Proposed environmental remediation at Argonne National Laboratory, Argonne, Illinois

International Nuclear Information System (INIS)

1997-05-01

The Department of Energy (DOE) has prepared an Environmental Assessment evaluating proposed environmental remediation activity at Argonne National Laboratory-East (ANL-E), Argonne, Illinois. The environmental remediation work would (1) reduce, eliminate, or prevent the release of contaminants from a number of Resource Conservation and Recovery Act (RCRA) Solid Waste Management Units (SWMUs) and two radiologically contaminated sites located in areas contiguous with SWMUs, and (2) decrease the potential for exposure of the public, ANL-E employees, and wildlife to such contaminants. The actions proposed for SWMUs are required to comply with the RCRA corrective action process and corrective action requirements of the Illinois Environmental Protection Agency; the actions proposed are also required to reduce the potential for continued contaminant release. Based on the analysis in the EA, the DOE has determined that the proposed action does not constitute a major federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, the preparation of an Environmental Impact Statement is not required

Argonne Wakefield Accelerator Update '92

International Nuclear Information System (INIS)

Rosing, M.; Balka, L.; Chojnacki, E.; Gai, W.; Ho, C.; Konecny, R.; Power, J.; Schoessow, P.; Simpson, J.

1992-01-01

The Argonne Wakefield Accelerator (AWA) is an experiment designed to test various ideas related to wakefield technology. Construction is now underway for a 100 nC electron beam in December of 1992. This report updates this progress

Science | Argonne National Laboratory

Science.gov (United States)

Security Photon Sciences Physical Sciences & Engineering Energy Frontier Research Centers Scientific Publications Researchers Postdocs Exascale Computing Institute for Molecular Engineering at Argonne Work with Us About Safety News Careers Education Community Diversity Directory Argonne National Laboratory

Argonne Chemical Sciences & Engineering - Awards Home

Science.gov (United States)

Argonne National Laboratory Chemical Sciences & Engineering DOE Logo CSE Home About CSE Argonne Home > Chemical Sciences & Engineering > Fundamental Interactions Catalysis & Energy Computational Postdoctoral Fellowships Contact Us CSE Intranet Awards Argonne's Chemical Sciences and

Tiger team assessment of the Argonne Illinois site

International Nuclear Information System (INIS)

1990-01-01

This report documents the results of the Department of Energy's (DOE) Tiger Team Assessment of the Argonne Illinois Site (AIS) (including the DOE Chicago Operations Office, DOE Argonne Area Office, Argonne National Laboratory-East, and New Brunswick Laboratory) and Site A and Plot M, Argonne, Illinois, conducted from September 17 through October 19, 1990. The Tiger Team Assessment was conducted by a team comprised of professionals from DOE, contractors, consultants. The purpose of the assessment was to provide the Secretary of Energy with the status of Environment, Safety, and Health (ES ampersand H) Programs at AIS. Argonne National Laboratory-East (ANL-E) is the principal tenant at AIS. ANL-E is a multiprogram laboratory operated by the University of Chicago for DOE. The mission of ANL-E is to perform basic and applied research that supports the development of energy-related technologies. There are a significant number of ES ampersand H findings and concerns identified in the report that require prompt management attention. A significant change in culture is required before ANL-E can attain consistent and verifiable compliance with statutes, regulations and DOE Orders. ES ampersand H activities are informal, fragmented, and inconsistently implemented. Communication is seriously lacking, both vertically and horizontally. Management expectations are not known or commondated adequately, support is not consistent, and oversight is not effective

Tiger team assessment of the Argonne Illinois site

Energy Technology Data Exchange (ETDEWEB)

1990-10-19

This report documents the results of the Department of Energy's (DOE) Tiger Team Assessment of the Argonne Illinois Site (AIS) (including the DOE Chicago Operations Office, DOE Argonne Area Office, Argonne National Laboratory-East, and New Brunswick Laboratory) and Site A and Plot M, Argonne, Illinois, conducted from September 17 through October 19, 1990. The Tiger Team Assessment was conducted by a team comprised of professionals from DOE, contractors, consultants. The purpose of the assessment was to provide the Secretary of Energy with the status of Environment, Safety, and Health (ES H) Programs at AIS. Argonne National Laboratory-East (ANL-E) is the principal tenant at AIS. ANL-E is a multiprogram laboratory operated by the University of Chicago for DOE. The mission of ANL-E is to perform basic and applied research that supports the development of energy-related technologies. There are a significant number of ES H findings and concerns identified in the report that require prompt management attention. A significant change in culture is required before ANL-E can attain consistent and verifiable compliance with statutes, regulations and DOE Orders. ES H activities are informal, fragmented, and inconsistently implemented. Communication is seriously lacking, both vertically and horizontally. Management expectations are not known or commondated adequately, support is not consistent, and oversight is not effective.

Argonne Liquid-Metal Advanced Burner Reactor : components and in-vessel system thermal-hydraulic research and testing experience - pathway forward.

Energy Technology Data Exchange (ETDEWEB)

Kasza, K.; Grandy, C.; Chang, Y.; Khalil, H.; Nuclear Engineering Division

2007-06-30

This white paper provides an overview and status report of the thermal-hydraulic nuclear research and development, both experimental and computational, conducted predominantly at Argonne National Laboratory. Argonne from the early 1970s through the early 1990s was the Department of Energy's (DOE's) lead lab for thermal-hydraulic development of Liquid Metal Reactors (LMRs). During the 1970s and into the mid-1980s, Argonne conducted thermal-hydraulic studies and experiments on individual reactor components supporting the Experimental Breeder Reactor-II (EBR-II), Fast Flux Test Facility (FFTF), and the Clinch River Breeder Reactor (CRBR). From the mid-1980s and into the early 1990s, Argonne conducted studies on phenomena related to forced- and natural-convection thermal buoyancy in complete in-vessel models of the General Electric (GE) Prototype Reactor Inherently Safe Module (PRISM) and Rockwell International (RI) Sodium Advanced Fast Reactor (SAFR). These two reactor initiatives involved Argonne working closely with U.S. industry and DOE. This paper describes the very important impact of thermal hydraulics dominated by thermal buoyancy forces on reactor global operation and on the behavior/performance of individual components during postulated off-normal accident events with low flow. Utilizing Argonne's LMR expertise and design knowledge is vital to the further development of safe, reliable, and high-performance LMRs. Argonne believes there remains an important need for continued research and development on thermal-hydraulic design in support of DOE's and the international community's renewed thrust for developing and demonstrating the Global Nuclear Energy Partnership (GNEP) reactor(s) and the associated Argonne Liquid Metal-Advanced Burner Reactor (LM-ABR). This white paper highlights that further understanding is needed regarding reactor design under coolant low-flow events. These safety-related events are associated with the transition

Argonne Physics Division Colloquium

Science.gov (United States)

[Argonne Logo] [DOE Logo] Physics Division Home News Division Information Contact PHY Org Chart Physics Division Colloquium Auditorium, Building 203, Argonne National Laboratory Fridays at 11:00 AM 2017 : Sereres Johnston 15 Sep 2017 Joint Physics and Materials Science Colloquium J. C. Séamus Davis, Cornell

Argonne National Laboratory-East summary site environmental report for calendar year 2002

International Nuclear Information System (INIS)

Golchert, N.W.; Kolzow, R.G.

2004-01-01

Argonne performs research and development in many areas of science and technology. General fields of research at Argonne include, but are not limited to, biosciences, biotechnology, chemical engineering, chemistry, decision and information sciences, energy systems and technology, high energy physics, materials science, math and computer science, nuclear reactors, physics, and environmental science. Argonne is not, and never has been, a weapons laboratory. Several missions provide focus for Argonne scientists. Basic research helps better understand the world, and applied research helps protect and improve it. For example, the prairies of Argonne provide sites for environmental studies that provide valuable information about invader species and the food webs within ecosystems. Argonne also operates world-class research facilities, such as the Advanced Photon Source (APS), which is a national research facility funded by the U.S. Department of Energy (DOE). Scientists use high brilliance X-rays from the APS for basic and applied research in many fields. Argonne also seeks to ensure our energy future. Currently, scientists and engineers are developing cleaner and more efficient energy sources, such as fuel cells and advanced electric power generation. Argonne has spent much of its history on developing nuclear reactor technology. That research is now being applied to American and Soviet nuclear reactors to improve the safety and life of the reactors. Other Argonne research seeks to improve the way we manage our environment. For example, Argonne scientists created a new catalyst that could help carmakers eliminate 95 percent of nitrogen-oxide emitted by diesel engines by the year 2007. Research and development solutions such as these will help protect our ecosystems

Argonne-West facility requirements for a radioactive waste treatment demonstration

International Nuclear Information System (INIS)

Dwight, C.C.; Felicione, F.S.; Black, D.B.; Kelso, R.B.; McClellan, G.C.

1995-01-01

At Argonne National Laboratory-West (ANL-W), near Idaho Falls, Idaho, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used and/or modified to meet the environmental and waste management research needs of DOE. One example is the use of an Argonne-West facility to conduct a radioactive waste treatment demonstration through a cooperative project with Science Applications International Corporation (SAIC) and Lockheed Idaho Technologies Company. The Plasma Hearth Process (PBP) project will utilize commercially-adapted plasma arc technology to demonstrate treatment of actual mixed waste. The demonstration on radioactive waste will be conducted at Argonne's Transient Reactor Test Facility (TREAT). Utilization of an existing facility for a new and different application presents a unique set of issues in meeting applicable federal state, and local requirements as well as the additional constraints imposed by DOE Orders and ANL-W site requirements. This paper briefly describes the PHP radioactive demonstrations relevant to the interfaces with the TREAT facility. Safety, environmental design, and operational considerations pertinent to the PHP radioactive demonstration are specifically addressed herein. The personnel equipment, and facility interfaces associated with a radioactive waste treatment demonstration are an important aspect of the demonstration effort. Areas requiring significant effort in preparation for the PBP Project being conducted at the TREAT facility include confinement design, waste handling features, and sampling and analysis considerations. Information about the facility in which a radioactive demonstration will be conducted, specifically Argonne's TREAT facility in the case of PHP, may be of interest to other organizations involved in developing and demonstrating technologies for mixed waste treatment

Argonne National Laboratory Research Highlights 1988

International Nuclear Information System (INIS)

Anon.

1988-01-01

The research and development highlights are summarized. The world's brightest source of X-rays could revolutionize materials research. Test of a prototype insertion device, a key in achieving brilliant X-ray beams, have given the first glimpse of the machine's power. Superconductivity research focuses on the new materials' structure, economics and applications. Other physical science programs advance knowledge of material structures and properties, nuclear physics, molecular structure, and the chemistry and structure of coal. New programming approaches make advanced computers more useful. Innovative approaches to fighting cancer are being developed. More experiments confirm the passive safety of Argonne's Integral Fast Reactor concept. Device simplifies nuclear-waste processing. Advanced fuel cell could provide better mileage, more power than internal combustion engine. New instruments find leaks in underground pipe, measure sodium impurities in molten liquids, detect flaws in ceramics. New antibody findings may explain ability to fight many diseases. Cadmium in cigarettes linked to bone loss in women. Programs fight deforestation in Nepal. New technology could reduce acid rain, mitigate greenhouse effect, enhance oil recovery. Innovative approaches transfer Argonne-developed technology to private industry. Each year Argonne educational programs reach some 1200 students

2016 Annual Report - Argonne Leadership Computing Facility

Energy Technology Data Exchange (ETDEWEB)

Collins, Jim [Argonne National Lab. (ANL), Argonne, IL (United States); Papka, Michael E. [Argonne National Lab. (ANL), Argonne, IL (United States); Cerny, Beth A. [Argonne National Lab. (ANL), Argonne, IL (United States); Coffey, Richard M. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-01-01

The Argonne Leadership Computing Facility (ALCF) helps researchers solve some of the world’s largest and most complex problems, while also advancing the nation’s efforts to develop future exascale computing systems. This report presents some of the ALCF’s notable achievements in key strategic areas over the past year.

'Experience with decommissioning of research and test reactors at Argonne National Laboratory'

International Nuclear Information System (INIS)

Bhattacharyya, S.K.; Yule, T.J.; Fellhauer, C.R.; Boing, L.E.

2002-01-01

A large number of research reactors around the world have reached the end of their useful operational life. Many of these are kept in a controlled storage mode awaiting decontamination and decommissioning (D and D). At Argonne National Laboratory located near Chicago in the United States of America, significant experience has been gained in the D and D of research and test reactors. These experiences span the entire range of activities in D and D - from planning and characterization of the facilities to the eventual disposition of all waste. A multifaceted D nd D program has been in progress at the Argonne National Laboratory - East site for nearly a decade. The program consists of three elements: - D and D of nuclear facilities on the site that have reached the end of their useful life; - Development and demonstrations of technologies that help in safe and cost effective D and D; - Presentation of training courses in D and D practices. Nuclear reactor facilities have been constructed and operated at the ANL-E site since the earliest days of nuclear power. As a result, a number of these early reactors reached end-of-life long before reactors on other sites and were ready for D and D earlier. They presented an excellent set of test beds on which D and D practices and technologies could be demonstrated in environments that were similar to commercial reactors, but considerably less hazardous. As shown, four reactor facilities, plutonium contaminated glove boxes and hot cells, a cyclotron facility and assorted other nuclear related facilities have been decommissioned in this program. The overall cost of the program has been modest relative to the cost of comparable projects undertaken both in the U.S. and abroad. The safety record throughout the program was excellent. Complementing the actual operations, a set of D and D technologies are being developed. These include robotic methods of tool handling and operation, chemical and laser decontamination techniques, sensors

Argonne National Laboratory 1983-1984

International Nuclear Information System (INIS)

1984-01-01

This publication presents significant developments at Argonne National Laboratory during 1983-84. Argonne is a multidisciplinary research center with primary focus on nuclear energy, basic research, biomedical-environmental studies and alternate energy research. The laboratory is operated by the University of Chicago for the Department of Energy

Argonne Tandem Linac Accelerator System (ATLAS)

Data.gov (United States)

Federal Laboratory Consortium — ATLAS is a national user facility at Argonne National Laboratory in Argonne, Illinois. The ATLAS facility is a leading facility for nuclear structure research in the...

Women in Energy: Rinku Gupta - Argonne Today

Science.gov (United States)

-performance clusters and supercomputers. What is the best part of your job? The best part is working with Argonne Today Argonne Today Mission People Work/Life Connections Focal Point Women in Energy: Rinku Gupta Home People Women in Energy: Rinku Gupta Women in Energy: Rinku Gupta Apr 1, 2016 | Posted by Argonne

Characterization of mixed CH-TRU waste at Argonne-West

International Nuclear Information System (INIS)

Dwight, C.C.; Guay, K.P.; Courtney, J.C.; Higgins, P.J.

1993-01-01

Argonne National Laboratory is participating in the Department of Energy's Waste Isolation Pilot Plant (WIPP) Experimental Test Program by characterizing and repackaging mixed contact-handled transuranic waste. Argonne's initial activities in the Program were described last year at Waste Management '92. Since then, additional waste has been characterized and repackaged, resulting in six bins ready for shipment to WIPP upon the initiation of the bin tests. Lessons learned from these operations are being factored in the design and installation of a new characterization facility, the Enhanced Waste Characterization Facility (EWCF). The objectives of the WIPP Experimental Test Program have also undergone change since last year leading to an accelerated effort to factor sludge sampling capability into the EWCF. Consequently, the initiation of non-sludge operations in the waste characterization chamber has been delayed to Summer 1993 while the sludge sampling modifications are incorporated into the facility. Benefits in operational flexibility, effectiveness, and efficiency and reductions in potential facility and personnel contamination and exposure are expected from the enhanced waste characterization facility within the Hot Fuel Examination Facility at Argonne-West. This paper summarizes results and lessons learned from recent characterization and repackaging efforts and future plans for characterization. It also describes design features and status of the EWCF

Argonne National Laboratory: Laboratory Directed Research and Development FY 1993 program activities. Annual report

Energy Technology Data Exchange (ETDEWEB)

None

1993-12-23

The purposes of Argonne`s Laboratory Directed Research and Development (LDRD) Program are to encourage the development of novel concepts, enhance the Laboratory`s R&D capabilities, and further the development of its strategic initiatives. Projects are selected from proposals for creative and innovative R&D studies which are not yet eligible for timely support through normal programmatic channels. Among the aims of the projects supported by the Program are establishment of engineering ``proof-of-principle`` assessment of design feasibility for prospective facilities; development of an instrumental prototype, method, or system; or discovery in fundamental science. Several of these projects are closely associated with major strategic thrusts of the Laboratory as described in Argonne`s Five Year Institutional Plan, although the scientific implications of the achieved results extend well beyond Laboratory plans and objectives. The projects supported by the Program are distributed across the major programmatic areas at Argonne as indicated in the Laboratory LDRD Plan for FY 1993.

Site characteristics of Argonne National Laboratory in Illinois

International Nuclear Information System (INIS)

Chang, Y.W.

1995-01-01

This report reviews the geology and topography of the Argonne National Laboratory, near Lemont, Illinois. It describes the thickness and stratigraphy of soils, glacial till, and bedrock in and adjacent to the laboratory and support facilities. Seismic surveys were also conducted through the area to help determine the values of seismic wave velocities in the glacial till which is important in determining the seismic hazard of the area. Borehole log descriptions are summarized along with information on area topography

Argonne National Laboratory institutional plan FY 2002 - FY 2007

International Nuclear Information System (INIS)

Beggs, S. D.

2001-01-01

The national laboratory system provides a unique resource for addressing the national needs inherent in the mission of the Department of Energy. Argonne, which grew out of Enrico Fermi's pioneering work on the development of nuclear power, was the first national laboratory and, in many ways, has set the standard for those that followed. As the Laboratory's new director, I am pleased to present the Argonne National Laboratory Institutional Plan for FY 2002 through FY 2007 on behalf of the extraordinary group of scientists, engineers, technicians, administrators, and others who re responsible for the Laboratory's distinguished record of achievement. Like our sister DOE laboratories, Argonne uses a multifaceted approach to advance U.S. R and D priorities. First, we assemble interdisciplinary teams of scientists and engineers to address complex problems. For example, our initiative in Functional Genomics will bring together biologists, computer scientists, environmental scientists, and staff of the Advanced Photon Source to develop complete maps of cellular function. Second, we cultivate specific core competencies in science and technology; this Institutional Plan discusses the many ways in which our core competencies support DOE's four mission areas. Third, we serve the scientific community by designing, building, and operating world-class user facilities, such as the Advanced Photon Source, the Intense Pulsed Neutron Source, and the Argonne Tandem-Linac Accelerator System. This Plan summarizes the visions, missions, and strategic plans for the Laboratory's existing major user facilities, and it explains our approach to the planned Rare Isotope Accelerator. Fourth, we help develop the next generation of scientists and engineers through educational programs, many of which involve bright young people in research. This Plan summarizes our vision, objectives, and strategies in the education area, and it gives statistics on student and faculty participation. Finally, we

Was Argonne whistleblower really blowing smoke?

International Nuclear Information System (INIS)

Marshall, E.

1992-01-01

Tension between scientists and lawyers is on the rise at one federal lab as a result of a recent Department of Energy (DOE) investigation of staffers at the Argonne National Laboratory near Chicago. In the past, DOE Tiger Teams have clashed with lab personnel over enforcement of safety and health codes. Now the battle is joined on the definition of good and bad science. Officials at DOE headquarters in Washington, DC say that scientific dissent was being suppressed at Argonne. Argonne's director Alan Schriesheim vehemently disagrees. The case that brought these issues to the fore last week involves a whistleblower named James Smith, a former assistant engineer at the Argonne National Laboratory's western branch near Idaho Falls, Idaho. Specifically, he charged that a consultant and staffers had used inaccurate data on the metallurgy and thermochemistry of fuel being designed for an experimental breeder reactor. Smith also claimed the errors might endanger public safety

An update on Argonne's AWA

International Nuclear Information System (INIS)

Rosing, M.; Chojnacki, E.; Gai, W.; Ho, C.; Konecny, R.; Mtingwa, S.; Norem, J.; Schoessow, P.; Simpson, J.

1991-01-01

The Argonne Wakefield Accelerator (AWA) is a new research facility which will possess unprecedented research capabilities for the study of wakefields and related areas requiring short, intense electron bunches. The AWA is designed to produce 100 nC, 14 ps (full width) electron bunches at rep rates up to 30 Hz. Phase-1 of the AWA, now under construction, will provide these pulses at 20 MeV for various experiments. Current designs, related research and development, and construction status are presented in this general overview and project update. 6 refs., 4 figs

Radiation-induced DNA damage and repair: Argonne National Laboratory symposium, Argonne, Illinois 60439, 15 April, 1988. Symposium report

Energy Technology Data Exchange (ETDEWEB)

Peak, M J; Peak, J G; Blazek, E R

1988-10-01

The Argonne National Laboratory Symposium brought together 109 scientists from five countries to discuss the molecular effects of radiation on DNA and the responses of cells to radiation exposure. Six speakers covered three general areas: (1) DNA damages caused by radiations; (2) repair of these damages in prokaryotes and eukaryotes; and (3) aminothiols as radioprotectors. In addition, a round table discussion chaired by J. Ward dealt with alkaline and neutral elution methodology.

Weerts to lead Physical Sciences and Engineering directorate | Argonne

Science.gov (United States)

Physical Sciences and Engineering directorate By Lynn Tefft Hoff * August 10, 2015 Tweet EmailPrint Hendrik Engineering (PSE) directorate at the U.S. Department of Energy's Argonne National Laboratory. Weerts has , chemistry, materials science and nanotechnology. Weerts joined Argonne in 2005 as director of Argonne's High

Batteries and Energy Storage | Argonne National Laboratory

Science.gov (United States)

Skip to main content Argonne National Laboratory Toggle Navigation Toggle Search Energy Batteries Security User Facilities Science Work with Us Energy Batteries and Energy Storage Energy Systems Modeling Transportation SPOTLIGHT Batteries and Energy Storage Argonne's all- encompassing battery research program spans

Argonne's atlas control system upgrade

International Nuclear Information System (INIS)

Munson, F.; Quock, D.; Chapin, B.; Figueroa, J.

