelletron accelerator was formally inaugurated on 30th December 1988, and marked an important milestone in nuclear physics research in India. The facility was augmented with the indigenously developed superconducting LINAC booster to enhance the energy of the accelerated beams. The LINAC booster was commissioned in a phased manner and the entire facility was dedicated to the users on the 28th November 2007. The LINAC booster consists of seven liquid helium cryostat modules, each housing four lead coated (2 μm) copper quarter wave resonators (QWR). The cavities are designed to operate at 150 MHz with an optimum acceptance at a velocity corresponding to β=0.1. The performance of the QWRs is found to be excellent with an average energy gain of 0.4 MV/q per cavity corresponding to 80% of the design value. Beam transmission from the entry to the exit of the LINAC was found to be 80% and the beam timing (FWHM) of 600 ps was measured at the target position. Development of the superconducting LINAC is a major milestone in the accelerator technology in our country. Most of the critical components of the LINAC booster, the first superconducting heavy-ion accelerator in India, have been designed, developed and fabricated indigenously

Arctic Atmospheric Measurements Using Manned and Unmanned Aircraft, Tethered Balloons, and Ground-Based Systems at U.S. DOE ARM Facilities on the North Slope Of Alaska

Science.gov (United States)

Ivey, M.; Dexheimer, D.; Roesler, E. L.; Hillman, B. R.; Hardesty, J. O.

2016-12-01

The U.S. Department of Energy (DOE) provides scientific infrastructure and data to the international Arctic research community via research sites located on the North Slope of Alaska and an open data archive maintained by the ARM program. In 2016, DOE continued investments in improvements to facilities and infrastructure at Oliktok Point Alaska to support operations of ground-based facilities and unmanned aerial systems for science missions in the Arctic. The Third ARM Mobile Facility, AMF3, now deployed at Oliktok Point, was further expanded in 2016. Tethered instrumented balloons were used at Oliktok to make measurements of clouds in the boundary layer including mixed-phase clouds and to compare measurements with those from the ground and from unmanned aircraft operating in the airspace above AMF3. The ARM facility at Oliktok Point includes Special Use Airspace. A Restricted Area, R-2204, is located at Oliktok Point. Roughly 4 miles in diameter, it facilitates operations of tethered balloons and unmanned aircraft. R-2204 and a new Warning Area north of Oliktok, W-220, are managed by Sandia National Laboratories for DOE Office of Science/BER. These Special Use Airspaces have been successfully used to launch and operate unmanned aircraft over the Arctic Ocean and in international airspace north of Oliktok Point.A steady progression towards routine operations of unmanned aircraft and tethered balloon systems continues at Oliktok. Small unmanned aircraft (DataHawks) and tethered balloons were successfully flown at Oliktok starting in June of 2016. This poster will discuss how principal investigators may apply for use of these Special Use Airspaces, acquire data from the Third ARM Mobile Facility, or bring their own instrumentation for deployment at Oliktok Point, Alaska.

Introduction to the Special Issue: Coastal GIS

Directory of Open Access Journals (Sweden)

Timothy Nyerges

2014-09-01

Full Text Available This special issue of the ISPRS International Journal of Geographic Information about “Coastal GIS” is motivated by many circumstances. More than one-half of the world’s human population lives in coastal areas (within 200 kilometers of coast as of 2000 [1]. The trend toward coastal habitation is expected to continue in the US with the total being 75 percent by 2025, meaning that coastal human–environment interactions will likely increase and intensify [2]. Geographic information systems (GIS are being developed and used by technical specialists, stakeholder publics, and executive/policy decision makers for improving our understanding and management of coastal areas, separately and together as more organizations focus on improving the sustainability and resilience of coastal systems. Coastal systems—defined as the area of land closely connected to the sea, including barrier islands, wetlands, mudflats, beaches, estuaries, cities, towns, recreational areas, and maritime facilities, the continental seas and shelves, and the overlying atmosphere—are subject to complex and dynamic interactions among natural and human-driven processes. Coastal systems are crucial to regional and national economies, hosting valued human-built infrastructure and providing ecosystem services that sustain human well-being. This special issue of IJGI about coastal GIS presents a collection of nine papers that address many of the issues mentioned above. [...

Nuclear facilities

International Nuclear Information System (INIS)

Anon.

2000-01-01

Here is given the decree (2000-1065) of the 25. of October 2000 reporting the publication of the convention between the Government of the French Republic and the CERN concerning the safety of the LHC (Large Hadron Collider) and the SPS (Proton Supersynchrotron) facilities, signed in Geneva on July 11, 2000. By this convention, the CERN undertakes to ensure the safety of the LHC and SPS facilities and those of the operations of the LEP decommissioning. The French legislation and regulations on basic nuclear facilities (concerning more particularly the protection against ionizing radiations, the protection of the environment and the safety of facilities) and those which could be decided later on apply to the LHC, SPS and auxiliary facilities. (O.M.)

Facility effluent monitoring plan for 242-A Evaporator facility

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.

1993-03-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility effluent Monitoring Plans, WHC-EP-0438-1**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

North Slope, Alaska ESI: FACILITY (Facility Points)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains data for oil field facilities for the North Slope of Alaska. Vector points in this data set represent oil field facility locations. This data...

Tritium transport around nuclear facilities