1999-01-01

The ATLAS facility (Argonne Tandem-Linac Accelerator System) is located at the Argonne National Laboratory. The facility is a tool used in nuclear and atomic physics research, which focuses primarily on heavy-ion physics. The accelerator as well as its control system are evolutionary in nature, and consequently, continue to advance. In 1998 the most recent project to upgrade the ATLAS control system was completed. This paper briefly reviews the upgrade, and summarizes the configuration and features of the resulting control system

Argonne Chemical Sciences & Engineering - Center for Electrical Energy

Science.gov (United States)

Laboratory Chemical Sciences & Engineering DOE Logo CSE Home About CSE Research Facilities People Publications Awards News & Highlights Events Search Argonne ... Search Argonne Home > Chemical Sciences & Engineering > Fundamental Interactions Catalysis & Energy Conversion Electrochemical

Present and future radioactive nuclear beam developments at Argonne

International Nuclear Information System (INIS)

Decrock, P.

1996-01-01

A scheme for building an ISOL-based radioactive nuclear beam facility at the Argonne Physics Division, is currently evaluated. The feasibility and efficiency of the different steps in the proposed production- and acceleration cycles are being tested. At the Dynamitron Facility of the ANL Physics Division, stripping yields of Kr, Xe and Ph beams in a windowless gas cell have been measured and the study of fission of 238 U induced by fast neutrons from the 9 Be(dn) reaction is in progress. Different aspects of the post-acceleration procedure are currently being investigated. In parallel with this work, energetic radioactive beams such as 17 F, 18 F and 56 Ni have recently been developed at Argonne using the present ATLAS facility

Environmental monitoring at Argonne National Laboratory. Annual report for 1978

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Sedlet, J.

1979-03-01

The results of the environmental monitoring program at Argonne National Laboratory for 1978 are presented and discussed. To evaluate the effect of Argonne operations on the environment, measurements were made for a variety of radionuclides in air, surface water, Argonne effluent water, soil, grass, bottom sediment, and foodstuffs; for a variety of chemical constituents in air, surface water, and Argonne effluent water; and of the environmental penetrating radiation dose. Sample collections and measurements were made at the site boundary and off the Argonne site for comparison purposes. Some on-site measurements wee made to aid in the interpretation of the boundary and off-site data. The results of the program are interpreted in terms of the sources and origin of the radioactive and chemical substances (natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. The potential radiation dose to off-site population groups is also estimated

Environmental monitoring at Argonne National Laboratory. Annual report for 1976

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Sedlet, J.

1977-03-01

The results of the environmental monitoring program at Argonne National Laboratory for 1976 are presented and discussed. To evaluate the effect of Argonne operations on the environment, measurements were made for a variety of radionuclides in air, surface water, Argonne effluent water, soil, grass, bottom sediment, and foodstuffs; for a variety of chemical constituents in surface and Argonne effluent water; and of the environmental penetrating radiation dose. Sample collections and measurements were made at the site boundary and off the Argonne site for comparison purposes. Some on-site measurements were made to aid in the interpretation of the boundary and off-site data. The results of the program are interpreted in terms of the sources and origin of the radioactive and chemical substances (natural, fallout, Argonne, and other) and are compared with accepted environmental quality standards. The potential radiation dose to off-site population groups is also estimated

Computing, Environment and Life Sciences | Argonne National Laboratory

Science.gov (United States)

Computing, Environment and Life Sciences Research Divisions BIOBiosciences CPSComputational Science DSLData Argonne Leadership Computing Facility Biosciences Division Environmental Science Division Mathematics and Computer Science Division Facilities and Institutes Argonne Leadership Computing Facility News Events About

1986 annual site environmental report for Argonne National Laboratory

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.

1987-03-01

The results of the environmental monitoring program at Argonne National Laboratory (ANL) for 1986 are presented and discussed. To evaluate the effect of Argonne operations on the environment, measurements were made for a variety of radionuclides in air, surface water, ground water, soil, grass, bottom sediment, and milk; of the environmental penetrating radiation dose; and for a variety of chemical constituents in surface water, ground water, and Argonne effluent water. Sample collections and measurements were made on the site, at the site boundary, and off the Argonne site for comparison purposes. The results of the program are interpreted in terms of the sources and origin of the radioactive and chemical substances (natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology based on recent International Commission on Radiological Protection (ICRP) recommendations is required and used in this report. The radiation dose to off-site population groups is estimated. The average concentrations and total amounts of radioactive and chemical pollutants released by Argonne to the environment were all below appropriate standards. 21 refs., 7 figs., 52 tabs

Environmental monitoring at Argonne National Laboratory. Annual report, 1981

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Sedlet, J.

1982-03-01

The results of the environmental monitoring program at Argonne National Laboratory for 1981 are presented and discussed. To evaluate the effect of Argonne operations on the environment, measurements were made for a variety of radionuclides in air, surface water, soil, grass, bottom sediment, and milk; for a variety of chemical constituents in air, surface water, and Argonne effluent water; and of the environmental penetrating radiation dose. Sample collections and measurements were made at the site boundary and off the Argonne site for comparison purposes. Some on-site measurements were made to aid in the interpretation of the boundary and off-site data. The results of the program are interpreted in terms of the sources and origin of the radioactive and chemical substances (natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. The potential radiation dose to off-site population groups is also estimated

Post-test analysis of lithium-ion battery materials at Argonne National Laboratory

Science.gov (United States)

Bareno, Javier; Dietz-Rago, Nancy; Bloom, Ira

2014-03-01

Electrochemical performance is often limited by surface and interfacial reactions at the electrodes. However, routine handling of samples can alter the very surfaces that are the object of study. Our approach combines standardized testing of batteries with sample harvesting under inert atmosphere conditions. Cells of different formats are disassembled inside an Argon glove box with controlled water and oxygen concentrations below 2 ppm. Cell components are characterized in situ, guaranteeing that observed changes in physicochemical state are due to electrochemical operation, rather than sample manipulation. We employ a complementary set of spectroscopic, microscopic, electrochemical and metallographic characterization to obtain a complete picture of cell degradation mechanisms. The resulting information about observed degradation mechanisms is provided to materials developers, both academic and industrial, to suggest new strategies and speed up the Research & Development cycle of Li-ion and related technologies. This talk will describe Argonne's post-test analysis laboratory, with an emphasis on capabilities and opportunities for collaboration. Cell disassembly, sample harvesting procedures and recent results will be discussed. This work was performed under the auspices of the U.S. Department of Energy, Office of Vehicle Technologies, Hybrid and Electric Systems, under Contract No. DE-AC02-06CH11357.

Environmental monitoring at Argonne National Laboratory. Annual report for 1982

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Sedlet, J.

1983-03-01

The results of the environmental monitoring program at Argonne Ntaional Laboratory for 1982 are presented and discussed. To evaluate the effect of Argonne operations on the environment, measurements were made for a variety of radionuclides in air, surface water, soil, grass, bottom sediment, and milk; for a variety of chemical constituents in air, surface water, ground water, and Argonne effluent water; and of the environmental penetrating radiation dose. Sample collections and masurements were made at the site boundary and off the Argonne site for comparison purposes. Some on-site measurements were made to aid in the interpretation of the boundary and off-site data. The results of the program are interpreted in terms of the sources and origin of the radioactive and chemical substances (natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. The potential radiation dose to off-site population groups is also estimated

Environmental monitoring at Argonne National Laboratory. Annual report for 1980

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Sedlet, J.

1981-03-01

The results of the environmental monitoring program at Argonne National Laboratory for 1980 are presented and discussed. To evaluate the effect of Argonne operations on the environment, measurements were made for a variety of radionuclides in air, surface water, soil, grass, bottom sediment, and foodstuffs; for a variety of chemical constituents in air, surface water, and Argonne effluent water; and of the environmental penetrating radiation dose. Sample collections and measurements were made at the site boundary and off the Argonne site for comparison purposes. Some on-site measurements were made to aid in the interpretation of the boundary and off-site data. The results of the program are interpreted in terms of the sources and origin of the radioactive and chemical substances (natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. The potential radiation dose to off-site population groups is also estimated

Environmental monitoring at Argonne National Laboratory. Annual report for 1979

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Sedlet, J.

1980-03-01

The results of the environmental monitoring program at Argonne National Laboratory for 1979 are presented and discussed. To evaluate the effect of Argonne operations on the environment, measurements were made for a variety of radionuclides in air, surface water, Argonne effluent water, soil, grass, bottom sediment, and foodstuffs; for a variety of chemical constituents in air, surface water, and Argonne effluent water; and of the environemetal penetrating radiation dose. Sample collections and measurements were made at the site boundary and off the Argonne site for comparison purposes. Some on-site measuremenets were made to aid in the interpretation of the boundary and off-site data. The results of the program are interpreted in terms of the sources and origin of the radioactive and chemical substances and are compared with applicable environmental quality standards. The potential radiation dose to off-site population groups is also estimated

Environment | Argonne National Laboratory

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Environmental monitoring at Argonne National Laboratory. Annual report for 1983

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Sedlet, J.

1984-03-01

The results of the environmental monitoring program at Argonne National Laboratory for 1983 are presented and discussed. To evaluate the effect of Argonne operations on the environment, measurements were made for a variety of radionuclides in air, surface water, soil, grass, bottom sediment, and milk; for a variety of chemical constituents in air, surface water, ground water, and Argonne effluent water; and of the environmental penetrating radiation dose. Sample collections and measurements were made at the site boundary and off the Argonne site for comparison purposes. Some on-site measurements were made to aid in the interpretation of the boundary and off-site data. The potential radiation dose to off-site population groups is also estimated. The results of the program are interpreted in terms of the sources and origin of the radioactive and chemical substances (natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. 19 references, 8 figures, 49 tables

Argonne National Laboratory Site Environmental report for calendar year 2009.

Energy Technology Data Exchange (ETDEWEB)

Golchert, N. W.; Davis, T. M.; Moos, L. P.

2010-08-04

This report discusses the status and the accomplishments of the environmental protection program at Argonne National Laboratory for calendar year 2009. The status of Argonne environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with the progress of environmental corrective actions and restoration projects. To evaluate the effects of Argonne operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the Argonne site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and Argonne effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, Argonne, and other) and are compared with applicable environmental quality standards. A U.S. Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection recommendations and the U.S. Environmental Protection Agency's (EPA) CAP-88 Version 3 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report.

Argonne National Laboratory Site Environmental Report for Calendar Year 2013

Energy Technology Data Exchange (ETDEWEB)

Davis, T. M. [Argonne National Lab. (ANL), Argonne, IL (United States); Gomez, J. L. [Argonne National Lab. (ANL), Argonne, IL (United States); Moos, L. P. [Argonne National Lab. (ANL), Argonne, IL (United States)

2014-09-02

This report discusses the status and the accomplishments of the environmental protection program at Argonne National Laboratory for calendar year 2013. The status of Argonne environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with environmental management, sustainability efforts, environmental corrective actions, and habitat restoration. To evaluate the effects of Argonne operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the Argonne site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and Argonne effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, Argonne, and other) and are compared with applicable standards intended to protect human health and the environment. A U.S. Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the U.S. Environmental Protection Agency’s (EPA) CAP-88 Version 3 computer code, was used in preparing this report.

Argonne National Laboratory site environmental report for calendar year 2007.

Energy Technology Data Exchange (ETDEWEB)

Golchert, N. W.; Davis, T. M.; Moos, L. P.; ESH/QA Oversight

2008-09-09

This report discusses the status and the accomplishments of the environmental protection program at Argonne National Laboratory for calendar year 2007. The status of Argonne environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with the progress of environmental corrective actions and restoration projects. To evaluate the effects of Argonne operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the Argonne site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and Argonne effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. A U.S. Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the U.S. Environmental Protection Agency's CAP-88 Version 3 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report.

Argonne National Laboratory site enviromental report for calendar year 2008.

Energy Technology Data Exchange (ETDEWEB)

Golchert, N. W.; Davis, T. M.; Moos, L. P.

2009-09-02

This report discusses the status and the accomplishments of the environmental protection program at Argonne National Laboratory for calendar year 2008. The status of Argonne environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with the progress of environmental corrective actions and restoration projects. To evaluate the effects of Argonne operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the Argonne site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and Argonne effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. A U.S. Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the U.S. Environmental Protection Agency's CAP-88 Version 3 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report.

Argonne National Laboratory site environmental report for calendar year 2006.

Energy Technology Data Exchange (ETDEWEB)

Golchert, N. W.; ESH/QA Oversight

2007-09-13

This report discusses the status and the accomplishments of the environmental protection program at Argonne National Laboratory for calendar year 2006. The status of Argonne environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with the progress of environmental corrective actions and restoration projects. To evaluate the effects of Argonne operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the Argonne site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and Argonne effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. A U.S. Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the U.S. Environmental Protection Agency's CAP-88 Version 3 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report.

Production-scale LLW and RMW solidification system operational testing at Argonne National Laboratory-East (ANL-E)

International Nuclear Information System (INIS)

Wescott, J.; Wagh, A.; Singh, D.; Nelson, R.; No, H.

1997-01-01

Argonne National Laboratory-East (ANL-E) has begun production-scale testing of a low-level waste and radioactive mixed waste solidification system. This system will be used to treat low-level and mixed radioactive waste to meet land burial requirements. The system can use any of several types of solidification media, including a chemically bonded phosphate ceramic developed by ANL-E scientists. The final waste product will consist of a solidified mass in a standard 208-liter drum. The system uses commercial equipment and incorporates several unique process control features to ensure proper treatment. This paper will discuss the waste types requiring treatment, the system configuration, and operation results for these waste streams

Argonne Laboratory Computing Resource Center - FY2004 Report.

Energy Technology Data Exchange (ETDEWEB)

Bair, R.

2005-04-14

In the spring of 2002, Argonne National Laboratory founded the Laboratory Computing Resource Center, and in April 2003 LCRC began full operations with Argonne's first teraflops computing cluster. The LCRC's driving mission is to enable and promote computational science and engineering across the Laboratory, primarily by operating computing facilities and supporting application use and development. This report describes the scientific activities, computing facilities, and usage in the first eighteen months of LCRC operation. In this short time LCRC has had broad impact on programs across the Laboratory. The LCRC computing facility, Jazz, is available to the entire Laboratory community. In addition, the LCRC staff provides training in high-performance computing and guidance on application usage, code porting, and algorithm development. All Argonne personnel and collaborators are encouraged to take advantage of this computing resource and to provide input into the vision and plans for computing and computational analysis at Argonne. Steering for LCRC comes from the Computational Science Advisory Committee, composed of computing experts from many Laboratory divisions. The CSAC Allocations Committee makes decisions on individual project allocations for Jazz.

Deployment of Phytotechnology in the 317/319 Area at Argonne National Laboratory-East, Innovative Technology Evaluation Report

Science.gov (United States)

Hybrid poplar and hybrid willow trees were planted for several environmental objectives at the Argonne National Laboratory - East, near Chicago, IL. Some trees were planted to clean TCE and other solvents from soil, some were planted to control surface water flow on a landfill, a...

Argonne National Lab gets Linux network teraflop cluster

CERN Multimedia

2003-01-01

"Linux NetworX, Salt Lake City, Utah, has delivered an Evolocity II (E2) Linux cluster to Argonne National Laboratory that is capable of performing more than one trillion calculations per second (1 teraFLOP). The cluster, named "Jazz" by Argonne, is designed to provide optimum performance for multiple disciplines such as chemistry, physics and reactor engineering and will be used by the entire scientific community at the Lab" (1 page).

Argonne National Laboratory Physics Division annual report, January--December 1996

Energy Technology Data Exchange (ETDEWEB)

Thayer, K.J. [ed.

1997-08-01

The past year has seen several of the Physics Division`s new research projects reach major milestones with first successful experiments and results: the atomic physics station in the Basic Energy Sciences Research Center at the Argonne Advanced Photon Source was used in first high-energy, high-brilliance x-ray studies in atomic and molecular physics; the Short Orbit Spectrometer in Hall C at the Thomas Jefferson National Accelerator (TJNAF) Facility that the Argonne medium energy nuclear physics group was responsible for, was used extensively in the first round of experiments at TJNAF; at ATLAS, several new beams of radioactive isotopes were developed and used in studies of nuclear physics and nuclear astrophysics; the new ECR ion source at ATLAS was completed and first commissioning tests indicate excellent performance characteristics; Quantum Monte Carlo calculations of mass-8 nuclei were performed for the first time with realistic nucleon-nucleon interactions using state-of-the-art computers, including Argonne`s massively parallel IBM SP. At the same time other future projects are well under way: preparations for the move of Gammasphere to ATLAS in September 1997 have progressed as planned. These new efforts are imbedded in, or flowing from, the vibrant ongoing research program described in some detail in this report: nuclear structure and reactions with heavy ions; measurements of reactions of astrophysical interest; studies of nucleon and sub-nucleon structures using leptonic probes at intermediate and high energies; atomic and molecular structure with high-energy x-rays. The experimental efforts are being complemented with efforts in theory, from QCD to nucleon-meson systems to structure and reactions of nuclei. Finally, the operation of ATLAS as a national users facility has achieved a new milestone, with 5,800 hours beam on target for experiments during the past fiscal year.

Argonne National Laboratory summary site environmental report for calendar year 2006.

Energy Technology Data Exchange (ETDEWEB)

Golchert, N. W.; ESH/QA Oversight

2008-03-27

This booklet is designed to inform the public about what Argonne National Laboratory is doing to monitor its environment and to protect its employees and neighbors from any adverse environmental impacts from Argonne research. The Downers Grove South Biology II class was selected to write this booklet, which summarizes Argonne's environmental monitoring programs for 2006. Writing this booklet also satisfies the Illinois State Education Standard, which requires that students need to know and apply scientific concepts to graduate from high school. This project not only provides information to the public, it will help students become better learners. The Biology II class was assigned to condense Argonne's 300-page, highly technical Site Environmental Report into a 16-page plain-English booklet. The site assessment relates to the class because the primary focus of the Biology II class is ecology and the environment. Students developed better learning skills by working together cooperatively, writing and researching more effectively. Students used the Argonne Site Environmental Report, the Internet, text books and information from Argonne scientists to help with their research on their topics. The topics covered in this booklet are the history of Argonne, groundwater, habitat management, air quality, Argonne research, Argonne's environmental non-radiological program, radiation, and compliance. The students first had to read and discuss the Site Environmental Report and then assign topics to focus on. Dr. Norbert Golchert and Mr. David Baurac, both from Argonne, came into the class to help teach the topics more in depth. The class then prepared drafts and wrote a final copy. Ashley Vizek, a student in the Biology class stated, 'I reviewed my material and read it over and over. I then took time to plan my paper out and think about what I wanted to write about, put it into foundation questions and started to write my paper. I rewrote and revised so I

Environment, Safety and Health Progress Assessment of the Argonne Illinois Site

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

This report documents the results of the US Department of Energy (DOE) Environment, Safety and Health (ES&H) Progress Assessment of the Argonne Illinois Site (AIS), near Chicago, Illinois, conducted from October 25 through November 9, 1993. During the Progress Assessment, activities included a selective review of the ES&H management systems and programs with principal focus on the DOE Office of Energy Research (ER); CH, which includes the Argonne Area Office; the University of Chicago; and the contractor`s organization responsible for operation of Argonne National Laboratory (ANL). The ES&H Progress Assessments are part of DOE`s continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. The purpose of the AIS ES&H Progress Assessment was to provide the Secretary of Energy, senior DOE managers, and contractor management with concise independent information on the following: change in culture and attitude related to ES&H activities; progress and effectiveness of the ES&H corrective actions resulting from the previous Tiger Team Assessment; adequacy and effectiveness of the ES&H self-assessment process of the DOE line organizations, the site management, and the operating contractor; and effectiveness of DOE and contractor management structures, resources, and systems to effectively address ES&H problems and new ES&H initiatives.

Environment, Safety and Health Progress Assessment of the Argonne Illinois Site

International Nuclear Information System (INIS)

1993-11-01

This report documents the results of the US Department of Energy (DOE) Environment, Safety and Health (ES ampersand H) Progress Assessment of the Argonne Illinois Site (AIS), near Chicago, Illinois, conducted from October 25 through November 9, 1993. During the Progress Assessment, activities included a selective review of the ES ampersand H management systems and programs with principal focus on the DOE Office of Energy Research (ER); CH, which includes the Argonne Area Office; the University of Chicago; and the contractor's organization responsible for operation of Argonne National Laboratory (ANL). The ES ampersand H Progress Assessments are part of DOE's continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. The purpose of the AIS ES ampersand H Progress Assessment was to provide the Secretary of Energy, senior DOE managers, and contractor management with concise independent information on the following: change in culture and attitude related to ES ampersand H activities; progress and effectiveness of the ES ampersand H corrective actions resulting from the previous Tiger Team Assessment; adequacy and effectiveness of the ES ampersand H self-assessment process of the DOE line organizations, the site management, and the operating contractor; and effectiveness of DOE and contractor management structures, resources, and systems to effectively address ES ampersand H problems and new ES ampersand H initiatives

Argonne National Laboratory Annual Report of Laboratory Directed Research and Development Program Activities for FY 1994

Energy Technology Data Exchange (ETDEWEB)

None

1995-02-25

The purposes of Argonne's Laboratory Directed Research and Development (LDRD) Program are to encourage the development of novel concepts, enhance the Laboratory's R and D capabilities, and further the development of its strategic initiatives. Projects are selected from proposals for creative and innovative R and D studies which are not yet eligible for timely support through normal programmatic channels. Among the aims of the projects supported by the Program are establishment of engineering proof-of-principle; assessment of design feasibility for prospective facilities; development of an instrumental prototype, method, or system; or discovery in fundamental science. Several of these projects are closely associated with major strategic thrusts of the Laboratory as described in Argonne's Five-Year Institutional Plan, although the scientific implications of the achieved results extend well beyond Laboratory plans and objectives. The projects supported by the Program are distributed across the major programmatic areas at Argonne as indicated in the Laboratory's LDRD Plan for FY 1994. Project summaries of research in the following areas are included: (1) Advanced Accelerator and Detector Technology; (2) X-ray Techniques for Research in Biological and Physical Science; (3) Nuclear Technology; (4) Materials Science and Technology; (5) Computational Science and Technology; (6) Biological Sciences; (7) Environmental Sciences: (8) Environmental Control and Waste Management Technology; and (9) Novel Concepts in Other Areas.

Careers | Argonne National Laboratory

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community. Learn More » Life at Argonne Our diverse community values work-life balance. Find your niche ; enjoy life at work! Learn More » Back to top Twitter Flickr Facebook Linked In YouTube Pinterest Google National Security User Facilities Science Work with Us About Safety News Careers Apply for a Job External

Electron scattering. Lectures given at Argonne National Laboratory

International Nuclear Information System (INIS)

Walecka, J.D.

1984-01-01

This report is an almost verbatim copy of lectures on Electron Scattering given at Argonne National Laboratory in the Fall of 1982 by John Dirk Walecka. Professor Walecka was an Argonne Fellow in the Physics Division from October 1982 to January 1983. Broad headings include general considerations, coincidence cross section (e,e'x), quantum electrodynamics and radiative corrections, unification of electroweak interactions, relativistic models of nuclear structure, electroproduction of pions and nucleon resonances, and deep inelastic (e,e')

Computational Science at the Argonne Leadership Computing Facility

Science.gov (United States)

Romero, Nichols

2014-03-01

The goal of the Argonne Leadership Computing Facility (ALCF) is to extend the frontiers of science by solving problems that require innovative approaches and the largest-scale computing systems. ALCF's most powerful computer - Mira, an IBM Blue Gene/Q system - has nearly one million cores. How does one program such systems? What software tools are available? Which scientific and engineering applications are able to utilize such levels of parallelism? This talk will address these questions and describe a sampling of projects that are using ALCF systems in their research, including ones in nanoscience, materials science, and chemistry. Finally, the ways to gain access to ALCF resources will be presented. This research used resources of the Argonne Leadership Computing Facility at Argonne National Laboratory, which is supported by the Office of Science of the U.S. Department of Energy under contract DE-AC02-06CH11357.

Recent developments in the target facilities at Argonne National Laboratory

International Nuclear Information System (INIS)

Greene, J.P.; Thomas, G.E.

1989-01-01

A description is given of recent developments in the target facility at Argonne National Laboratory (ANL). Highlights include equipment upgrades which enable us to provide enhanced capabilities for support of the Argonne Heavy-Ion ATLAS Accelerator Project. Also, future plans and additional equipment acquisitions will be discussed. (orig.)

Applied mathematical sciences research at Argonne, April 1, 1981-March 31, 1982

International Nuclear Information System (INIS)

Pieper, G.W.

1982-01-01

This report reviews the research activities in Applied Mathematical Sciences at Argonne National Laboratory for the period April 1, 1981, through March 31, 1982. The body of the report discusses various projects carried out in three major areas of research: applied analysis, computational mathematics, and software engineering. Information on section staff, visitors, workshops, and seminars is found in the appendices

Recent developments in the target facilities at Argonne National Laboratory

International Nuclear Information System (INIS)

Greene, J.P.; Thomas, G.E.

1988-01-01

A description is given of recent developments in the target facility at Argonne National Laboratory. Highlights include equipment upgrades which enables us to provide enhanced capabilities for support of the Argonne Heavy-Ion ATLAS Accelerator Project. Also future plans and additional equipment acquisitions will be discussed. 3 refs., 3 tabs

Argonne Bubble Experiment Thermal Model Development III

Energy Technology Data Exchange (ETDEWEB)

Buechler, Cynthia Eileen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2018-01-11

This report describes the continuation of the work reported in “Argonne Bubble Experiment Thermal Model Development” and “Argonne Bubble Experiment Thermal Model Development II”. The experiment was performed at Argonne National Laboratory (ANL) in 2014. A rastered 35 MeV electron beam deposited power in a solution of uranyl sulfate, generating heat and radiolytic gas bubbles. Irradiations were performed at beam power levels between 6 and 15 kW. Solution temperatures were measured by thermocouples, and gas bubble behavior was recorded. The previous report2 described the Monte-Carlo N-Particle (MCNP) calculations and Computational Fluid Dynamics (CFD) analysis performed on the as-built solution vessel geometry. The CFD simulations in the current analysis were performed using Ansys Fluent, Ver. 17.2. The same power profiles determined from MCNP calculations in earlier work were used for the 12 and 15 kW simulations. The primary goal of the current work is to calculate the temperature profiles for the 12 and 15 kW cases using reasonable estimates for the gas generation rate, based on images of the bubbles recorded during the irradiations. Temperature profiles resulting from the CFD calculations are compared to experimental measurements.

ARGONNE/ NOVOSIBIRSK: Storing polarized deuterons

International Nuclear Information System (INIS)

Anon.

1990-01-01

Promising new results come from a collaboration between the Institute of Physics, Novosibirsk, and the US Argonne Laboratory, initiated in 1988 to look at the possibilities for using polarized (spin oriented) gas targets in high current electron storage rings, the object being to maximize target polarization levels

Argonne's Expedited Site Characterization: An integrated approach to cost- and time-effective remedial investigation

International Nuclear Information System (INIS)

Burton, J.C.; Walker, J.L.; Aggarwal, P.K.; Meyer, W.T.

1995-01-01

Argonne National Laboratory has developed a methodology for remedial site investigation that has proven to be both technically superior to and more cost- and time-effective than traditional methods. This methodology is referred to as the Argonne Expedited Site Characterization (ESC). Quality is the driving force within the process. The Argonne ESC process is abbreviated only in time and cost and never in terms of quality. More usable data are produced with the Argonne ESC process than with traditional site characterization methods that are based on statistical-grid sampling and multiple monitoring wells. This paper given an overview of the Argonne ESC process and compares it with traditional methods for site characterization. Two examples of implementation of the Argonne ESC process are discussed to illustrate the effectiveness of the process in CERCLA (Comprehensive Environmental Response, Compensation, and Liability Act) and RCRA (Resource Conservation and Recovery Act) programs

Argonne Wakefield Accelerator update '92

International Nuclear Information System (INIS)

Rosing, M.; Balka, L.; Chojnacki, E.; Gai, W.; Ho, C.; Konecny, R.; Power, J.; Schoessow, P.; Simpson, J.

1992-01-01

The construction of the Argonne Wakefield Accelerator (AWA) is under way. The majority of the hardware is about to be delivered or is installed. Radiation safety systems are in the review process, and the laser system is operational. Bunch production should begin in December 1992. 4 refs., 5 figs

Argonne National Laboratory High Energy Physics Division semiannual report of research activities, January 1, 1989--June 30, 1989

International Nuclear Information System (INIS)

1989-01-01

This paper discuss the following areas on High Energy Physics at Argonne National Laboratory: experimental program; theory program; experimental facilities research; accelerator research and development; and SSC detector research and development

Inspection and monitoring plan, contaminated groundwater seeps 317/319/ENE Area, Argonne National Laboratory

International Nuclear Information System (INIS)

1996-01-01

During the course of completing the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) in the 317/319/East-Northeast (ENE) Area of Argonne National Laboratory-East (ANL-E), groundwater was discovered moving to the surface through a series of groundwater seeps. The seeps are located in a ravine approximately 600 ft south of the ANL-E fence line in Waterfall Glen Forest Preserve. Samples of the seep water were collected and analyzed for selected parameters. Two of the five seeps sampled were found to contain detectable levels of organic contaminants. Three chemical species were identified: chloroform (14--25 microg/L), carbon tetrachloride (56--340 microg/L), and tetrachloroethylene (3--6 microg/L). The other seeps did not contain detectable levels of volatile organics. The nature of the contaminants in the seeps will also be monitored on a regular basis. Samples of surface water flowing through the bottom of the ravine and groundwater emanating from the seeps will be collected and analyzed for chemical and radioactive constituents. The results of the routine sampling will be compared with the concentrations used in the risk assessment. If the concentrations exceed those used in the risk assessment, the risk calculations will be revised by using the higher numbers. This revised analysis will determine if additional actions are warranted

2015 Annual Report - Argonne Leadership Computing Facility

Energy Technology Data Exchange (ETDEWEB)

Collins, James R. [Argonne National Lab. (ANL), Argonne, IL (United States); Papka, Michael E. [Argonne National Lab. (ANL), Argonne, IL (United States); Cerny, Beth A. [Argonne National Lab. (ANL), Argonne, IL (United States); Coffey, Richard M. [Argonne National Lab. (ANL), Argonne, IL (United States)

2015-01-01

The Argonne Leadership Computing Facility provides supercomputing capabilities to the scientific and engineering community to advance fundamental discovery and understanding in a broad range of disciplines.

2014 Annual Report - Argonne Leadership Computing Facility

Energy Technology Data Exchange (ETDEWEB)

Collins, James R. [Argonne National Lab. (ANL), Argonne, IL (United States); Papka, Michael E. [Argonne National Lab. (ANL), Argonne, IL (United States); Cerny, Beth A. [Argonne National Lab. (ANL), Argonne, IL (United States); Coffey, Richard M. [Argonne National Lab. (ANL), Argonne, IL (United States)

2014-01-01

The Argonne Leadership Computing Facility provides supercomputing capabilities to the scientific and engineering community to advance fundamental discovery and understanding in a broad range of disciplines.

Radiological safety at Argonne National Laboratory's heavy ion research facility

International Nuclear Information System (INIS)

Cooke, R.H.; Wynveen, R.A.

1985-01-01

This paper discusses the radiological safety system to be employed at the Argonne tandem-linac accelerator system (ATLAS). The design parameters of ATLAS that affect safety have remained unchanged since ATLAS construction began in 1982. This paper will present the details of the hardware, the administrative controls, and the radiation monitoring that will be in effect when beam is produced in April 1985. The experimental hall utilizing the maximum energy beam (proportional27 MeV per nucleon) from the completed ATLAS has been partitioned with shielding blocks into its final configuration. Because scientists want access to some of the partitioned-off areas while beam is present in other areas, an interlock and logic system allowing such occupancy has been designed. The rationale and hardware of the system will be discussed. Since one of the potential radiation hazards is high-energy forward-directed neutrons from any location where the beam impinges (such as collimators, bending and focussing systems, experimental targets, and beam stops), radiation surveys and hazard assessments are necessary for the administrative controls that allow occupancy of various areas. Because of the various uses of ATLAS, neutrons (the dominant beam hazard) will be non-existent in some experiments and will be of energies > or approx.10 MeV for a few experiments. These conditions may exist at specific locations during beam preparation but may change rapidly when beam is finally delivered to an experimental area. Monitoring and assessing such time varying and geographically changing hazards will be a challenge since little data will be available on source terms until various beams are produced of sufficient intensity and energy to make measurements. How the operating division for ATLAS and the Argonne safety division are addressing this aspect through administrative controls will also be discussed. (orig./HSI)

Argonne National Laboratory, High Energy Physics Division, semiannual report of research activities, July 1, 1989--December 31, 1989

International Nuclear Information System (INIS)

1989-01-01

This report discusses research being conducted at the Argonne National Laboratory in the following areas: Experimental High Energy Physics; Theoretical High Energy Physics; Experimental Facilities Research; Accelerator Research and Development; and SSC Detector Research and Development

Environmental assessment related to the operation of Argonne National Laboratory, Argonne, Illinois

Energy Technology Data Exchange (ETDEWEB)

1982-08-01

In order to evaluate the environmental impacts of Argonne National Laboratory (ANL) operations, this assessment includes a descriptive section which is intended to provide sufficient detail to allow the various impacts to be viewed in proper perspective. In particular, details are provided on site characteristics, current programs, characterization of the existing site environment, and in-place environmental monitoring programs. In addition, specific facilities and operations that could conceivably impact the environment are described at length. 77 refs., 16 figs., 47 tabs.

Argonne National Laboratory summary site environmental report for calendar year 2007.

Energy Technology Data Exchange (ETDEWEB)

Golchert, N. W.

2009-05-22

This summary of Argonne National Laboratory's Site Environmental Report for calendar year 2007 was written by 20 students at Downers Grove South High School in Downers Grove, Ill. The student authors are classmates in Mr. Howard's Bio II course. Biology II is a research-based class that teaches students the process of research by showing them how the sciences apply to daily life. For the past seven years, Argonne has worked with Biology II students to create a short document summarizing the Site Environmental Report to provide the public with an easy-to-read summary of the annual 300-page technical report on the results of Argonne's on-site environmental monitoring program. The summary is made available online and given to visitors to Argonne, researchers interested in collaborating with Argonne, future employees, and many others. In addition to providing Argonne and the public with an easily understandable short summary of a large technical document, the participating students learn about professional environmental monitoring procedures, achieve a better understanding of the time and effort put forth into summarizing and publishing research, and gain confidence in their own abilities to express themselves in writing. The Argonne Summary Site Environmental Report fits into the educational needs for 12th grade students. Illinois State Educational Goal 12 states that a student should understand the fundamental concepts, principles, and interconnections of the life, physical, and earth/space sciences. To create this summary booklet, the students had to read and understand the larger technical report, which discusses in-depth many activities and programs that have been established by Argonne to maintain a safe local environment. Creating this Summary Site Environmental Report also helps students fulfill Illinois State Learning Standard 12B5a, which requires that students be able to analyze and explain biodiversity issues, and the causes and effects of

Argonne Fuel Cycle Facility ventilation system -- modeling and results

International Nuclear Information System (INIS)

Mohr, D.; Feldman, E.E.; Danielson, W.F.

1995-01-01

This paper describes an integrated study of the Argonne-West Fuel Cycle Facility (FCF) interconnected ventilation systems during various operations. Analyses and test results include first a nominal condition reflecting balanced pressures and flows followed by several infrequent and off-normal scenarios. This effort is the first study of the FCF ventilation systems as an integrated network wherein the hydraulic effects of all major air systems have been analyzed and tested. The FCF building consists of many interconnected regions in which nuclear fuel is handled, transported and reprocessed. The ventilation systems comprise a large number of ducts, fans, dampers, and filters which together must provide clean, properly conditioned air to the worker occupied spaces of the facility while preventing the spread of airborne radioactive materials to clean am-as or the atmosphere. This objective is achieved by keeping the FCF building at a partial vacuum in which the contaminated areas are kept at lower pressures than the other worker occupied spaces. The ventilation systems of FCF and the EBR-II reactor are analyzed as an integrated totality, as demonstrated. We then developed the network model shown in Fig. 2 for the TORAC code. The scope of this study was to assess the measured results from the acceptance/flow balancing testing and to predict the effects of power failures, hatch and door openings, single-failure faulted conditions, EBR-II isolation, and other infrequent operations. The studies show that the FCF ventilation systems am very controllable and remain stable following off-normal events. In addition, the FCF ventilation system complex is essentially immune to reverse flows and spread of contamination to clean areas during normal and off-normal operation

Argonne Tau-charm factory collider design study

International Nuclear Information System (INIS)

Teng, L.C.; Crosbie, E.A.; Norem, J.

1995-01-01

The design approach and design principles for a Tau-charm Factory at Argonne were studied. These studies led to a set of preliminary parameters and tentative component features as presented in this paper

Mathematics and Computer Science | Argonne National Laboratory

Science.gov (United States)

Extreme Computing Data-Intensive Science Applied Mathematics Science & Engineering Applications Software Extreme Computing Data-Intensive Science Applied Mathematics Science & Engineering Opportunities For Employees Staff Directory Argonne National Laboratory Mathematics and Computer Science Tools

Use of nuclear facilities at Argonne-West to support new environmental missions

International Nuclear Information System (INIS)

Black, D.B.; Dwight, C.C.; Lineberry, M.J.

1994-08-01

At Argonne National Laboratory-West, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used to meet the environmental and waste management need of the US Department of Energy. These needs include waste characterization, waste testing, and waste treatment technology development. Waste characterization and repackaging activities are being performed in the Hot Fuel Examination Facility for the Waste Isolation Pilot Plant (WIPP) Experimental Test Program. Characterization activities include sampling the gas in actual waste containers, categorizing waste contents for their gas generation potential, and extracting solid samples. A new waste testing project will utilize the Zero Powered Physics Reactor facility. In the workroom of these facility, laboratory gas generation experiments will be conducted with contact-handled transuranic waste. Both the characterization and waste testing activities are part of the effort to prepare the WIPP performance assessment. Waste treatment demonstrations have or will be conducted at the Transient Reactor Test facility and involve private sector participants. The demonstrations involve the development of thermal treatment for materials containing residual amounts of plutonium using plasma-arc technology. The success of these new programs is largely due to experience gained from past missions in such areas as radiological control and nuclear safety

Action-oriented characterization at Argonne National Laboratory

International Nuclear Information System (INIS)

Moos, L.P.; Swale, R.E.

1995-01-01

Argonne National Laboratory-East and the US Department of Energy have initiated a voluntary corrective action strategy to characterize and clean up some of the on-site solid waste management units that are subject to the Resource Conservation and Recovery Act Corrective Action process. This strategy is designed for the current atmosphere of reduced funding levels and, increased demands for cleanup actions. A focused characterization program is used to identify and roughly delineate the areas of greatest risk, relying as much as possible on existing data about the site; then, removal or interim remedial actions are implemented, where appropriate. Two interim cleanup operations were completed in 1994. Two additional interim actions are planned for 1995. Future actions may include decontamination operations, soil remediation, and construction of containment barriers

The Argonne silicon strip-detector array

Energy Technology Data Exchange (ETDEWEB)

Wuosmaa, A H; Back, B B; Betts, R R; Freer, M; Gehring, J; Glagola, B G; Happ, Th; Henderson, D J; Wilt, P [Argonne National Lab., IL (United States); Bearden, I G [Purdue Univ., Lafayette, IN (United States). Dept. of Physics

1992-08-01

Many nuclear physics experiments require the ability to analyze events in which large numbers of charged particles are detected and identified simultaneously, with good resolution and high efficiency, either alone, or in coincidence with gamma rays. The authors have constructed a compact large-area detector array to measure these processes efficiently and with excellent energy resolution. The array consists of four double-sided silicon strip detectors, each 5x5 cm{sup 2} in area, with front and back sides divided into 16 strips. To exploit the capability of the device fully, a system to read each strip-detector segment has been designed and constructed, based around a custom-built multi-channel preamplifier. The remainder of the system consists of high-density CAMAC modules, including multi-channel discriminators, charge-sensing analog-to-digital converters, and time-to-digital converters. The array`s performance has been evaluated using alpha-particle sources, and in a number of experiments conducted at Argonne and elsewhere. Energy resolutions of {Delta}E {approx} 20-30 keV have been observed for 5 to 8 MeV alpha particles, as well as time resolutions {Delta}T {<=} 500 ps. 4 figs.

Verification Survey of the Building 315 Zero Power Reactor-6 Facility, Argonne National Laboratory-East, Argonne, Illinois

International Nuclear Information System (INIS)

W. C. Adams

2007-01-01

status surveys (FSS) on Cell 5 that formerly contained the ZPR-6. For the FSS, ANL is following the guidance presented in Draft NUREG/CR-5849, 'Manual for Conducting Radiological Surveys in Support of License Termination', and portions of NUREG-1575, 'Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)', as appropriate and DOE Order 5400.5, 'Radiation Protection of the Public and Environment'. (NRC 1992 and 2000 and DOE 1993 and 1995). At the time of the FSS, all contaminated systems and associated components within the scope of the surveyed areas had been removed (ANL 2006). DOE's Argonne Site Office (ASO) is responsible for oversight of the Building 315, Zero Power Reactor-6 remedial action and FSS activities. It is the policy of the DOE to perform independent (third party) verification of FSS activities (DOE 2006). The purpose of these independent verifications (IV) is to confirm that remedial actions have been effective in meeting established and site-specific guidelines and that the documentation accurately and adequately describes the radiological conditions at the site. The Oak Ridge Institute for Science and Education (ORISE) has been designated by the DOE as the organization responsible for this task at ANL, and has been requested to verify the final radiological status of the cleanup activities associated with the Building 315, ZPR-6 Decontamination and Decommissioning Project (ZPR6DDP) at ANL-E

Frontiers: Research highlights 1946-1996 [50th Anniversary Edition. Argonne National Laboratory

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

This special edition of 'Frontiers' commemorates Argonne National Laboratory's 50th anniversary of service to science and society. America's first national laboratory, Argonne has been in the forefront of U.S. scientific and technological research from its beginning. Past accomplishments, current research, and future plans are highlighted.

Argonne Tau-charm Factory collider design study

International Nuclear Information System (INIS)

Teng, L.C.; Crosbie, E.A.; Norem, J.; Repond, J.

1996-01-01

The design approach and design principles for a Tau-charm Factory at Argonne were studied. These studies led to a set of preliminary parameters and tentative component features as presented in this paper. copyright 1996 American Institute of Physics

Argonne National Laboratory Physics Division annual report, January--December 1996

International Nuclear Information System (INIS)

Thayer, K.J.

1997-08-01

The past year has seen several of the Physics Division's new research projects reach major milestones with first successful experiments and results: the atomic physics station in the Basic Energy Sciences Research Center at the Argonne Advanced Photon Source was used in first high-energy, high-brilliance x-ray studies in atomic and molecular physics; the Short Orbit Spectrometer in Hall C at the Thomas Jefferson National Accelerator (TJNAF) Facility that the Argonne medium energy nuclear physics group was responsible for, was used extensively in the first round of experiments at TJNAF; at ATLAS, several new beams of radioactive isotopes were developed and used in studies of nuclear physics and nuclear astrophysics; the new ECR ion source at ATLAS was completed and first commissioning tests indicate excellent performance characteristics; Quantum Monte Carlo calculations of mass-8 nuclei were performed for the first time with realistic nucleon-nucleon interactions using state-of-the-art computers, including Argonne's massively parallel IBM SP. At the same time other future projects are well under way: preparations for the move of Gammasphere to ATLAS in September 1997 have progressed as planned. These new efforts are imbedded in, or flowing from, the vibrant ongoing research program described in some detail in this report: nuclear structure and reactions with heavy ions; measurements of reactions of astrophysical interest; studies of nucleon and sub-nucleon structures using leptonic probes at intermediate and high energies; atomic and molecular structure with high-energy x-rays. The experimental efforts are being complemented with efforts in theory, from QCD to nucleon-meson systems to structure and reactions of nuclei. Finally, the operation of ATLAS as a national users facility has achieved a new milestone, with 5,800 hours beam on target for experiments during the past fiscal year

Initial operation of the Argonne superconducting heavy-ion linac

Energy Technology Data Exchange (ETDEWEB)

Shepard, K. W.

1979-01-01

Initial operation and recent development of the Argonne superconducting heavy-ion linac are discussed. The linac has been developed in order to demonstrate a cost-effective means of extending the performance of electrostatic tandem accelerators. The results of beam acceleration tests which began in June 1978 are described. At present 7 of a planned array of 22 resonators are operating on-line, and the linac system provides an effective accelerating potential of 7.5 MV. Although some technical problems remain, the level of performance and reliability is sufficient that appreciable beam time is becoming available to users.

Safety analysis report: packages. Argonne National Laboratory SLSF test train shipping container, P-1 shipment. Fissile material. Final report

International Nuclear Information System (INIS)

Meyer, C.A.

1975-06-01

The package is used to ship an instrumented test fuel bundle (test train) containing fissile material. The package assembly is Argonne National Laboratory (ANL) Model R1010-0032. The shipment is fissile class III. The packaging consists of an outer carbon steel container into which an inner container is placed; the inner container is separated from the outer container by urethane foam cushioning material. The test train is supported in the inner container by a series of transverse supports spaced along the length of the test train. Both the inner and outer containers are closed with bolted covers. The covers do not seal the containers in a leaktight manner. The gross weight of the shipment is about 8350 lb. The unirradiated fissile material content is less than 3 kg of UO 2 of up to 93.2 percent enrichment. This is a Type A quantity (transport group III and less than 3 curies) of radioactive material which does not require shielding, cooling or heating, or neutron absorption or moderation functions in its packaging. The maximum exterior dimensions of the container are 37 ft 11 in. long, 24 1 / 2 in. wide, and 19 3 / 4 in. high

Status of RF superconductivity at Argonne

International Nuclear Information System (INIS)

Shepard, K.W.

1990-01-01

Development of a superconducting slow-wave structures began at Argonne National Laboratory (ANL) in 1971, and led to the first superconducting heavy-ion linac (ATLAS - the Argonne Tandem-Linac Accelerator System). The Physics Division at ANL has continued to develop superconducting RF technology for accelerating heavy-ions, with the result that the linac has been in an almost continuous process of upgrade and expansion. In 1987, the Engineering Physics Division at ANL began developing of superconducting RF components for the acceleration of high-brightness proton and deuterium beams. The two divisions collaborate in work on several applications of RF superconductivity, and also in work to develop the technology generally. The present report briefly describes major features of the superconducting heavy-ion linac (very-low-velocity superconducting linac, positive ion injector), proton accelerating structures (superconducting resonant cavities for acceleration of high-current proton and deuteron beams, RF properties of oxide superconductors), and future work. Both divisions expect to continue a variety of studies, frequently in collaboration, to advance the basic technology of RF superconductivity. (N.K.)

Argonne's Laboratory computing center - 2007 annual report.

Energy Technology Data Exchange (ETDEWEB)

Bair, R.; Pieper, G. W.

2008-05-28

Argonne National Laboratory founded the Laboratory Computing Resource Center (LCRC) in the spring of 2002 to help meet pressing program needs for computational modeling, simulation, and analysis. The guiding mission is to provide critical computing resources that accelerate the development of high-performance computing expertise, applications, and computations to meet the Laboratory's challenging science and engineering missions. In September 2002 the LCRC deployed a 350-node computing cluster from Linux NetworX to address Laboratory needs for mid-range supercomputing. This cluster, named 'Jazz', achieved over a teraflop of computing power (1012 floating-point calculations per second) on standard tests, making it the Laboratory's first terascale computing system and one of the 50 fastest computers in the world at the time. Jazz was made available to early users in November 2002 while the system was undergoing development and configuration. In April 2003, Jazz was officially made available for production operation. Since then, the Jazz user community has grown steadily. By the end of fiscal year 2007, there were over 60 active projects representing a wide cross-section of Laboratory expertise, including work in biosciences, chemistry, climate, computer science, engineering applications, environmental science, geoscience, information science, materials science, mathematics, nanoscience, nuclear engineering, and physics. Most important, many projects have achieved results that would have been unobtainable without such a computing resource. The LCRC continues to foster growth in the computational science and engineering capability and quality at the Laboratory. Specific goals include expansion of the use of Jazz to new disciplines and Laboratory initiatives, teaming with Laboratory infrastructure providers to offer more scientific data management capabilities, expanding Argonne staff use of national computing facilities, and improving the scientific

The restoration of an Argonne National Laboratory foundry

International Nuclear Information System (INIS)

Shearer, T.; Pancake, D.; Shelton, B.

1997-01-01

The Environmental Management Operations' Waste Management Department (WMD) at Argonne National Laboratory-East (ANL-E) undertook the restoration of an unused foundry with the goal of restoring the area for general use. The foundry was used in the fabrication of reactor components for ANL's research and development programs; many of the items fabricated in the facility were radioactive, thereby contaminating the foundry equipment. This paper very briefly describes the dismantling and decontamination of the facility. The major challenges associated with the safe removal of the foundry equipment included the sheer size of the equipment, a limited overhead crane capability (4.5 tonne), the minimization of radioactive and hazardous wastes, and the cost-effective completion of the project, the hazardous and radioactive wastes present, and limited process knowledge (the facility was unused for many years)

Argonne National Lab deploys Force10 networks' massively dense ethernet switch for supercomputing cluster

CERN Multimedia

2003-01-01

"Force10 Networks, Inc. today announced that Argonne National Laboratory (Argonne, IL) has successfully deployed Force10 E-Series switch/routers to connect to the TeraGrid, the world's largest supercomputing grid, sponsored by the National Science Foundation (NSF)" (1/2 page).

Status of RF superconductivity at Argonne

Energy Technology Data Exchange (ETDEWEB)

Shepard, K.W.

1989-01-01

Development of a superconducting (SC) slow-wave structures began at Argonne National Laboratory (ANL) in 1971, and led to the first SC heavy-ion linac (ATLAS - the Argonne Tandem-Linac Accelerating System), which began regularly scheduled operation in 1978. To date, more than 40,000 hours of bean-on target operating time has been accumulated with ATLAS. The Physics Division at ANL has continued to develop SC RF technology for accelerating heavy-ions, with the result that the SC linac has, up to the present, has been in an almost continuous process of upgrade and expansion. It should be noted that this has been accomplished while at the same time maintaining a vigorous operating schedule in support of the nuclear and atomic physics research programs of the division. In 1987, the Engineering Physics Division at ANL began development of SC RF components for the acceleration of high-brightness proton and deuterium beams. This work has included the evaluation of RF properties of high-{Tc} oxide superconductors, both for the above and for other applications. The two divisions collaborated while they worked on several applications of RF SC, and also worked to develop the technology generally. 11 refs., 6 figs.

CWDD accelerator at Argonne: Status and future opportunities

International Nuclear Information System (INIS)

McMichael, G.; Carwardine, J.; Den Hartog, P.; Sagalovsky, L.; Yule, T.; Clarkson, I.; Papsco, R.; Pile, G.

1994-01-01

The Continuous Wave Deuterium Demonstrator (CWDD) accelerator, a cryogenically-cooled (26K) linac, was designed to accelerate 80 mA cw of D to 7.5 MeV. CWDD was being built to demonstrate the launching of a beam with characteristics suitable for a space-based neutral particle beam (NPB). A considerable amount of hardware was constructed and installed in the Argonne-based facility, and major performance milestones were achieved before program funding ended in October 1993. Existing assets have been turned over to Argonne for continuation under other sponsors. These include a fully functional 200 kV cw D injector and high power (1 MW) cw rf amplifier, a cw RFQ that has been tuned, leak checked and aligned, and a partially completed ramped-gradient DTL. Project status and achievements are reviewed and proposals for future use of the equipment are discussed

Wire chamber degradation at the Argonne ZGS

International Nuclear Information System (INIS)

Haberichter, W.; Spinka, H.

1986-01-01

Experience with multiwire proportional chambers at high rates at the Argonne Zero Gradient Synchrotron is described. A buildup of silicon on the sense wires was observed where the beam passed through the chamber. Analysis of the chamber gas indicated that the density of silicon was probably less than 10 ppM

Three Argonne technologies win R&D 100 awards

CERN Multimedia

2003-01-01

"Three technologies developed or co-developed at the U.S. Department of Energy's Argonne National Laboratory have been recognized with R&D 100 Awards, which highlight some of the best products and technologies from around the world" (1 page).

Argonne's Laboratory computing resource center : 2006 annual report.

Energy Technology Data Exchange (ETDEWEB)

Bair, R. B.; Kaushik, D. K.; Riley, K. R.; Valdes, J. V.; Drugan, C. D.; Pieper, G. P.

2007-05-31

Argonne National Laboratory founded the Laboratory Computing Resource Center (LCRC) in the spring of 2002 to help meet pressing program needs for computational modeling, simulation, and analysis. The guiding mission is to provide critical computing resources that accelerate the development of high-performance computing expertise, applications, and computations to meet the Laboratory's challenging science and engineering missions. In September 2002 the LCRC deployed a 350-node computing cluster from Linux NetworX to address Laboratory needs for mid-range supercomputing. This cluster, named 'Jazz', achieved over a teraflop of computing power (10{sup 12} floating-point calculations per second) on standard tests, making it the Laboratory's first terascale computing system and one of the 50 fastest computers in the world at the time. Jazz was made available to early users in November 2002 while the system was undergoing development and configuration. In April 2003, Jazz was officially made available for production operation. Since then, the Jazz user community has grown steadily. By the end of fiscal year 2006, there were 76 active projects on Jazz involving over 380 scientists and engineers. These projects represent a wide cross-section of Laboratory expertise, including work in biosciences, chemistry, climate, computer science, engineering applications, environmental science, geoscience, information science, materials science, mathematics, nanoscience, nuclear engineering, and physics. Most important, many projects have achieved results that would have been unobtainable without such a computing resource. The LCRC continues to foster growth in the computational science and engineering capability and quality at the Laboratory. Specific goals include expansion of the use of Jazz to new disciplines and Laboratory initiatives, teaming with Laboratory infrastructure providers to offer more scientific data management capabilities, expanding Argonne staff

Quality management at Argonne National Laboratory: Status, accomplishments, and lessons learned

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

In April 1992, Argonne National Laboratory (ANL) launched the implementation of quality management (QM) as an initiative of the Laboratory Director. The goal of the program is to seek ways of improving Laboratory performance and effectiveness by drawing from the realm of experiences in the global total quality management movement. The Argonne QM initiative began with fact finding and formulating a strategy for implementation; the emphasis is that the underlying principles of QM should be an integral part of how the Laboratory is managed and operated. A primary theme that has guided the Argonne QM initiative is to consider only those practices that offer the potential for real improvement, make sense, fit the culture, and would be credible to the broad population. In October 1993, the Laboratory began to pilot a targeted set of QM activities selected to produce outcomes important to the Laboratory--strengthening the customer focus, improving work processes, enhancing employee involvement and satisfaction, and institutionalizing QM. This report describes the results of the just-concluded QM development and demonstration phase in terms of detailed strategies, accomplishments, and lessons learned. These results are offered as evidence to support the conclusion that the Argonne QM initiative has achieved value-added results and credibility and is well positioned to support future deployment across the entire Laboratory as an integrated management initiative. Recommendations for follow-on actions to implement future deployment are provided separately.

Flow Induced Vibration Program at Argonne National Laboratory

Science.gov (United States)

1984-01-01

The Argonne National Laboratory's Flow Induced Vibration Program, currently residing in the Laboratory's Components Technology Division is discussed. Throughout its existence, the overall objective of the program was to develop and apply new and/or improved methods of analysis and testing for the design evaluation of nuclear reactor plant components and heat exchange equipment from the standpoint of flow induced vibration. Historically, the majority of the program activities were funded by the US Atomic Energy Commission, the Energy Research and Development Administration, and the Department of Energy. Current DOE funding is from the Breeder Mechanical Component Development Division, Office of Breeder Technology Projects; Energy Conversion and Utilization Technology Program, Office of Energy Systems Research; and Division of Engineering, Mathematical and Geosciences, office of Basic Energy Sciences. Testing of Clinch River Breeder Reactor upper plenum components was funded by the Clinch River Breeder Reactor Plant Project Office. Work was also performed under contract with Foster Wheeler, General Electric, Duke Power Company, US Nuclear Regulatory Commission, and Westinghouse.

Status of RF superconductivity at Argonne

International Nuclear Information System (INIS)

Shepard, K.W.

1989-01-01

Development of a superconducting (SC) slow-wave structures began at Argonne National Laboratory (ANL) in 1971, and led to the first SC heavy-ion linac (ATLAS - the Argonne Tandem-Linac Accelerating System), which began regularly scheduled operation in 1978. To date, more than 40,000 hours of bean-on target operating time has been accumulated with ATLAS. The Physics Division at ANL has continued to develop SC RF technology for accelerating heavy-ions, with the result that the SC linac has, up to the present, has been in an almost continuous process of upgrade and expansion. It should be noted that this has been accomplished while at the same time maintaining a vigorous operating schedule in support of the nuclear and atomic physics research programs of the division. In 1987, the Engineering Physics Division at ANL began development of SC RF components for the acceleration of high-brightness proton and deuterium beams. This work has included the evaluation of RF properties of high-T c oxide superconductors, both for the above and for other applications. The two divisions collaborated while they worked on several applications of RF SC, and also worked to develop the technology generally. 11 refs., 6 figs

Radiation chemistry at the Metallurgical Laboratory, Manhattan Project, University of Chicago (1942-1947) and the Argonne National Laboratory, Argonne, IL (1947-1984)

International Nuclear Information System (INIS)

Gordon, S.

1989-01-01

The events in radiation chemistry which occurred in the Manhattan Project Laboratory and Argonne National Laboratory during World War II are reviewed. Research programmes from then until the present day are presented, with emphasis on pulse radiolysis studies. (UK)

Materials technology at Argonne National Laboratory

International Nuclear Information System (INIS)

Betten, P.

1989-01-01

Argonne is actively involved in the research and development of new materials research and development (R ampersand D). Five new materials technologies have been identified for commercial potential and are presented in this paper as follows: (1) nanophase materials, (2) nuclear magnetic resonance (NMR) imaging of ceramics, (3) superconductivity developments and technology transfer mechanisms, and (4) COMMIX computer code modeling for metal castings, and (5) tribology using ion-assisted deposition (IAB). 4 refs., 7 figs., 1 tab

Argonne National Laboratory: An example of a US nuclear research centre

International Nuclear Information System (INIS)

Bhattacharyya, S.

2001-01-01

The nuclear era was ushered in 1942 with the demonstration of a sustained nuclear chain reaction in Chicago Pile 1 facility. The USA then set up five large national multi disciplinary laboratories for developing nuclear technology for civilian use and three national laboratories for military applications. Reactor development, including prototype construction, was the main focus of the Argonne National Laboratory. More than 100 power reactors operating in the USA have benefited from R and D in the national laboratories. However, currently the support for nuclear power has waned. With the end of the cold war there has also been a need to change the mission of laboratories involved in military applications. For all laboratories of the Department of Energy (DOE) the mission, which was clearly focused earlier on high risk, high payoff long term R and D has now become quite diffused with a number of near term programmes. Cost and mission considerations have resulted in shutting down of many large facilities as well as auxiliary facilities. Erosion of infrastructure has also resulted in reduced opportunities for research which means dwindling of interest in nuclear science and engineering among the younger generation. The current focus of nuclear R and D in the DOE laboratories is on plant life extension, deactivation and decommissioning, spent fuel management and waste management. Advanced aspects include space nuclear applications and nuclear fusion R and D. At the Argonne National Laboratory, major initiatives for the future would be in the areas of science, energy, environment and non-proliferation technologies. International collaboration would be useful mechanisms to achieve cost effective solutions for major developmental areas. These include reactor operation and safety, repositories for high level nuclear waste, reactor system decommissioning, large projects like a nuclear fusion reactor and advanced power reactors. The IAEA could have a positive role in these

Argonne National Laboratory research offers clues to Alzheimer's plaques

CERN Multimedia

2003-01-01

Researchers from Argonne National Laboratory and the University of Chicago have developed methods to directly observe the structure and growth of microscopic filaments that form the characteristic plaques found in the brains of those with Alzheimer's Disease (1 page).

Argonne National Laboratory 1985 publications

International Nuclear Information System (INIS)

Kopta, J.A.; Hale, M.R.

1987-08-01

This report is a bibliography of scientific and technical 1985 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1985. This compilation, prepared by the Technical Information Services Technical Publications Section (TPB), lists all nonrestricted 1985 publications submitted to TPS by Laboratory's Divisions. The report is divided into seven parts: Journal Articles - Listed by first author, ANL Reports - Listed by report number, ANL and non-ANL Unnumbered Reports - Listed by report number, Non-ANL Numbered Reports - Listed by report number, Books and Book Chapters - Listed by first author, Conference Papers - Listed by first author, Complete Author Index

Argonne's Laboratory Computing Resource Center : 2005 annual report.

Energy Technology Data Exchange (ETDEWEB)

Bair, R. B.; Coghlan, S. C; Kaushik, D. K.; Riley, K. R.; Valdes, J. V.; Pieper, G. P.

2007-06-30

Argonne National Laboratory founded the Laboratory Computing Resource Center in the spring of 2002 to help meet pressing program needs for computational modeling, simulation, and analysis. The guiding mission is to provide critical computing resources that accelerate the development of high-performance computing expertise, applications, and computations to meet the Laboratory's challenging science and engineering missions. The first goal of the LCRC was to deploy a mid-range supercomputing facility to support the unmet computational needs of the Laboratory. To this end, in September 2002, the Laboratory purchased a 350-node computing cluster from Linux NetworX. This cluster, named 'Jazz', achieved over a teraflop of computing power (10{sup 12} floating-point calculations per second) on standard tests, making it the Laboratory's first terascale computing system and one of the fifty fastest computers in the world at the time. Jazz was made available to early users in November 2002 while the system was undergoing development and configuration. In April 2003, Jazz was officially made available for production operation. Since then, the Jazz user community has grown steadily. By the end of fiscal year 2005, there were 62 active projects on Jazz involving over 320 scientists and engineers. These projects represent a wide cross-section of Laboratory expertise, including work in biosciences, chemistry, climate, computer science, engineering applications, environmental science, geoscience, information science, materials science, mathematics, nanoscience, nuclear engineering, and physics. Most important, many projects have achieved results that would have been unobtainable without such a computing resource. The LCRC continues to improve the computational science and engineering capability and quality at the Laboratory. Specific goals include expansion of the use of Jazz to new disciplines and Laboratory initiatives, teaming with Laboratory infrastructure

Flow Induced Vibration Program at Argonne National Laboratory

International Nuclear Information System (INIS)

1984-01-01

Argonne National Laboratory has had a Flow Induced Vibration Program since 1967; the Program currently resides in the Laboratory's Components Technology Division. Throughout its existence, the overall objective of the program has been to develop and apply new and/or improved methods of analysis and testing for the design evaluation of nuclear reactor plant components and heat exchange equipment from the standpoint of flow induced vibration. Historically, the majority of the program activities have been funded by the US Atomic Energy Commission (AEC), Energy Research and Development Administration (ERDA), and Department of Energy (DOE). Current DOE funding is from the Breeder Mechanical Component Development Division, Office of Breeder Technology Projects; Energy Conversion and Utilization Technology (ECUT) Program, Office of Energy Systems Research; and Division of Engineering, Mathematical and Geosciences, Office of Basic Energy Sciences. Testing of Clinch River Breeder Reactor upper plenum components has been funded by the Clinch River Breeder Reactor Plant (CRBRP) Project Office. Work has also been performed under contract with Foster Wheeler, General Electric, Duke Power Company, US Nuclear Regulatory Commission, and Westinghouse

An in-house alternative to traditional SDI services at Argonne National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Noel, R.E.; Dominiak, R.R.

1997-02-20

Selective Dissemination of Information (SDIs) are based on automated, well-defined programs that regularly produce precise, relevant bibliographic information. Librarians have typically turned to information vendors such as Dialog or STN international to design and implement these searches for their users in business, academia, and the science community. Because Argonne National Laboratory (ANL) purchases the Institute for Scientific Information (ISI) Current Contents tapes (all subject areas excluding Humanities). ANL scientists enjoy the benefit of in-house developments with BASISplus software programming and no longer need to turn to outside companies for reliable SDI service. The database and its customized services are known as ACCESS (Argonne Current Contents Electronic Search Service). Through collaboration with librarians on Boolean logic and selection of terms, users can now design their own personal profiles to comb the new data, thereby avoiding service fees from outside providers. Based on the feedback from scientists, it seems that this new service can help transform the ANL distributed libraries into more efficient central functioning entities that better serve the users. One goal is to eliminate the routing of paper copies of many new journal issues to different library locations for users to browse; instead users may be expected to rely more on electronic dissemination of both table of contents and customized SDIs for new scientific and technical information.

Physics Division Argonne National Laboratory description of the programs and facilities.

Energy Technology Data Exchange (ETDEWEB)

Thayer, K.J. [ed.

1999-05-24

The ANL Physics Division traces its roots to nuclear physics research at the University of Chicago around the time of the second world war. Following the move from the University of Chicago out to the present Argonne site and the formation of Argonne National Laboratory: the Physics Division has had a tradition of research into fundamental aspects of nuclear and atomic physics. Initially, the emphasis was on areas such as neutron physics, mass spectrometry, and theoretical studies of the nuclear shell model. Maria Goeppert Maier was an employee in the Physics Division during the time she did her Nobel-Prize-winning work on the nuclear shell model. These interests diversified and at the present time the research addresses a wide range of current problems in nuclear and atomic physics. The major emphasis of the current experimental nuclear physics research is in heavy-ion physics, centered around the ATLAS facility (Argonne Tandem-Linac Accelerator System) with its new injector providing intense, energetic ion beams over the fill mass range up to uranium. ATLAS is a designated National User Facility and is based on superconducting radio-frequency technology developed in the Physics Division. A small program continues in accelerator development. In addition, the Division has a strong program in medium-energy nuclear physics carried out at a variety of major national and international facilities. The nuclear theory research in the Division spans a wide range of interests including nuclear dynamics with subnucleonic degrees of freedom, dynamics of many-nucleon systems, nuclear structure, and heavy-ion interactions. This research makes contact with experimental research programs in intermediate-energy and heavy-ion physics, both within the Division and on the national and international scale. The Physics Division traditionally has strong connections with the nation's universities. We have many visiting faculty members and we encourage students to participate in our

The Argonne laser-driven D target: Recent developments and progress

International Nuclear Information System (INIS)

Fedchak, J.A.; Bailey, K.; Cummings, W.J.

1997-01-01

The first direct measurements of nuclear tensor polarization p zz in a laser-driven polarized D target have been performed at Argonne. We present p zz and electron polarization P e data taken at a magnetic field of 600 G in the optical pumping cell. These results are highly indicative that spin-temperature equilibrium is achieved in the system. To prevent spin relaxation of D and K atoms as well as the molecular recombination of D atoms, the walls of the laser-driven D target are coated with organosilane compounds. We discuss a new coating technique, the open-quotes afterwashclose quotes, developed at Argonne which has yielded stable atomic fraction results when the coating is exposed to K. We also present new coating techniques for glass and Cu substrates

Welcome to the home page of the Decontamination and Decommissioning Program at Argonne National Laboratory

International Nuclear Information System (INIS)

1996-01-01

This report presents the details of the Argonne National Laboratory Home Page. Topics discussed include decontamination and decommissioning of the following: hot cells; remedial action; Experimental Boiling Water Reactor; glove boxes; the Chicago Pile No. 5 Research Reactor Facility; the Janus Reactor; Building 310 Retention Tanks; Zero Power Reactors 6 and 9; Argonne Thermal Source Reactor; cyclotron facility; and Juggernaut reactor

Argonne National Laboratory 1985 publications

Energy Technology Data Exchange (ETDEWEB)

Kopta, J.A. (ED.); Hale, M.R. (comp.)

1987-08-01

This report is a bibliography of scientific and technical 1985 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1985. This compilation, prepared by the Technical Information Services Technical Publications Section (TPB), lists all nonrestricted 1985 publications submitted to TPS by Laboratory's Divisions. The report is divided into seven parts: Journal Articles - Listed by first author, ANL Reports - Listed by report number, ANL and non-ANL Unnumbered Reports - Listed by report number, Non-ANL Numbered Reports - Listed by report number, Books and Book Chapters - Listed by first author, Conference Papers - Listed by first author, Complete Author Index.

Argonne Natl Lab receives TeraFLOP Cluster Linux NetworX

CERN Multimedia

2002-01-01

" Linux NetworX announced today it has delivered an Evolocity II (E2) Linux cluster to Argonne National Laboratory that is capable of performing more than one trillion calculations per second (1 teraFLOP)" (1/2 page).

Addendum to a proposal for ATLAS: a precision heavy-ion accelerator at Argonne National Laboratory

International Nuclear Information System (INIS)

1978-12-01

This revised proposal for the construction of the Argonne Tandem-Linac Accelerator System (ATLAS) is in all essentials the same as the proposal originally presented to NUSAC in March 1978. The only differences worth mentioning are the plan to expand the experimental area somewhat more than was originally proposed and an increased cost, brought about principally by inflation. The outline presented is the same as in the original document, reproduced for the convenience of the reader. The objective of the proposed Argonne Tandem-Linac Accelerator System (ATLAS) is to provide precision beams of heavy ions for nuclear physics research in the region of projectile energies comparable to nuclear binding energies (5 to 25 MeV/A). By using the demonstrated potential of superconducting rf technology, beams of exceptional quality and flexibility can be obtained. The proposed system is designed to provide beams with tandem-like energy resolution and ease of energy variation, and the energy range is comparable to that of a approx. 50 MV tandem. In addition, the beam will be bunched into very short (approx. 50 psec) pulses, permitting fast-timing measurements that can open up major new experimental approaches

The big and little of fifty years of Moessbauer spectroscopy at Argonne

International Nuclear Information System (INIS)

Westfall, C.

2005-01-01

Using radioactive materials obtained by chance, a turntable employing gears from Heidelberg's mechanical toy shops, and other minimal equipment available in post World War II Germany, in 1959 Rudolf Moessbauer confirmed his suspicion that his graduate research had yielded ground-breaking results. He published his conclusion: an atomic nucleus in a crystal undergoes negligible recoil when it emits a low energy gamma ray and provides the entire energy to the gamma ray. In the beginning Moessbauer's news might have been dismissed. As Argonne nuclear physicist Gilbert Perlow noted: ''Everybody knew that nuclei were supposed to recoil when emitting gamma rays--people made those measurements every day''. If any such effect existed, why had no one noticed it before? The notion that some nuclei would not recoil was ''completely crazy'', in the words of the eminent University of Illinois condensed matter physicist Frederich Seitz. Intrigued, however, nuclear physicists as well as condensed matter (or solid state) physicists in various locations--but particularly at the Atomic Energy Research Establishment at Harwell in Britain and at Argonne and Los Alamos in the U.S.--found themselves pondering the Moessbauer spectra with its nuclear and solid state properties starting in late 1959. After an exciting year during which Moessbauer's ideas were confirmed and extended, the physics community concluded that Moessbauer was right. Moessbauer won the Nobel Prize for his work in 1961. In the 1960s and 1970s Argonne physicists produced an increasingly clear picture of the properties of matter using the spectroscopy ushered in by Moessbauer. The scale of this traditional Moessbauer spectroscopy, which required a radioactive source and other simple equipment, began quite modestly by Argonne standards. For example Argonne hosted traditional Moessbauer spectroscopy research using mostly existing equipment in the early days and equipment that cost $100,000 by the 1970s alongside work at

The big and little of fifty years of Moessbauer spectroscopy at Argonne.

Energy Technology Data Exchange (ETDEWEB)

Westfall, C.

2005-09-20

Using radioactive materials obtained by chance, a turntable employing gears from Heidelberg's mechanical toy shops, and other minimal equipment available in post World War II Germany, in 1959 Rudolf Moessbauer confirmed his suspicion that his graduate research had yielded ground-breaking results. He published his conclusion: an atomic nucleus in a crystal undergoes negligible recoil when it emits a low energy gamma ray and provides the entire energy to the gamma ray. In the beginning Moessbauer's news might have been dismissed. As Argonne nuclear physicist Gilbert Perlow noted: ''Everybody knew that nuclei were supposed to recoil when emitting gamma rays--people made those measurements every day''. If any such effect existed, why had no one noticed it before? The notion that some nuclei would not recoil was ''completely crazy'', in the words of the eminent University of Illinois condensed matter physicist Frederich Seitz. Intrigued, however, nuclear physicists as well as condensed matter (or solid state) physicists in various locations--but particularly at the Atomic Energy Research Establishment at Harwell in Britain and at Argonne and Los Alamos in the U.S.--found themselves pondering the Moessbauer spectra with its nuclear and solid state properties starting in late 1959. After an exciting year during which Moessbauer's ideas were confirmed and extended, the physics community concluded that Moessbauer was right. Moessbauer won the Nobel Prize for his work in 1961. In the 1960s and 1970s Argonne physicists produced an increasingly clear picture of the properties of matter using the spectroscopy ushered in by Moessbauer. The scale of this traditional Moessbauer spectroscopy, which required a radioactive source and other simple equipment, began quite modestly by Argonne standards. For example Argonne hosted traditional Moessbauer spectroscopy research using mostly existing equipment in the early days and

Noise reduction techniques used on the high power klystron modulators at Argonne National Laboratory

International Nuclear Information System (INIS)

Russell, T.J.

1993-01-01

The modulators used in the Advanced Photon Source at Argonne National Laboratory have been redesigned with an emphasis on electrical noise reduction. Since the modulators are 100 MW modulators with <700 ns rise time, electrical noise can be coupled very easily to other electronic equipment in the area. This paper will detail the efforts made to reduce noise coupled to surrounding equipment. Shielding and sound grounding techniques accomplished the goal of drastically reducing the noise induced in surrounding equipment. The approach used in grounding and shielding will be discussed, and data will be presented comparing earlier designs to the improved design

Draft environmental assessment of Argonne National Laboratory, East

Energy Technology Data Exchange (ETDEWEB)

1975-10-01

This environmental assessment of the operation of the Argonne National Laboratory is related to continuation of research and development work being conducted at the Laboratory site at Argonne, Illinois. The Laboratory has been monitoring various environmental parameters both offsite and onsite since 1949. Meteorological data have been collected to support development of models for atmospheric dispersion of radioactive and other pollutants. Gaseous and liquid effluents, both radioactive and non-radioactive, have been measured by portable monitors and by continuous monitors at fixed sites. Monitoring of constituents of the terrestrial ecosystem provides a basis for identifying changes should they occur in this regime. The Laboratory has established a position of leadership in monitoring methodologies and their application. Offsite impacts of nonradiological accidents are primarily those associated with the release of chlorine and with sodium fires. Both result in releases that cause no health damage offsite. Radioactive materials released to the environment result in a cumulative dose to persons residing within 50 miles of the site of about 47 man-rem per year, compared to an annual total of about 950,000 man-rem delivered to the same population from natural background radiation. 100 refs., 17 figs., 33 tabs.

How Argonne's Intense Pulsed Neutron Source came to life and gained its niche : the view from an ecosystem perspective

International Nuclear Information System (INIS)

Westfall, C.

2008-01-01

At first glance the story of the Intense Pulsed Neutron Source (IPNS) at Argonne National Laboratory (ANL) appears to have followed a puzzling course. When researchers first proposed their ideas for an accelerator-driven neutron source for exploring the structure of materials through neutron scattering, the project seemed so promising that both Argonne managers and officials at the laboratory's funding agency, the Department of Energy (DOE), suggested that it be made larger and more expensive. But then, even though prototype building, testing, and initial construction went well a group of prominent DOE reviewers recommended in fall 1980 that it be killed, just months before it had been slated to begin operation, and DOE promptly accepted the recommendation. In response, Argonne's leadership declared the project was the laboratory's top priority and rallied to save it. In late 1982, thanks to another review panel led by the same scientist who had chaired the panel that had delivered the death sentence, the project was granted a reprieve. However, by the late 1980s, the IPNS was no longer top priority within the international materials science community, at Argonne, or within the DOE budget because prospects for another, larger materials science accelerator emerged. At just this point, the facility started to produce exciting scientific results. For the next two decades, the IPNS, its research, and its experts became valued resources at Argonne, within the U.S. national laboratory system, and within the international materials science community. Why did this Argonne project prosper and then almost suffer premature death, even though it promised (and later delivered) good science? How was it saved and how did it go on to have a long, prosperous life for more than a quarter of a century? In particular, what did an expert assessment of the quality of IPNS science have to do with its fate? Getting answers to such questions is important. The U.S. government spends a lot

GRAPHIC, time-sharing magnet design computer programs at Argonne

International Nuclear Information System (INIS)

Lari, R.J.

1974-01-01

This paper describes three magnet design computer programs in use at the Zero Gradient Synchrotron of Argonne National Laboratory. These programs are used in the time sharing mode in conjunction with a Tektronix model 4012 graphic display terminal. The first program in called TRIM, the second MAGNET, and the third GFUN. (U.S.)

Argonne Bubble Experiment Thermal Model Development II

Energy Technology Data Exchange (ETDEWEB)

Buechler, Cynthia Eileen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-07-01

This report describes the continuation of the work reported in “Argonne Bubble Experiment Thermal Model Development”. The experiment was performed at Argonne National Laboratory (ANL) in 2014. A rastered 35 MeV electron beam deposited power in a solution of uranyl sulfate, generating heat and radiolytic gas bubbles. Irradiations were performed at three beam power levels, 6, 12 and 15 kW. Solution temperatures were measured by thermocouples, and gas bubble behavior was observed. This report will describe the Computational Fluid Dynamics (CFD) model that was developed to calculate the temperatures and gas volume fractions in the solution vessel during the irradiations. The previous report described an initial analysis performed on a geometry that had not been updated to reflect the as-built solution vessel. Here, the as-built geometry is used. Monte-Carlo N-Particle (MCNP) calculations were performed on the updated geometry, and these results were used to define the power deposition profile for the CFD analyses, which were performed using Fluent, Ver. 16.2. CFD analyses were performed for the 12 and 15 kW irradiations, and further improvements to the model were incorporated, including the consideration of power deposition in nearby vessel components, gas mixture composition, and bubble size distribution. The temperature results of the CFD calculations are compared to experimental measurements.

Cooling systems research at Argonne National Laboratory

International Nuclear Information System (INIS)

Spigarelli, S.A.

1977-01-01

Studies of the thermal plumes resulting from discharges from once-through cooling systems of electric generating stations are reviewed. The collection of large amounts of water temperature data for definition of the three-dimensional structure of a thermal plume, of current data, and related ambient data for model evaluation purposes required the development of an integrated data collection system. The Argonne system employs measurements of water temperature over the water column from a moving small boat. Temperatures are measured with thermistors attached to a rigid strut for surface plumes and to a flexible, faired cable for submerged plumes. Water temperatures and boat location, determined by a microwave ranging system, are recorded on magnetic tape while the boat is underway and prove a quasi-synoptic map of plume temperatures. Automated data handling and processing procedures provide for the production of isotherm maps of the plume at several elevations and in cross section. Mathematical model evaluation for surface discharges of waste heat included the consideration of over 40 different models and detailed evaluation of 11 models. Most models were run on Argonne's computers, and all models were evaluated in terms of their limitations and capabilities as well as their predictive performance against prototype data. Measurements were made of thermal plumes at the discharges of nuclear power plants located on the shores of Lake Michigan

76 FR 28214 - UChicago Argonne, LLC, et al.; Notice of Decision on Applications for Duty-Free Entry of...

Science.gov (United States)

2011-05-16

... DEPARTMENT OF COMMERCE International Trade Administration UChicago Argonne, LLC, et al.; Notice of.... Applicant: UChicago Argonne, LLC, Lemont, IL 60439. Instrument: Mythen 1K Detector System. Manufacturer... instrument will be used for resonant inelastic x-ray scattering (RIXS) to study the electronic structure of...

Script for Argonne lithium process video

International Nuclear Information System (INIS)

1995-01-01

Approximately 2700 metric tons of spent nuclear fuel, representing over 40 years of reactor research and development, has accumulated within the DOE complex. This fuel reflects the varied purposes of DOE reactors and covers a wide range of composition, enrichment, cladding, and chemical reactivity. The varied nature of these fuels complicates their long term disposal. To attempt to individually qualify each type for disposal in a repository would be prohibitively expensive. The electrometallurgical treatment technique, developed by Argonne National Laboratory, is designed to homogenize the wide variety of spent fuel types into a single set of acceptable disposal forms

Brookhaven Lab and Argonne Lab scientists invent a plasma valve

CERN Multimedia

2003-01-01

Scientists from Brookhaven National Laboratory and Argonne National Laboratory have received U.S. patent number 6,528,948 for a device that shuts off airflow into a vacuum about one million times faster than mechanical valves or shutters that are currently in use (1 page).

Argonne National Laboratory annual report of Laboratory Directed Research and Development Program Activities FY 2009.

Energy Technology Data Exchange (ETDEWEB)

Office of the Director

2010-04-09

I am pleased to submit Argonne National Laboratory's Annual Report on its Laboratory Directed Research and Development (LDRD) activities for fiscal year 2009. Fiscal year 2009 saw a heightened focus by DOE and the nation on the need to develop new sources of energy. Argonne scientists are investigating many different sources of energy, including nuclear, solar, and biofuels, as well as ways to store, use, and transmit energy more safely, cleanly, and efficiently. DOE selected Argonne as the site for two new Energy Frontier Research Centers (EFRCs) - the Institute for Atom-Efficient Chemical Transformations and the Center for Electrical Energy Storage - and funded two other EFRCs to which Argonne is a major partner. The award of at least two of the EFRCs can be directly linked to early LDRD-funded efforts. LDRD has historically seeded important programs and facilities at the lab. Two of these facilities, the Advanced Photon Source and the Center for Nanoscale Materials, are now vital contributors to today's LDRD Program. New and enhanced capabilities, many of which relied on LDRD in their early stages, now help the laboratory pursue its evolving strategic goals. LDRD has, since its inception, been an invaluable resource for positioning the Laboratory to anticipate, and thus be prepared to contribute to, the future science and technology needs of DOE and the nation. During times of change, LDRD becomes all the more vital for facilitating the necessary adjustments while maintaining and enhancing the capabilities of our staff and facilities. Although I am new to the role of Laboratory Director, my immediate prior service as Deputy Laboratory Director for Programs afforded me continuous involvement in the LDRD program and its management. Therefore, I can attest that Argonne's program adhered closely to the requirements of DOE Order 413.2b and associated guidelines governing LDRD. Our LDRD program management continually strives to be more efficient. In

Argonne National Laboratory annual report of Laboratory Directed Research and Development Program Activities FY 2009

International Nuclear Information System (INIS)

2010-01-01

I am pleased to submit Argonne National Laboratory's Annual Report on its Laboratory Directed Research and Development (LDRD) activities for fiscal year 2009. Fiscal year 2009 saw a heightened focus by DOE and the nation on the need to develop new sources of energy. Argonne scientists are investigating many different sources of energy, including nuclear, solar, and biofuels, as well as ways to store, use, and transmit energy more safely, cleanly, and efficiently. DOE selected Argonne as the site for two new Energy Frontier Research Centers (EFRCs) - the Institute for Atom-Efficient Chemical Transformations and the Center for Electrical Energy Storage - and funded two other EFRCs to which Argonne is a major partner. The award of at least two of the EFRCs can be directly linked to early LDRD-funded efforts. LDRD has historically seeded important programs and facilities at the lab. Two of these facilities, the Advanced Photon Source and the Center for Nanoscale Materials, are now vital contributors to today's LDRD Program. New and enhanced capabilities, many of which relied on LDRD in their early stages, now help the laboratory pursue its evolving strategic goals. LDRD has, since its inception, been an invaluable resource for positioning the Laboratory to anticipate, and thus be prepared to contribute to, the future science and technology needs of DOE and the nation. During times of change, LDRD becomes all the more vital for facilitating the necessary adjustments while maintaining and enhancing the capabilities of our staff and facilities. Although I am new to the role of Laboratory Director, my immediate prior service as Deputy Laboratory Director for Programs afforded me continuous involvement in the LDRD program and its management. Therefore, I can attest that Argonne's program adhered closely to the requirements of DOE Order 413.2b and associated guidelines governing LDRD. Our LDRD program management continually strives to be more efficient. In addition to

Alpha-Gamma Hot-Cell Facility at Argonne National Laboratory East

International Nuclear Information System (INIS)

Neimark, L.A.; Jackson, W.D.; Donahue, D.A.

1979-01-01

The Alpha-Gamma Hot-Cell Facility has been in operation at Argonne National Laboratory East (ANL-E) for 15 years. The facility was designed for plutonium research in support of ANL's LMFBR program. The facility consists of a kilocurie, nitrogen-atmosphere alpha-gamma hot cell and supporting laboratories. Modifications to the facility and its equipment have been made over the years as the workload and nature of the work changed. These modifications included inerting the entire hot cell, adding four work stations, modifying in-loading procedures and examination equipment to handle longer test articles, and changing to a new sodium-vapor lighting system. Future upgrading includes the addition of a decontamination and repair facility, use of radio-controlled transfer carts, refurbishment of the zinc bromide windows, and the installation of an Auger microprobe

Argonne National Laboratory research to help U.S. steel industry

CERN Multimedia

2003-01-01

Argonne National Laboratory has joined a $1.29 million project to develop technology software that will use advanced computational fluid dynamics (CFD), a method of solving fluid flow and heat transfer problems. This technology allows engineers to evaluate and predict erosion patterns within blast furnaces (1 page).

Around the laboratories: Dubna: Physics results and progress on bubble chamber techniques; Stanford (SLAC): Operation of a very rapid cycling bubble chamber; Daresbury: Photographs of visitors to the Laboratory; Argonne: Charge exchange injection tests into the ZGS in preparation for a proposed Booster

CERN Multimedia

1969-01-01

Around the laboratories: Dubna: Physics results and progress on bubble chamber techniques; Stanford (SLAC): Operation of a very rapid cycling bubble chamber; Daresbury: Photographs of visitors to the Laboratory; Argonne: Charge exchange injection tests into the ZGS in preparation for a proposed Booster

Argonne National Laboratory Publications July 1, 1968 - June 30, 1969.

Energy Technology Data Exchange (ETDEWEB)

None, None

1969-08-01

This publication list is a bibliography of scientific and technical accounts originated at Argonne and published during the fiscal year 1969 (July 1, 1968 through June 30, 1969). It includes items published as journal articles, technical reports, books, etc., all of which have been made available to the public.

Argonne's Laboratory Computing Resource Center 2009 annual report.

Energy Technology Data Exchange (ETDEWEB)

Bair, R. B. (CLS-CI)

2011-05-13

Now in its seventh year of operation, the Laboratory Computing Resource Center (LCRC) continues to be an integral component of science and engineering research at Argonne, supporting a diverse portfolio of projects for the U.S. Department of Energy and other sponsors. The LCRC's ongoing mission is to enable and promote computational science and engineering across the Laboratory, primarily by operating computing facilities and supporting high-performance computing application use and development. This report describes scientific activities carried out with LCRC resources in 2009 and the broad impact on programs across the Laboratory. The LCRC computing facility, Jazz, is available to the entire Laboratory community. In addition, the LCRC staff provides training in high-performance computing and guidance on application usage, code porting, and algorithm development. All Argonne personnel and collaborators are encouraged to take advantage of this computing resource and to provide input into the vision and plans for computing and computational analysis at Argonne. The LCRC Allocations Committee makes decisions on individual project allocations for Jazz. Committee members are appointed by the Associate Laboratory Directors and span a range of computational disciplines. The 350-node LCRC cluster, Jazz, began production service in April 2003 and has been a research work horse ever since. Hosting a wealth of software tools and applications and achieving high availability year after year, researchers can count on Jazz to achieve project milestones and enable breakthroughs. Over the years, many projects have achieved results that would have been unobtainable without such a computing resource. In fiscal year 2009, there were 49 active projects representing a wide cross-section of Laboratory research and almost all research divisions.

Optimizing recoil-isomer tagging with the Argonne fragment mass analyzer

International Nuclear Information System (INIS)

Garnsworthy, A.B.; Lister, C.J.; Regan, P.H.; Blank, B.B.; Cullen, I.J.; Gros, S.; Henderson, D.J.; Jones, G.A.; Liu, Z.; Seweryniak, D.; Shumard, B.R.; Thompson, N.J.; Williams, S.J.; Zhu, S.

2008-01-01

A new focal plane detector arrangement for the Fragment Mass Analyzer (FMA) has been built and tested at Argonne National Laboratory. This set-up is particularly sensitive for performing Recoil-Isomer Tagging on nuclei with isomeric states with lifetimes in the microsecond range. Recoiling nuclei from fusion-evaporation reactions at the target position are dispersed by their ratio of mass to charge (A/q) by the FMA and stopped in low pressure gas (air) at the focal plane. Subsequent gamma decays from isomeric states in the reaction products are observed using Ge detectors. A constant gas flow through the focal plane chamber efficiently removes longer-lived beta-decaying species from sight of the detectors. This set-up has been commissioned successfully with the microsecond isomer in 80 Rb, populated via the 52 Cr( 32 S, 3pn) reaction at 135 MeV

Argonne National Laboratory 1986 publications

International Nuclear Information System (INIS)

Kopta, J.A.; Springer, C.J.

1987-12-01

This report is a bibliography of scientific and technical 1986 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1986. This compilation, prepared by the Technical Information Services Technical Publications Section (TPS), lists all nonrestricted 1986 publications submitted to TPS by the Laboratory's Divisions. Author indexes list ANL authors only. If a first author is not an ANL employee, an asterisk in the bibliographic citation indicates the first ANL author. The report is divided into seven parts: Journal Articles -- Listed by first author; ANL Reports -- Listed by report number; ANL and non-ANL Unnumbered Reports -- Listed by report number; Non-ANL Numbered Reports -- Listed by report number; Books and Book Chapters -- Listed by first author; Conference Papers -- Listed by first author; and Complete Author Index

Argonne National Laboratory 1986 publications

Energy Technology Data Exchange (ETDEWEB)

Kopta, J.A.; Springer, C.J.

1987-12-01

This report is a bibliography of scientific and technical 1986 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1986. This compilation, prepared by the Technical Information Services Technical Publications Section (TPS), lists all nonrestricted 1986 publications submitted to TPS by the Laboratory's Divisions. Author indexes list ANL authors only. If a first author is not an ANL employee, an asterisk in the bibliographic citation indicates the first ANL author. The report is divided into seven parts: Journal Articles -- Listed by first author; ANL Reports -- Listed by report number; ANL and non-ANL Unnumbered Reports -- Listed by report number; Non-ANL Numbered Reports -- Listed by report number; Books and Book Chapters -- Listed by first author; Conference Papers -- Listed by first author; and Complete Author Index.

How Argonne's Intense Pulsed Neutron Source came to life and gained its niche : the view from an ecosystem perspective.

Energy Technology Data Exchange (ETDEWEB)

Westfall, C.; Office of The Director

2008-02-25

At first glance the story of the Intense Pulsed Neutron Source (IPNS) at Argonne National Laboratory (ANL) appears to have followed a puzzling course. When researchers first proposed their ideas for an accelerator-driven neutron source for exploring the structure of materials through neutron scattering, the project seemed so promising that both Argonne managers and officials at the laboratory's funding agency, the Department of Energy (DOE), suggested that it be made larger and more expensive. But then, even though prototype building, testing, and initial construction went well a group of prominent DOE reviewers recommended in fall 1980 that it be killed, just months before it had been slated to begin operation, and DOE promptly accepted the recommendation. In response, Argonne's leadership declared the project was the laboratory's top priority and rallied to save it. In late 1982, thanks to another review panel led by the same scientist who had chaired the panel that had delivered the death sentence, the project was granted a reprieve. However, by the late 1980s, the IPNS was no longer top priority within the international materials science community, at Argonne, or within the DOE budget because prospects for another, larger materials science accelerator emerged. At just this point, the facility started to produce exciting scientific results. For the next two decades, the IPNS, its research, and its experts became valued resources at Argonne, within the U.S. national laboratory system, and within the international materials science community. Why did this Argonne project prosper and then almost suffer premature death, even though it promised (and later delivered) good science? How was it saved and how did it go on to have a long, prosperous life for more than a quarter of a century? In particular, what did an expert assessment of the quality of IPNS science have to do with its fate? Getting answers to such questions is important. The U.S. government

Status of Data Base Management Systems at Argonne National Laboratory

International Nuclear Information System (INIS)

Fuja, P.M.; Lindeman, A.J.

1978-01-01

Argonne National Laboratory has been using the System 2000 data base management system for the past two years. It has been used for technical as well as administrative applications. This paper describes some of the experience gained relating to advantages and disadvantages of data base management systems as well as of System 2000 in particular

Flood-hazard analysis of four headwater streams draining the Argonne National Laboratory property, DuPage County, Illinois

Science.gov (United States)

Soong, David T.; Murphy, Elizabeth A.; Straub, Timothy D.; Zeeb, Hannah L.

2016-11-22

Results of a flood-hazard analysis conducted by the U.S. Geological Survey, in cooperation with the Argonne National Laboratory, for four headwater streams within the Argonne National Laboratory property indicate that the 1-percent and 0.2-percent annual exceedance probability floods would cause multiple roads to be overtopped. Results indicate that most of the effects on the infrastructure would be from flooding of Freund Brook. Flooding on the Northeast and Southeast Drainage Ways would be limited to overtopping of one road crossing for each of those streams. The Northwest Drainage Way would be the least affected with flooding expected to occur in open grass or forested areas.The Argonne Site Sustainability Plan outlined the development of hydrologic and hydraulic models and the creation of flood-plain maps of the existing site conditions as a first step in addressing resiliency to possible climate change impacts as required by Executive Order 13653 “Preparing the United States for the Impacts of Climate Change.” The Hydrological Simulation Program-FORTRAN is the hydrologic model used in the study, and the Hydrologic Engineering Center‒River Analysis System (HEC–RAS) is the hydraulic model. The model results were verified by comparing simulated water-surface elevations to observed water-surface elevations measured at a network of five crest-stage gages on the four study streams. The comparison between crest-stage gage and simulated elevations resulted in an average absolute difference of 0.06 feet and a maximum difference of 0.19 feet.In addition to the flood-hazard model development and mapping, a qualitative stream assessment was conducted to evaluate stream channel and substrate conditions in the study reaches. This information can be used to evaluate erosion potential.

Argonne National Laboratory Annual Report of Laboratory Directed Research and Development program activities FY 2011.

Energy Technology Data Exchange (ETDEWEB)

(Office of The Director)

2012-04-25

As a national laboratory Argonne concentrates on scientific and technological challenges that can only be addressed through a sustained, interdisciplinary focus at a national scale. Argonne's eight major initiatives, as enumerated in its strategic plan, are Hard X-ray Sciences, Leadership Computing, Materials and Molecular Design and Discovery, Energy Storage, Alternative Energy and Efficiency, Nuclear Energy, Biological and Environmental Systems, and National Security. The purposes of Argonne's Laboratory Directed Research and Development (LDRD) Program are to encourage the development of novel technical concepts, enhance the Laboratory's research and development (R and D) capabilities, and pursue its strategic goals. projects are selected from proposals for creative and innovative R and D studies that require advance exploration before they are considered to be sufficiently developed to obtain support through normal programmatic channels. Among the aims of the projects supported by the LDRD Program are the following: establishment of engineering proof of principle, assessment of design feasibility for prospective facilities, development of instrumentation or computational methods or systems, and discoveries in fundamental science and exploratory development.

Argonne National Laboratory Annual Report of Laboratory Directed Research and Development program activities FY 2010.

Energy Technology Data Exchange (ETDEWEB)

(Office of The Director)

2012-04-25

As a national laboratory Argonne concentrates on scientific and technological challenges that can only be addressed through a sustained, interdisciplinary focus at a national scale. Argonne's eight major initiatives, as enumerated in its strategic plan, are Hard X-ray Sciences, Leadership Computing, Materials and Molecular Design and Discovery, Energy Storage, Alternative Energy and Efficiency, Nuclear Energy, Biological and Environmental Systems, and National Security. The purposes of Argonne's Laboratory Directed Research and Development (LDRD) Program are to encourage the development of novel technical concepts, enhance the Laboratory's research and development (R and D) capabilities, and pursue its strategic goals. projects are selected from proposals for creative and innovative R and D studies that require advance exploration before they are considered to be sufficiently developed to obtain support through normal programmatic channels. Among the aims of the projects supported by the LDRD Program are the following: establishment of engineering proof of principle, assessment of design feasibility for prospective facilities, development of instrumentation or computational methods or systems, and discoveries in fundamental science and exploratory development.

Radioactive target and source development at Argonne National Laboratory

International Nuclear Information System (INIS)

Greene, J.P.; Ahmad, I.; Thomas, G.E.

1992-01-01

An increased demand for low-level radioactive targets has created the need for a laboratory dedicated to the production of these foils. A description is given of the radioactive target produced as well as source development work being performed at the Physics Division target facility of Argonne National Laboratory (ANL). Highlights include equipment used and the techniques employed. In addition, some examples of recent source preparation are given as well as work currently in progress

Results from the Argonne, Los Alamos, JAERI collaboration

Energy Technology Data Exchange (ETDEWEB)

Meadows, J.; Smith, D.; Greenwood, L. [Argonne National Lab., IL (United States); Haight, R. [Los Alamos National Lab., NM (United States); Ikeda, Y.; Konno, C. [Japan Atomic Energy Research Inst., Ibaraki (Japan)

1993-07-01

Four sample packets containing elemental Ti, Fe, Ni, Cu, Nb, Ag, Eu, Tb and Hf have been irradiated in three distinct accelerator neutron fields, at Argonne National Laboratory and Los Alamos National Laboratory, USA, and Japan Atomic Energy Research Institute, Tokai, Japan. The acquired experimental data include differential cross sections and integral cross sections for the continuum neutron spectrum produced by 7-MeV deuterons incident on thick Be-metal target. The U-238(n,f) cross section was also measured at 10.3 MeV as a consistency check on the experimental technique. This the third progress report on a project which has been carried out under the auspices of an IAEA Coordinated Research Program entitled ``Activation Cross Sections for the Generation Of Long-lived Radionuclides of Importance in Fusion Reactor Technology``. The present report provides the latest results from this work. Comparison is made between the 14.7-MeV cross-section values obtained from the separate investigations at Argonne and JAERI. Generally, good agreement observed within the experimental errors when consistent sample parameters, radioactivity decay data and reference cross values are employed. A comparison is also made between the experimental results and those derived from calculations using a nuclear model. Experimental neutron information on the Be(d,n) neutron spectrum was incorporated in the comparisons for the integral results. The agreement is satisfactory considering the various uncertainties that are involved.

ASPUN: design for an Argonne super-intense pulsed neutron source

International Nuclear Information System (INIS)

Khoe, T.K.; Kustom, R.L.

1983-01-01

Argonne pioneered the pulsed spallation neutron source with the ZING-P and IPNS-I concepts. IPNS-I is now a reliable and actively used source for pulsed spallation neutrons. The accelerator is a 500-MeV, 8 to 9 μa, 30-Hz rapid-cycling proton synchrotron. Other proton spallation sources are now in operation or in construction. These include KENS-I at the National Laboratory for High Energy Physics in Japan, the WNR/PSR at Los Alamos National Laboratory in the USA, and the SNS at the Rutherford Appleton Laboratory in England. Newer and bolder concepts are being developed for more-intense pulsed spallation neutron sources. These include SNQ at the KFA Laboratory in Juelich, Germany, ASTOR at the Swiss Institute for Nuclear Physics in Switzerland, and ASPUN, the Argonne concept. ASPUN is based on the Fixed-Field Alternating Gradient concept. The design goal is to provide a time-averaged beam of 3.5 ma at 1100 MeV on a spallation target in intense bursts, 100 to 200 nanoseconds long, at a repetition rate of no more than 60 to 85 Hz

Treatment of mixed radioactive liquid wastes at Argonne National Laboratory

International Nuclear Information System (INIS)

Vandegrift, G.F.; Chamberlain, D.B.; Conner, C.

1994-01-01

Aqueous mixed waste at Argonne National Laboratory (ANL) is traditionally generated in small volumes with a wide variety of compositions. A cooperative effort at ANL between Waste Management (WM) and the Chemical Technology Division (CMT) was established, to develop, install, and implement a robust treatment operation to handle the majority of such wastes. For this treatment, toxic metals in mixed-waste solutions are precipitated in a semiautomated system using Ca(OH) 2 and, for some metals, Na 2 S additions. This step is followed by filtration to remove the precipitated solids. A filtration skid was built that contains several filter types which can be used, as appropriate, for a variety of suspended solids. When supernatant liquid is separated from the toxic-metal solids by decantation and filtration, it will be a low-level waste (LLW) rather than a mixed waste. After passing a Toxicity Characteristic Leaching Procedure (TCLP) test, the solids may also be treated as LLW

Atomic physics at the Argonne PII ECR [electron cyclotron resonance] Ion Source

International Nuclear Information System (INIS)

Dunford, R.W.; Berry, H.G.; Billquist, P.J.; Pardo, R.C.; Zabransky, B.J.; Bakke, E.; Groeneveld, K.O.; Hass, M.; Raphaelian, M.L.A.

1987-01-01

An atomic physics beam line has been set up at the Argonne PII ECR Ion Source. The source is on a 350-kV high-voltage platform which is a unique feature of particular interest in work on atomic collisions. We describe our planned experimental program which includes: measurement of state-selective electron-capture cross sections, studies of doubly-excited states, precision spectroscopy of few-electron ions, tests of quantum electrodynamics, and studies of polarization transfer using optically pumped polarized alkali targets. The first experiments will be measurements of cross sections for electron capture into specific nl subshells in ion-atom collisions. Our method is to observe the characteristic radiation emitted after capture using a VUV spectrometer. Initial data from these experiments are presented. 12 refs., 4 figs

Around the laboratories: Rutherford: Successful tests on bubble chamber target technique; Stanford (SLAC): New storage rings proposal; Berkeley: The HAPPE project to examine cosmic rays with superconducting magnets; The 60th birthday of Professor N.N. Bogolyubov; Argonne: Performance of the automatic film measuring system POLLY II

CERN Multimedia

1969-01-01

Around the laboratories: Rutherford: Successful tests on bubble chamber target technique; Stanford (SLAC): New storage rings proposal; Berkeley: The HAPPE project to examine cosmic rays with superconducting magnets; The 60th birthday of Professor N.N. Bogolyubov; Argonne: Performance of the automatic film measuring system POLLY II

Argonne National Laboratory-East site environmental report for calendar year 1995

Energy Technology Data Exchange (ETDEWEB)

Golchert, N.W.; Kolzow, R.G. [Environmental Management Operation, Argonne National Lab., IL (United States)

1996-09-01

This report presents the environmental report for the Argonne National Laboratory-East for the year of 1995. Topics discussed include: general description of the site including climatology, geology, seismicity, hydrology, vegetation, endangered species, population, water and land use, and archaeology; compliance summary; environmental program information; environmental nonradiological program information; ground water protection; and radiological monitoring program.

The Argonne Leadership Computing Facility 2010 annual report.

Energy Technology Data Exchange (ETDEWEB)

Drugan, C. (LCF)

2011-05-09

Researchers found more ways than ever to conduct transformative science at the Argonne Leadership Computing Facility (ALCF) in 2010. Both familiar initiatives and innovative new programs at the ALCF are now serving a growing, global user community with a wide range of computing needs. The Department of Energy's (DOE) INCITE Program remained vital in providing scientists with major allocations of leadership-class computing resources at the ALCF. For calendar year 2011, 35 projects were awarded 732 million supercomputer processor-hours for computationally intensive, large-scale research projects with the potential to significantly advance key areas in science and engineering. Argonne also continued to provide Director's Discretionary allocations - 'start up' awards - for potential future INCITE projects. And DOE's new ASCR Leadership Computing (ALCC) Program allocated resources to 10 ALCF projects, with an emphasis on high-risk, high-payoff simulations directly related to the Department's energy mission, national emergencies, or for broadening the research community capable of using leadership computing resources. While delivering more science today, we've also been laying a solid foundation for high performance computing in the future. After a successful DOE Lehman review, a contract was signed to deliver Mira, the next-generation Blue Gene/Q system, to the ALCF in 2012. The ALCF is working with the 16 projects that were selected for the Early Science Program (ESP) to enable them to be productive as soon as Mira is operational. Preproduction access to Mira will enable ESP projects to adapt their codes to its architecture and collaborate with ALCF staff in shaking down the new system. We expect the 10-petaflops system to stoke economic growth and improve U.S. competitiveness in key areas such as advancing clean energy and addressing global climate change. Ultimately, we envision Mira as a stepping-stone to exascale-class computers

Study of Second Phase Particles and Fe content in Zr Alloys Using the Advanced Photon Source at Argonne

Energy Technology Data Exchange (ETDEWEB)

Arthur T. Motta

2001-11-07

We have conducted a study of second phase particles and matrix alloying element concentrations in zirconium alloys using synchrotron radiation from the Advanced Photon Source (APS) at Argonne National Laboratory. The high flux of synchrotron radiation delivered at the 2BM beamline compared to conventional x-ray generators, enables the detection of very small precipitate volume fractions. We detected the standard C14 hcp Zr(Cr,Fe)2 precipitates, (the stable second phase in Zircaloy-4) in the bulk material at a cumulative annealing parameter as low as 10-20 h, and we followed the kinetics of precipitation and growth as a function of the cumulative annealing parameter (CAP) in the range 10-22 (quench) to 10-16 h. In addition, the unique combination of spatial resolution and elemental sensitivity of the 2ID-D/E microbeam line at the Advanced Photon Source at Argonne (APS) allows study of the alloying element concentrations at ppm levels in an area as small as 0.2 mm. We used x-ray fluorescence induced by this sub-micron x-ray beam to determine the concentration of these alloying elements in the matrix as a function of alloy type and thermal history. We discuss these results and the potential of synchrotron radiation-based techniques for studying zirconium alloys.

Study of Second Phase Particles and Fe content in Zr Alloys Using the Advanced Photon Source at Argonne

International Nuclear Information System (INIS)

Motta, Arthur T.

2001-01-01

We have conducted a study of second phase particles and matrix alloying element concentrations in zirconium alloys using synchrotron radiation from the Advanced Photon Source (APS) at Argonne National Laboratory. The high flux of synchrotron radiation delivered at the 2BM beamline compared to conventional x-ray generators, enables the detection of very small precipitate volume fractions. We detected the standard C14 hcp Zr(Cr,Fe)2 precipitates, (the stable second phase in Zircaloy-4) in the bulk material at a cumulative annealing parameter as low as 10-20 h, and we followed the kinetics of precipitation and growth as a function of the cumulative annealing parameter (CAP) in the range 10-22 (quench) to 10-16 h. In addition, the unique combination of spatial resolution and elemental sensitivity of the 2ID-D/E microbeam line at the Advanced Photon Source at Argonne (APS) allows study of the alloying element concentrations at ppm levels in an area as small as 0.2 mm. We used x-ray fluorescence induced by this sub-micron x-ray beam to determine the concentration of these alloying elements in the matrix as a function of alloy type and thermal history. We discuss these results and the potential of synchrotron radiation-based techniques for studying zirconium alloys

Reactor D and D at Argonne National Laboratory - lessons learned

International Nuclear Information System (INIS)

Fellhauer, C. R.

1998-01-01

This paper focuses on the lessons learned during the decontamination and decommissioning (D and D) of two reactors at Argonne National Laboratory-East (ANL-E). The Experimental Boiling Water Reactor (EBWR) was a 100 MW(t), 5 MSV(e) proof-of-concept facility. The Janus Reactor was a 200 kW(t) reactor located at the Biological Irradiation Facility and was used to study the effects of neutron radiation on animals

Frequency selective bolometer development at Argonne National Laboratory

Science.gov (United States)

Datesman, Aaron; Pearson, John; Wang, Gensheng; Yefremenko, Volodymyr; Divan, Ralu; Downes, Thomas; Chang, Clarence; McMahon, Jeff; Meyer, Stephan; Carlstrom, John; Logan, Daniel; Perera, Thushara; Wilson, Grant; Novosad, Valentyn

2008-07-01

We discuss the development, at Argonne National Laboratory, of a four-pixel camera suitable for photometry of distant dusty galaxies located by Spitzer and SCUBA, and for study of other millimeter-wave sources such as ultra-luminous infrared galaxies, the Sunyaev-Zeldovich (SZ) effect in clusters, and galactic dust. Utilizing Frequency Selective Bolometers (FSBs) with superconducting Transition-Edge Sensors (TESs), each of the camera's four pixels is sensitive to four colors, with frequency bands centered approximately at 150, 220, 270, and 360 GHz. The current generation of these devices utilizes proximity effect superconducting bilayers of Mo/Au or Ti/Au for TESs, along with frequency selective circuitry on membranes of silicon nitride 1 cm across and 1 micron thick. The operational properties of these devices are determined by this circuitry, along with thermal control structures etched into the membranes. These etched structures do not perforate the membrane, so that the device is both comparatively robust mechanically and carefully tailored in terms of its thermal transport properties. In this paper, we report on development of the superconducting bilayer TES technology and characterization of the FSB stacks. This includes the use of new materials, the design and testing of thermal control structures, the introduction of desirable thermal properties using buried layers of crystalline silicon underneath the membrane, detector stability control, and optical and thermal test results. The scientific motivation, FSB design, FSB fabrication, and measurement results are discussed.

Surviving to tell the tale: Argonne's Intense Pulsed Neutron Source from an ecosystem perspective

International Nuclear Information System (INIS)

Westfall, C.

2010-01-01

At first glance the story of the Intense Pulsed Neutron Source (IPNS), an accelerator-driven neutron source for exploring the structure of materials through neutron scattering, seems to be one of puzzling ups and downs. For example, Argonne management, Department of Energy officials, and materials science reviewers continued to offer, then withdraw, votes of confidence even though the middling-sized IPNS produced high-profile research, including work that made the cover of Nature in 1987. In the midst of this period of shifting opinion and impressive research results, some Argonne materials scientists were unenthusiastic, members of the laboratory's energy physics group were key supporters, and materials scientists at another laboratory provided, almost fortuitously, a new lease on life. What forces shaped the puzzling life cycle of the IPNS? And what role - if any - did the moderate price tag and the development of scientific and technological ideas play in the course it took? To answer these questions this paper looks to an ecosystem metaphor for inspiration, exploring how opinions, ideas, and machinery emerged from the interrelated resource economies of Argonne, the DOE, and the materials science community by way of a tangled web of shifting group interactions. The paper will conclude with reflections about what the resulting focus on relationality explains about the IPNS story as well as the underlying dynamic that animates knowledge production at U.S. national laboratories.

Fabrication and Testing of Deflecting Cavities for APS

Energy Technology Data Exchange (ETDEWEB)

Mammosser, John; Wang, Haipeng; Rimmer, Robert; Jim, Henry; Katherine, Wilson; Dhakal, Pashupati; Ali, Nassiri; Jim, Kerby; Jeremiah, Holzbauer; Genfa, Wu; Joel, Fuerst; Yawei, Yang; Zenghai, Li

2013-09-01

Jefferson Lab (Newport News, Virginia) in collaboration with Argonne National Laboratory (Argonne, IL) has fabricated and tested four first article, 2.8 GHz, deflecting SRF cavities, for Argonne's Short-Pulse X-ray (SPX) project. These cavities are unique in many ways including the fabrication techniques in which the cavity cell and waveguides were fabricated. These cavity subcomponents were milled from bulk large grain niobium ingot material directly from 3D CAD files. No forming of sub components was used with the exception of the beam-pipes. The challenging cavity and helium vessel design and fabrication results from the stringent RF performance requirements required by the project and operation in the APS ring. Production challenges and fabrication techniques as well as testing results will be discussed in this paper.

Bush will tour Illionois lab working to fight terrorism Argonne develops chemical detectors

CERN Multimedia

2002-01-01

"A chemical sensor that detects cyanide gas, a biochip that can determine the presence of anthrax, and a portable device that finds concealed nuclear materials are among the items scientists at Argonne National Laboratory are working on to combat terrorism" (1/2 page).

Proceedings of the international meeting on research and test reactor core conversions from HEU to LEU fuels

Energy Technology Data Exchange (ETDEWEB)

Travelli, A [Argonne National Laboratory, Argonne, IL (United States)

1983-09-01

Conversion of research and test reactor cores from the use of high enrichment uranium to the use of low enrichment uranium depends on the cooperation of many research organizations, reactor operators, and government agencies. At a technical level, it involves almost all aspects of the fuel cycle, including fuel development, testing, shipping and reprocessing; experiment performance; economics; and safety and licensing aspects. The reactors involved and the conversion activities are distributed among approximately 25 countries, making this a subject which is best dealt with on an international basis. To foster direct communication in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the fifth of a series which began in 1978. The previous meetings were held at Argonne (International Meeting of Research Reactor Fuel Designers, Developers, and Fabricators, Argonne National Laboratory, Argonne, U.S.A., November 910, 1978), at Saclay (IAEA Consultants' Meeting on Research Reactor Core Conversions from HEU to LEU, Centre d'etudes Nucleaires de Saclay, Saclay, France, December 12-14, 1979), at Argonne (International Meeting on Development, Fabrication and Application of Reduced Enrichment Fuels for Research and Test Reactors, Argonne National Laboratory, Argonne, U.S.A., November 12-14, 1980) and at Juelich (Seminar on Research Reactor Operation and Use, Juelich Nuclear Research Center, Juelich, F.R.G., September 48, 1981). Proceedings from the two most recent previous meetings were published as ANL/RERTR/TM-3 (CONF-801144) and IAEA-SR-77. The spirit of this meeting differs slightly from that of the previous meetings. The advances which have been made and the growing maturity of the effort have caused a gradual shift of emphasis away from those topics which dominated the floor during the first meetings, such as fuel and methods development, and towards topics which concern more

Proceedings of the international meeting on research and test reactor core conversions from HEU to LEU fuels

International Nuclear Information System (INIS)

Travelli, A.

1983-09-01

Conversion of research and test reactor cores from the use of high enrichment uranium to the use of low enrichment uranium depends on the cooperation of many research organizations, reactor operators, and government agencies. At a technical level, it involves almost all aspects of the fuel cycle, including fuel development, testing, shipping and reprocessing; experiment performance; economics; and safety and licensing aspects. The reactors involved and the conversion activities are distributed among approximately 25 countries, making this a subject which is best dealt with on an international basis. To foster direct communication in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the fifth of a series which began in 1978. The previous meetings were held at Argonne (International Meeting of Research Reactor Fuel Designers, Developers, and Fabricators, Argonne National Laboratory, Argonne, U.S.A., November 910, 1978), at Saclay (IAEA Consultants' Meeting on Research Reactor Core Conversions from HEU to LEU, Centre d'etudes Nucleaires de Saclay, Saclay, France, December 12-14, 1979), at Argonne (International Meeting on Development, Fabrication and Application of Reduced Enrichment Fuels for Research and Test Reactors, Argonne National Laboratory, Argonne, U.S.A., November 12-14, 1980) and at Juelich (Seminar on Research Reactor Operation and Use, Juelich Nuclear Research Center, Juelich, F.R.G., September 48, 1981). Proceedings from the two most recent previous meetings were published as ANL/RERTR/TM-3 (CONF-801144) and IAEA-SR-77. The spirit of this meeting differs slightly from that of the previous meetings. The advances which have been made and the growing maturity of the effort have caused a gradual shift of emphasis away from those topics which dominated the floor during the first meetings, such as fuel and methods development, and towards topics which concern more

Argonne effect - evidence for the shell structure of proton

International Nuclear Information System (INIS)

Levintov, I.I.

1983-01-01

A strong spin effect in P,P scattering at parallel spin orientation of a target and a projectile and psub(t)sup(2) > or approximately 4(GeV/c) 2 (psub(t) is a transverse momentum of scattered proton) - Argonne effect - is explained by the presence of Fock configuration (qqc anti cq) ip proton which has the structure of p-shell. An analogous effect in the region psub(perpendicular)sup(2) > or approximately 25(GeV/c) 2 associated with the configuration (qqb anti bq) is predicted

Effect of synchrotron radiation in the proposed 4 GeV Argonne microtron

International Nuclear Information System (INIS)

Crosbie, E.A.

1983-01-01

Synchrotron radiation in the sector magnets of the 4-GeV microtron designed at the Argonne National Laboratory produces a small but noticeable distortion of the closed orbits of the system and a very-significant growth of the horizontal and longitudinal phase-space emittances. Because of the small apertures in the three 25-meter linacs, it is important that the expected growth of the beam be calculated as accurately as possible. For this reason, a computer program has been written which follows the motions of individual electrons in the four dimensional horizontal and longitudinal phase space as they are accelerated in the system. As the electrons go through the sector magnets, they emit quanta at random with randomly chosen energies. The final results show 63% emittance (area π) values of 0.15 mm mrad and 630 keV degrees for the horizontal and longitudinal phase spaces, respectively. The 99% values are about 4.6 times larger

Harbin Institute of Technology collaborative base project at APS of Argonne

Science.gov (United States)

Liu, H.; Liu, L. L.

2013-05-01

In this paper, the progress of Harbin Institute of Technology (HIT) collaborative base project, which was launched at Argonne National Laboratory in 2010, will be presented. The staff and students from HIT involved in advanced technological developments, which included tomography, high energy PDF, diffraction and scattering, and inelastic scattering techniques in APS to study structures changes of minerals and materials under high pressure conditions.

Argonne National Laboratory high performance network support of APS experiments

International Nuclear Information System (INIS)

Knot, M.J.; McMahon, R.J.

1996-01-01

Argonne National Laboratory is currently positioned to provide access to high performance regional and national networks. Much of the impetus for this effort is the anticipated needs of the upcoming experimental program at the APS. Some APS collaborative access teams (CATs) are already pressing for network speed improvements and security enhancements. Requirements range from the need for high data rate, secure transmission of experimental data, to the desire to establish a open-quote open-quote virtual experimental environment close-quote close-quote at their home institution. In the near future, 155 megabit/sec (Mb/s) national and regional asynchronous transfer mode (ATM) networks will be operational and available to APS users. Full-video teleconferencing, virtual presence operation of experiments, and high speed, secure transmission of data are being tested and, in some cases, will be operational. We expect these efforts to enable a substantial improvement in the speed of processing experimental results as well as an increase in convenience to the APS experimentalist. copyright 1996 American Institute of Physics

Argonne tandem as injector to a superconducting linac

International Nuclear Information System (INIS)

Yntema, J.L.; Den Hartog, P.K.; Henning, W.; Kutschera, W.

1980-01-01

The Argonne Tandem uses Pelletron chains, NEC accelerator tubes, and a dual closed-corona system. Its main function is to be an injector for a superconducting linear accelerator. As long as the transverse and longitudinal emittances are within the acceptance of the linac, the output beam quality of the tandem-linac system is essentially determined by the tandem. The sensitivity of the linac to the longitudinal emittance ΔEΔt of the incident beam makes the output beam quality dependent on the negative-ion velocity distribution in the source, transit-time effects in the tandem, molecular-beam dissociation, and stripper-foil uniformity. This paper discusses these beam-degrading effects

Calculations of transient fields in the Felix experiments at Argonne using null field integrated techniques

International Nuclear Information System (INIS)

Han, H.C.; Davey, K.R.; Turner, L.

1985-08-01

The transient eddy current problem is characteristically computationally intensive. The motivation for this research was to realize an efficient, accurate, solution technique involving small matrices via an eigenvalue approach. Such a technique is indeed realized and tested using the null field integral technique. Using smart (i.e., efficient, global) basis functions to represent unknowns in terms of a minimum number of unknowns, homogeneous eigenvectors and eigenvalues are first determined. The general excitatory response is then represented in terms of these eigenvalues/eigenvectors. Excellent results are obtained for the Argonne Felix cylinder experiments using a 4 x 4 matrix. Extension to the 3-D problem (short cylinder) is set up in terms of an 8 x 8 matrix

1985 annual site environmental report for Argonne National Laboratory

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Sedlet, J.

1986-03-01

This is one in a series of annual reports prepared to provide DOE, environmental agencies, and the public with information on the level of radioactive and chemical pollutants in the environment and on the amounts of such substances, if any, added to the environment as a result of Argonne operations. Included in this report are the results of measurements obtained in 1985 for a number of radionuclides in air, surface water, ground water, soil, grass, bottom sediment, and milk; for a variety of chemical constituents in surface and subsurface water; and for the external penetrating radiation dose

Alkaloid-derived molecules in low rank Argonne premium coals.

Energy Technology Data Exchange (ETDEWEB)

Winans, R. E.; Tomczyk, N. A.; Hunt, J. E.

2000-11-30

Molecules that are probably derived from alkaloids have been found in the extracts of the subbituminous and lignite Argonne Premium Coals. High resolution mass spectrometry (HRMS) and liquid chromatography mass spectrometry (LCMS) have been used to characterize pyridine and supercritical extracts. The supercritical extraction used an approach that has been successful for extracting alkaloids from natural products. The first indication that there might be these natural products in coals was the large number of molecules found containing multiple nitrogen and oxygen heteroatoms. These molecules are much less abundant in bituminous coals and absent in the higher rank coals.

Large area damage testing of optics

International Nuclear Information System (INIS)

Sheehan, L.; Kozlowski, M.; Stolz, C.

1996-01-01

The damage threshold specifications for the National Ignition Facility will include a mixture of standard small-area tests and new large-area tests. During our studies of laser damage and conditioning processes of various materials we have found that some damage morphologies are fairly small and this damage does not grow with further illumination. This type of damage might not be detrimental to the laser performance. We should therefore assume that some damage can be allowed on the optics, but decide on a maximum damage allowance of damage. A new specification of damage threshold termed open-quotes functional damage thresholdclose quotes was derived. Further correlation of damage size and type to system performance must be determined in order to use this measurement, but it is clear that it will be a large factor in the optics performance specifications. Large-area tests have verified that small-area testing is not always sufficient when the optic in question has defect-initiated damage. This was evident for example on sputtered polarizer and mirror coatings where the defect density was low enough that the features could be missed by standard small- area testing. For some materials, the scale-length at which damage non-uniformities occur will effect the comparison of small-area and large-area tests. An example of this was the sub-aperture tests on KD*P crystals on the Beamlet test station. The tests verified the large-area damage threshold to be similar to that found when testing a small-area. Implying that for this KD*P material, the dominate damage mechanism is of sufficiently small scale-length that small-area testing is capable of determining the threshold. The Beamlet test station experiments also demonstrated the use of on-line laser conditioning to increase the crystals damage threshold

An Applied Study on the Decontamination and Decommissioning of the Map Tube Facility 317 Area Argonne National Laboratory, Chicago

Energy Technology Data Exchange (ETDEWEB)

Varley, Geoff; Rusch, Chris [NAC International, Henley-on-Thames (United Kingdom)

2005-01-01

less. Unlike the MTF, AT has some storage vaults in addition to storage tubes. Based on available descriptions of the nature of the wastes stored in AT and the MTF, in general terms the range of wastes appears to be somewhat similar. In the case of the MTF it was determined that radioactive sludge was present at the bottom of the tubes, resulting from water ingress and corrosion of both storage containers and their contents. In the case of AT it is not known exactly what the condition of the tubes is but it is recognised that leakage/contamination in the lower parts of the tubes is likely to have occurred. This is an important consideration in the planning of the AT decommissioning program and the related cost estimate, principally because of the potential consequence of different approaches and specific techniques chosen to implement decommissioning. The AT decommissioning cost estimate report is not entirely clear in detail regarding the specific methodology to be adopted. In addition there are a number of important uncertainties concerning the extent of radioactive contamination. Depending on what the reality turns out to be, the decommissioning methodology could be affected and the quantities of wastes in various categories also could vary. In any event, the AT cost estimate report is unclear regarding waste volumes in a number of respects. The AT cost estimate is presented in a similar fashion to several other recent decommissioning cost estimates prepared by Westinghouse for SVAFO, using an approach and presentation format that suffers somewhat from: - Not always being clear, - Not always being unambiguous and easy to understand and, - Lack of detail and clear substantiation of assumptions in some important areas. Setting these concerns aside, the available information has been evaluated and compared with the Argonne MTF decommissioning costs and other selected NAC derived decommissioning cost benchmarks. In summary the conclusions for the AT decommissioning cost

An Applied Study on the Decontamination and Decommissioning of the Map Tube Facility 317 Area Argonne National Laboratory, Chicago

International Nuclear Information System (INIS)

Varley, Geoff; Rusch, Chris

2005-01-01

less. Unlike the MTF, AT has some storage vaults in addition to storage tubes. Based on available descriptions of the nature of the wastes stored in AT and the MTF, in general terms the range of wastes appears to be somewhat similar. In the case of the MTF it was determined that radioactive sludge was present at the bottom of the tubes, resulting from water ingress and corrosion of both storage containers and their contents. In the case of AT it is not known exactly what the condition of the tubes is but it is recognised that leakage/contamination in the lower parts of the tubes is likely to have occurred. This is an important consideration in the planning of the AT decommissioning program and the related cost estimate, principally because of the potential consequence of different approaches and specific techniques chosen to implement decommissioning. The AT decommissioning cost estimate report is not entirely clear in detail regarding the specific methodology to be adopted. In addition there are a number of important uncertainties concerning the extent of radioactive contamination. Depending on what the reality turns out to be, the decommissioning methodology could be affected and the quantities of wastes in various categories also could vary. In any event, the AT cost estimate report is unclear regarding waste volumes in a number of respects. The AT cost estimate is presented in a similar fashion to several other recent decommissioning cost estimates prepared by Westinghouse for SVAFO, using an approach and presentation format that suffers somewhat from: - Not always being clear, - Not always being unambiguous and easy to understand and, - Lack of detail and clear substantiation of assumptions in some important areas. Setting these concerns aside, the available information has been evaluated and compared with the Argonne MTF decommissioning costs and other selected NAC derived decommissioning cost benchmarks. In summary the conclusions for the AT decommissioning cost

Low-level radioactive waste management at Argonne National Laboratory-East

International Nuclear Information System (INIS)

Rock, C.M.; Shearer, T.L.; Nelson, R.A.

1997-01-01

This paper is an overview of the low-level radioactive waste management practices and treatment systems at Argonne National Laboratory - East (ANL-E). It addresses the systems, processes, types of waste treated, and the status and performance of the systems. ANL-E is a Department of Energy laboratory that is engaged in a variety of research projects, some of which generate radioactive waste, in addition a significant amount of radioactive waste remains from previous projects and decontamination and decommissioning of facilities where this work was performed

Progress Report on the ISCR Pilot Test Conducted at the Former CCC/USDA Grain Storage Facility in Montgomery City, Missouri, as of April 2013

Energy Technology Data Exchange (ETDEWEB)

LaFreniere, Lorraine M. [Argonne National Lab. (ANL), Argonne, IL (United States). Environmental Science Division. Applied Geoscience and Environmental Restoration Program

2013-06-01

The Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) is conducting an environmental investigation at the former CCC/USDA grain storage facility on the county fairgrounds in Montgomery City, Missouri, to evaluate contamination associated with the former use of grain fumigants containing carbon tetrachloride at the site. The CCC/USDA studies have identified carbon tetrachloride in the soils (primarily unconsolidated glacial tills) at concentrations that exceed the U.S. Environmental Protection Agency (EPA) regional screening level (RSL) values for this compound in residential soils (610 μg/kg) but are below the corresponding RSL for industrial soils (3,000 μg/kg). Concentrations of carbon tetrachloride greater than the EPA maximum contaminant level (MCL; 5.0 μg/L) for this contaminant in drinking water were also identified in the shallow groundwater (Argonne 2012). On the basis of these findings, remedial actions are considered necessary to mitigate the present and potential future impacts of the contamination. In cooperation with the Missouri Department of Natural Resources (MDNR), the CCC/USDA has initiated a field-scale pilot test to evaluate an in situ technology for treatment of the carbon tetrachloride contamination. In this approach, a chemical amendment consisting primarily of slow-release organic matter and zero-valent iron is employed to induce oxygen-depleted, chemically reducing conditions in the subsurface. These conditions foster the in situ chemical reduction (ISCR) of carbon tetrachloride and its degradation products (chloroform, methylene chloride, and chloromethane) via both inorganic and biologically mediated processes. The chemical amendment being used, EHC™, was developed by the Adventus Group, Freeport, Illinois, and is now manufactured and distributed by FMC Environmental Solutions, Philadelphia, Pennsylvania. With the approval of the MDNR (2012), the ISCR technology is being tested in two target areas

ANL-W 779 pond seepage test

International Nuclear Information System (INIS)

Braun, D.R.

1992-11-01

The ANL-W 779 sanitary wastewater treatment ponds are located on the Idaho National Engineering Laboratory (INEL), north of the Argonne National Laboratory -- West (ANL-W) site A seepage test was performed for two Argonne National Laboratory -- West (ANL-W) sanitary wastewater treatment ponds, Facility 779. Seepage rates were measured to determine if the ponds are a wastewater land application facility. The common industry standard for wastewater land application facilities is a field-measured seepage rate of one quarter inch per day or greater

Fiscal year 1996 decontamination and decommissioning activities photobriefing book for the Argonne National Laboratory-East Site, Technology Development Division, Waste Management Program, Decontamination and Decommissioning Projects Department

International Nuclear Information System (INIS)

1996-01-01

The Photobriefing Book describes the Decontamination and Decommissioning (D and D) Program at the Argonne National Laboratory-East Site (ANL-E) near Lemont, Illinois. This book summarizes current D and D projects, reviews fiscal year (FY) 1996 accomplishments, and outlines FY 1997 goals. A section on D and D Technology Development provides insight on new technologies for D and D developed or demonstrated at ANL-E. Past projects are recapped and upcoming projects are described as Argonne works to accomplish its commitment to, ''Close the Circle on the Splitting of the Atom.'' Finally, a comprehensive review of the status and goals of the D and D Program is provided to give a snap-shot view of the program and the direction it's taking as it moves into FY 1997. The D and D projects completed to date include: Plutonium Fuel Fabrication Facility; East Area Surplus Facilities; Experimental Boiling Water Reactor; M-Wing Hot Cell Facilities; Plutonium Gloveboxes; and Fast Neutron Generator

Energy Systems Test Area (ESTA). Power Systems Test Facilities

Science.gov (United States)

Situ, Cindy H.

2010-01-01

This viewgraph presentation provides a detailed description of the Johnson Space Center's Power Systems Facility located in the Energy Systems Test Area (ESTA). Facilities and the resources used to support power and battery systems testing are also shown. The contents include: 1) Power Testing; 2) Power Test Equipment Capabilities Summary; 3) Source/Load; 4) Battery Facilities; 5) Battery Test Equipment Capabilities Summary; 6) Battery Testing; 7) Performance Test Equipment; 8) Battery Test Environments; 9) Battery Abuse Chambers; 10) Battery Abuse Capabilities; and 11) Battery Test Area Resources.

Fire protection program evaluation of Argonne National Laboratory, West for the Department of Energy

International Nuclear Information System (INIS)

1984-01-01

A fire protection engineering survey was conducted of the Argonne National Laboratory, West Facility, near Idaho Falls, Idaho. This facility includes EBR-II, TREAT, ZPPR, and HFEF. The facility meets the improved risk criteria as set forth in DOE Order 5480.1, Chapter VII. Some recommendations are given

Leidos Biomed Teams with NCI, DOE, and Argonne National Lab to Support National X-Ray Resource | Poster

Science.gov (United States)

Scientists are making progress in understanding a bleeding disorder caused by prescription drug interactions, thanks to a high-tech research facility involving two federal national laboratories, Argonne and Frederick.

Decontamination and decommissioning of the Experimental Boiling Water Reactor (EBWR): Project final report, Argonne National Laboratory

International Nuclear Information System (INIS)

Fellhauer, C.R.; Boing, L.E.; Aldana, J.

1997-03-01

The Final Report for the Decontamination and Decommissioning (D ampersand D) of the Argonne National Laboratory - East (ANL-E) Experimental Boiling Water Reactor (EBWR) facility contains the descriptions and evaluations of the activities and the results of the EBWR D ampersand D project. It provides the following information: (1) An overall description of the ANL-E site and EBWR facility. (2) The history of the EBWR facility. (3) A description of the D ampersand D activities conducted during the EBWR project. (4) A summary of the final status of the facility, including the final and confirmation surveys. (5) A summary of the final cost, schedule, and personnel exposure associated with the project, including a summary of the total waste generated. This project report covers the entire EBWR D ampersand D project, from the initiation of Phase I activities to final project closeout. After the confirmation survey, the EBWR facility was released as a open-quotes Radiologically Controlled Area,close quotes noting residual elevated activity remains in inaccessible areas. However, exposure levels in accessible areas are at background levels. Personnel working in accessible areas do not need Radiation Work Permits, radiation monitors, or other radiological controls. Planned use for the containment structure is as an interim transuranic waste storage facility (after conversion)

A tau-charm-factory at Argonne

International Nuclear Information System (INIS)

Norem, J.; Repond, J.

1994-01-01

In this paper we explore the possibility of building a tau-charm-factory at the Argonne National Laboratory. A tau-charm-factory is an e + e - collider with a center-of-mass energy between 3.0 GeV and 5.0 GeV and a luminosity of at least 1 x 10 33 cm -2 s -1 . Once operational, the facility will produce large samples of τ pairs, charm mesons, and charmonium with either negligible or well understood backgrounds. This will lead to high precision measurements in the second generation quark and the third generation lepton sectors that cannot be done at other facilities. Basic physical properties and processes, such as the tau neutrino mass, rare tau decays, charm decay constants, rare charm meson decays, neutral D 0 -- meson mixing, and many more will be studied with unique precision. An initial design of the collider including the injector system is described. The design shows that a luminosity of at least 1 x 10 33 cm -2 s -1 can be achieved over the entire center-of-mass energy range of the factory

Project plan for the decontamination and decommissioning of the Argonne National Laboratory Experimental Boiling Water Reactor

International Nuclear Information System (INIS)

Boing, L.E.

1989-12-01

In 1956, the Experimental Boiling Water Reactor (EBWR) Facility was first operated at Argonne National Laboratory (ANL) as a test reactor to demonstrate the feasibility of operating an integrated power plant using a direct cycle boiling water reactor as a heat source. In 1967, ANL permanently shut down the EBWR and placed it in dry lay-up. This project plan presents the schedule and organization for the decontamination and decommissioning of the EBWR Facility which will allow it to be reused by other ANL scientific research programs. The project total estimated cost is $14.3M and is projected to generate 22,000 cubic feet of low-level radioactive waste which will be disposed of at an approved DOE burial ground. 18 figs., 3 tabs

Project plan for the decontamination and decommissioning of the Argonne National Laboratory Experimental Boiling Water Reactor

Energy Technology Data Exchange (ETDEWEB)

Boing, L.E.

1989-12-01

In 1956, the Experimental Boiling Water Reactor (EBWR) Facility was first operated at Argonne National Laboratory (ANL) as a test reactor to demonstrate the feasibility of operating an integrated power plant using a direct cycle boiling water reactor as a heat source. In 1967, ANL permanently shut down the EBWR and placed it in dry lay-up. This project plan presents the schedule and organization for the decontamination and decommissioning of the EBWR Facility which will allow it to be reused by other ANL scientific research programs. The project total estimated cost is $14.3M and is projected to generate 22,000 cubic feet of low-level radioactive waste which will be disposed of at an approved DOE burial ground. 18 figs., 3 tabs.

Decontamination and decommissioning of the JANUS reactor at the Argonne National Laboratory-East site

International Nuclear Information System (INIS)

Fellhauer, C.R.; Garlock, G.A.

1997-05-01

Argonne National Laboratory has begun the decontamination and decommissioning (D ampersand D) of the JANUS Reactor Facility. The project is managed by the Technology Development Division's D ampersand D Program personnel. D ampersand D procedures are performed by sub-contractor personnel. Specific activities involving the removal, size reduction, and packaging of radioactive components and facilities are discussed

YUCCA Mountain Project - Argonne National Laboratory, Annual Progress Report, FY 1997 for activity WP 1221 unsaturated drip condition testing of spent fuel and unsaturated dissolution tests of glass.

Energy Technology Data Exchange (ETDEWEB)

Bates, J. K.; Buck, E. C.; Emery, J. W.; Finch, R. J.; Finn, P. A.; Fortner, J.; Hoh, J. C.; Mertz, C.; Neimark, L. A.; Wolf, S. F.; Wronkiewicz, D. J.

1998-09-18

This document reports on the work done by the Nuclear Waste Management Section of the Chemical Technology Division of Argonne National Laboratory in the period of October 1996 through September 1997. Studies have been performed to evaluate the behavior of nuclear waste glass and spent fuel samples under the unsaturated conditions (low-volume water contact) that are likely to exist in the Yucca Mountain environment being considered as a potential site for a high-level waste repository. Tests with actinide-doped waste glasses, in progress for over 11 years, indicate that the transuranic element release is dominated by colloids that continuously form and span from the glass surface. The nature of the colloids that form in the glass and spent fuel testing programs is being investigated by dynamic light scattering to determine the size distribution, by autoradiography to determine the chemistry, and by zeta potential to measure the electrical properties of the colloids. Tests with UO{sub 2} have been ongoing for 12 years. They show that the oxidation of UO{sub 2} occurs rapidly, and the resulting paragenetic sequence of secondary phases forming on the sample surface is similar to that observed for uranium found in natural oxidizing environments. The reaction of spent fuel samples in conditions similar to those used with UO{sub 2} have been in progress for over six years, and the results suggest that spent fuel forms many of the same alteration products as UO{sub 2}. With spent fuel, the bulk of the reaction occurs via a through-grain reaction process, although grain boundary attack is sufficient to have reacted all of the grain boundary regions in the samples. New test methods are under development to evaluate the behavior of spent fuel samples with intact cladding: the rate at which alteration and radionuclide release occurs when water penetrates fuel sections and whether the reaction causes the cladding to split. Alteration phases have been formed on fine grains of UO

YUCCA Mountain Project - Argonne National Laboratory, Annual Progress Report, FY 1997 for activity WP 1221 unsaturated drip condition testing of spent fuel and unsaturated dissolution tests of glass

International Nuclear Information System (INIS)

Bates, J.K.; Buck, E.C.; Emery, J.W.; Finch, R.J.; Finn, P.A.; Fortner, J.; Hoh, J.C.; Mertz, C.; Neimark, L.A.; Wolf, S.F.; Wronkiewicz, D.J.

1998-01-01

This document reports on the work done by the Nuclear Waste Management Section of the Chemical Technology Division of Argonne National Laboratory in the period of October 1996 through September 1997. Studies have been performed to evaluate the behavior of nuclear waste glass and spent fuel samples under the unsaturated conditions (low-volume water contact) that are likely to exist in the Yucca Mountain environment being considered as a potential site for a high-level waste repository. Tests with actinide-doped waste glasses, in progress for over 11 years, indicate that the transuranic element release is dominated by colloids that continuously form and span from the glass surface. The nature of the colloids that form in the glass and spent fuel testing programs is being investigated by dynamic light scattering to determine the size distribution, by autoradiography to determine the chemistry, and by zeta potential to measure the electrical properties of the colloids. Tests with UO 2 have been ongoing for 12 years. They show that the oxidation of UO 2 occurs rapidly, and the resulting paragenetic sequence of secondary phases forming on the sample surface is similar to that observed for uranium found in natural oxidizing environments. The reaction of spent fuel samples in conditions similar to those used with UO 2 have been in progress for over six years, and the results suggest that spent fuel forms many of the same alteration products as UO 2 . With spent fuel, the bulk of the reaction occurs via a through-grain reaction process, although grain boundary attack is sufficient to have reacted all of the grain boundary regions in the samples. New test methods are under development to evaluate the behavior of spent fuel samples with intact cladding: the rate at which alteration and radionuclide release occurs when water penetrates fuel sections and whether the reaction causes the cladding to split. Alteration phases have been formed on fine grains of UO 2 in contact with

Glovebox characterization and barrier integrity testing using fluorescent powder

International Nuclear Information System (INIS)

Wahlquist, D.R.

1996-01-01

This paper presents a method for characterizing the spread of contamination and testing the barrier integrity of a new glovebox during material transfer operations and glove change-outs using fluorescent powder. Argonne National Laboratory-West has performed this test on several new gloveboxes prior to putting them into service. The test is performed after the glovebox has been leak tested and all systems have been verified to be operational. The purpose of the test is to show that bag-in/bag-out operations and glove change-outs can be accomplished without spreading the actual contaminated material to non-contaminated areas. The characterization test also provides information as to where contamination might be expected to build-up during actual operations. The fluorescent powder is used because it is easily detectable using an ultra-violet light and disperses in a similar fashion to radioactive material. The characterization and barrier integrity test of a glovebox using fluorescent powder provides a visual method of determining areas of potential contamination accumulation and helps evaluate the ability to perform clean transfer operations and glove change-outs

Changes in the Vegetation Cover in a Constructed Wetland at Argonne National Laboratory, Illinois

Energy Technology Data Exchange (ETDEWEB)

Bergman, C.L.; LaGory, K.

2004-01-01

Wetlands are valuable resources that are disappearing at an alarming rate. Land development has resulted in the destruction of wetlands for approximately 200 years. To combat this destruction, the federal government passed legislation that requires no net loss of wetlands. The United States Army Corps of Engineers (USACE) is responsible for regulating wetland disturbances. In 1991, the USACE determined that the construction of the Advanced Photon Source at Argonne National Laboratory would damage three wetlands that had a total area of one acre. Argonne was required to create a wetland of equal acreage to replace the damaged wetlands. For the first five years after this wetland was created (1992-1996), the frequency of plant species, relative cover, and water depth was closely monitored. The wetland was not monitored again until 2002. In 2003, the vegetation cover data were again collected with a similar methodology to previous years. The plant species were sampled using quadrats at randomly selected locations along transects throughout the wetland. The fifty sampling locations were monitored once in June and percent cover of each of the plant species was determined for each plot. Furthermore, the extent of standing water in the wetland was measured. In 2003, 21 species of plants were found and identified. Eleven species dominated the wetland, among which were reed canary grass (Phalaris arundinacea), crown vetch (Coronilla varia), and Canada thistle (Cirsium arvense). These species are all non-native, invasive species. In the previous year, 30 species were found in the same wetland. The common species varied from the 2002 study but still had these non-native species in common. Reed canary grass and Canada thistle both increased by more than 100% from 2002. Unfortunately, the non-native species may be contributing to the loss of biodiversity in the wetland. In the future, control measures should be taken to ensure the establishment of more desired native species.

Assessing environmental risk of the retired filter bed area, Battelle West Jefferson

International Nuclear Information System (INIS)

Miller, S.F.; Thompson, M.D.; Glennon, M.A.

1997-04-01

Initial investigations conducted by the U.S. Department of Energy, Chicago Operations Office, and by Argonne National Laboratory used seismic refraction profiling, electrical resistivity depth sounding, conductivity profiling, magnetic gradiometry, and ground-penetrating radar to study environmental geophysics in the area of the Battelle West Jefferson site's radiologically contaminated retired filter beds. The investigators used a combination of nonintrusive technologies and innovative drilling techniques to assess environmental risk at the filter beds and to improve understanding of the geology of the Big Darby Creek floodplain. The geophysical investigation, which showed that the preferred groundwater pathway is associated with a laterally extensive deposit of silty sand to sand that is less than 12 ft deep in the floodplain area, also guided the location of cone penetrometer test sites and piezometer installation. Cone penetrometer testing was useful for comparing continuous logging data with surface geophysical data in establishing correlations among unconsolidated materials

Argonne National Laboratory heavy ion beam transport experiments with a 2 mA 80 keV Xe+1 source

International Nuclear Information System (INIS)

Mazarakis, M.; Price, D.; Watson, J.

1978-01-01

The critical dimensions of the Argonne heavy ion beam transmission experiments and the experimental set-up are considered. Experimental results of beam transmission and emittance measurements are discussed

Decontamination and decommissioning of 61 plutonium gloveboxes in D-Wing, Building 212 Argonne National Laboratory-East: Final project report

International Nuclear Information System (INIS)

Cheever, C.L.; Rose, R.W.

1996-09-01

Argonne National Laboratory-East (ANL-E) is a government-owned, contractor operated, multipurpose research facility located 25 miles southwest of downtown Chicago on 689 hectares (1,700 acres) in DuPage County, Illinois, as shown in Figure 1.1. Building 212 is located in the central area of ANL-E, as shown in Figure 1.2. The purpose of this project was to eliminate the risk of radioactive material release from the contaminated glovebox systems and to make the laboratories available for unrestricted use. The following work objectives were established: (1) Identify and remove radioactive materials for return to ANL-E Special Materials control. (2) Remove and package the radioactively contaminated materials and equipment from the gloveboxes. (3) Decontaminate the gloveboxes to nontransuranic (non-TRU) levels. (4) Size-reduce and package the gloveboxes and support systems. (5) Document and dispose of the radioactive and mixed waste. (6) Decontaminate, survey, and release the nine laboratories and corridor areas for unrestricted use

Argonne National Laboratory contributions to the International Symposium on Fusion Nuclear Technology (ISFNT)

Energy Technology Data Exchange (ETDEWEB)

1988-10-01

A total of sixteen papers with authors from Argonne National Laboratory were presented at the First International Symposium on Fusion Nuclear Technology (ISFNT), held in Tokyo, Japan, in April 1988. The papers cover the results of recent investigations in blanket design and analysis, fusion neutronics, materials experiments in liquid metal corrosion and solid breeders, tritium recovery analysis, experiments and analysis for liquid metal MHD, reactor safety and economic analysis, and transient electromagnetic analysis.

Argonne National Laboratory contributions to the International Symposium on Fusion Nuclear Technology (ISFNT)

International Nuclear Information System (INIS)

1988-10-01

A total of sixteen papers with authors from Argonne National Laboratory were presented at the First International Symposium on Fusion Nuclear Technology (ISFNT), held in Tokyo, Japan, in April 1988. The papers cover the results of recent investigations in blanket design and analysis, fusion neutronics, materials experiments in liquid metal corrosion and solid breeders, tritium recovery analysis, experiments and analysis for liquid metal MHD, reactor safety and economic analysis, and transient electromagnetic analysis

A five-picosecond electron pulse from ANL (Argonne National Laboratory) L-Band Linac

International Nuclear Information System (INIS)

Cox, G.L.; Jonah, C.D.; Ficht, D.T.; Mavrogenes, G.S.; Sauer, M.C. Jr.

1989-01-01

The pulse-compression system of the Argonne National Laboratory Chemistry Division L-Band Linac, presented at the 1986 Linear Accelerator Conference at Stanford, California, has been completed. A five-picosecond-wide electron pulse containing 6 x 10 -9 coulomb charge has been achieved. Acceleration parameters and the pulse-width measurement technique are discussed, and future plans for the utilization of this pulse in radiation chemistry studies are presented. 5 refs., 4 figs

Leidos Biomed Teams with NCI, DOE, and Argonne National Lab to Support National X-Ray Resource | FNLCR Staging

Science.gov (United States)

Scientists are making progress in understanding a bleeding disorder caused by prescription drug interactions, thanks to a high-tech research facility involving two federal national laboratories, Argonne and Frederick. Miroslawa Dauter is a Senior Res

Analysis of the Argonne distance tabletop exercise method.

Energy Technology Data Exchange (ETDEWEB)

Tanzman, E. A.; Nieves, L. A.; Decision and Information Sciences

2008-02-14

The purpose of this report is to summarize and evaluate the Argonne Distance Tabletop Exercise (DISTEX) method. DISTEX is intended to facilitate multi-organization, multi-objective tabletop emergency response exercises that permit players to participate from their own facility's incident command center. This report is based on experience during its first use during the FluNami 2007 exercise, which took place from September 19-October 17, 2007. FluNami 2007 exercised the response of local public health officials and hospitals to a hypothetical pandemic flu outbreak. The underlying purpose of the DISTEX method is to make tabletop exercising more effective and more convenient for playing organizations. It combines elements of traditional tabletop exercising, such as scenario discussions and scenario injects, with distance learning technologies. This distance-learning approach also allows playing organizations to include a broader range of staff in the exercise. An average of 81.25 persons participated in each weekly webcast session from all playing organizations combined. The DISTEX method required development of several components. The exercise objectives were based on the U.S. Department of Homeland Security's Target Capabilities List. The ten playing organizations included four public health departments and six hospitals in the Chicago area. An extent-of-play agreement identified the objectives applicable to each organization. A scenario was developed to drive the exercise over its five-week life. Weekly problem-solving task sets were designed to address objectives that could not be addressed fully during webcast sessions, as well as to involve additional playing organization staff. Injects were developed to drive play between webcast sessions, and, in some cases, featured mock media stories based in part on player actions as identified from the problem-solving tasks. The weekly 90-minute webcast sessions were discussions among the playing organizations

Status report on the positive ion injector (PII) for ATLAS at Argonne National Laboratory

International Nuclear Information System (INIS)

Zinkann, G.P.; Added, N.; Billquist, P.; Bogaty, J.; Clifft, B.; Markovich, P.; Phillips, D.; Strickhorn, P.; Shepard, K.W.

1991-01-01

The Positive Ion Injector (PII) is part of the Uranuim upgrade for ATLAS accelerator at Argonne National Laboratory. This paper will include a technical discussion of the Positive Ion Injector (PII) accelerator with its superconducting, niobium, very low-velocity accelerating structures. It will also discuss the current construction schedule of PII, and review an upgrade of the fast- tuning system. 10 refs., 6 figs

Status report on the positive ion injector (PII) for ATLAS at Argonne National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Zinkann, G.P.; Added, N.; Billquist, P.; Bogaty, J.; Clifft, B.; Markovich, P.; Phillips, D.; Strickhorn, P.; Shepard, K.W.

1991-01-01

The Positive Ion Injector (PII) is part of the Uranuim upgrade for ATLAS accelerator at Argonne National Laboratory. This paper will include a technical discussion of the Positive Ion Injector (PII) accelerator with its superconducting, niobium, very low-velocity accelerating structures. It will also discuss the current construction schedule of PII, and review an upgrade of the fast- tuning system. 10 refs., 6 figs.

ATLAS experience with HEP software at the Argonne leadership computing facility

International Nuclear Information System (INIS)

Uram, Thomas D; LeCompte, Thomas J; Benjamin, D

2014-01-01

A number of HEP software packages used by the ATLAS experiment, including GEANT4, ROOT and ALPGEN, have been adapted to run on the IBM Blue Gene supercomputers at the Argonne Leadership Computing Facility. These computers use a non-x86 architecture and have a considerably less rich operating environment than in common use in HEP, but also represent a computing capacity an order of magnitude beyond what ATLAS is presently using via the LCG. The status and potential for making use of leadership-class computing, including the status of integration with the ATLAS production system, is discussed.

ATLAS Experience with HEP Software at the Argonne Leadership Computing Facility

CERN Document Server

LeCompte, T; The ATLAS collaboration; Benjamin, D

2014-01-01

A number of HEP software packages used by the ATLAS experiment, including GEANT4, ROOT and ALPGEN, have been adapted to run on the IBM Blue Gene supercomputers at the Argonne Leadership Computing Facility. These computers use a non-x86 architecture and have a considerably less rich operating environment than in common use in HEP, but also represent a computing capacity an order of magnitude beyond what ATLAS is presently using via the LCG. The status and potential for making use of leadership-class computing, including the status of integration with the ATLAS production system, is discussed.

Advanced reactor development: The LMR integral fast reactor program at Argonne

International Nuclear Information System (INIS)

Till, C.E.

1990-01-01

Reactor technology for the 21st Century must develop with characteristics that can now be seen to be important for the future, quite different from the things when the fundamental materials and design choices for present reactors were made in the 1950s. Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 3 figs

Proc. of the sixteenth symposium on energy engineering sciences, May 13-15, 1998, Argonne, IL.

Energy Technology Data Exchange (ETDEWEB)

None

1998-05-13

This Proceedings Volume includes the technical papers that were presented during the Sixteenth Symposium on Energy Engineering Sciences on May 13--15, 1998, at Argonne National Laboratory, Argonne, Illinois. The Symposium was structured into eight technical sessions, which included 30 individual presentations followed by discussion and interaction with the audience. A list of participants is appended to this volume. The DOE Office of Basic Energy Sciences (BES), of which Engineering Research is a component program, is responsible for the long-term, mission-oriented research in the Department. The Office has prime responsibility for establishing the basic scientific foundation upon which the Nation's future energy options will be identified, developed, and built. BES is committed to the generation of new knowledge necessary to solve present and future problems regarding energy exploration, production, conversion, and utilization, while maintaining respect for the environment. Consistent with the DOE/BES mission, the Engineering Research Program is charged with the identification, initiation, and management of fundamental research on broad, generic topics addressing energy-related engineering problems. Its stated goals are to improve and extend the body of knowledge underlying current engineering practice so as to create new options for enhancing energy savings and production, prolonging the useful life of energy-related structures and equipment, and developing advanced manufacturing technologies and materials processing. The program emphasis is on reducing costs through improved industrial production and performance and expanding the nation's store of fundamental knowledge for solving anticipated and unforeseen engineering problems in energy technologies. To achieve these goals, the Engineering Research Program supports approximately 130 research projects covering a broad spectrum of topics that cut across traditional engineering disciplines. The program

Laboratory testing of glasses for Lockheed Idaho Technology Company: Final report

International Nuclear Information System (INIS)

Ellison, A.J.G.; Buck, E.C.; Dietz, N.L.; Ebert, W.L.; Luo, J.S.; Wolf, S.F.; Bates, J.K.

1997-06-01

Tests have been conducted at Argonne National Laboratory (ANL) in support of the efforts of Lockheed Idaho Technology Company (LITCO) to vitrify high-level waste calcines. Tests were conducted with three classes of LITCO glass formulations: Formula 127 (fluorine-bearing), Formula 532 (fluorine-free), and 630 series (both single- and mixed-alkali) glasses. The test matrices included, as appropriate, the Product Consistency Test Method B (PCT-B), the Materials Characterization Center Test 1 (MCC-1), and the Argonne vapor hydration test (VHT). Test durations ranged from 7 to 183 d. In 7-d PCT-Bs, normalized mass losses of major glass-forming elements for the LITCO glasses are similar to, or lower than, normalized mass losses obtained for other domestic candidate waste glasses. Formula 532 glasses form zeolite alteration phases relatively early in their reaction with water. The formation of those phases increased the dissolution rate. In contrast, the Formula 127 glass is highly durable and forms alteration phases only after prolonged exposure to water in tests with very high surface area to volume ratios; these alteration phases have a relatively small effect on the rate of glass corrosion. No alteration phases formed within the maximum test duration of 183 d in PCT-Bs with the 630 series glasses. The corrosion behavior of the mixed-alkali 630 series glasses is similar to that of 630 series glasses containing sodium alone. In VHTs, both single- and mixed-alkali glasses form zeolite phases that increase the rate of glass reaction. The original 630 series glasses and those based on a revised surrogate calcine formulation react at the same rate in PCT-Bs and form the same major alteration phases in VHTs

Users Handbook for the Argonne Premium Coal Sample Program

Energy Technology Data Exchange (ETDEWEB)

Vorres, K.S.

1993-10-01

This Users Handbook for the Argonne Premium Coal Samples provides the recipients of those samples with information that will enhance the value of the samples, to permit greater opportunities to compare their work with that of others, and aid in correlations that can improve the value to all users. It is hoped that this document will foster a spirit of cooperation and collaboration such that the field of basic coal chemistry may be a more efficient and rewarding endeavor for all who participate. The different sections are intended to stand alone. For this reason some of the information may be found in several places. The handbook is also intended to be a dynamic document, constantly subject to change through additions and improvements. Please feel free to write to the editor with your comments and suggestions.

Accelerator mass spectrometry of 59Ni and Fe isotopes at the Argonne superconducting linac

International Nuclear Information System (INIS)

Henning, W.; Kutschera, W.; Myslek-Laurikainen, B.; Pardo, R.C.; Smither, R.K.; Yntema, J.L.

1981-01-01

We have obtained initial results in an attempt to use the Argonne tandem-linac system for accelerator mass spectrometry of medium-heavy nuclei. Nuclei of the radioisotope 59 Ni (T/sub 1/2 = 7.5 x 10 5 y) and of the stable isotope 58 Fe at low concentrations have been accelerated and clearly identified. The latter experiment is in preparation of a measurement of the half-life of 60 Fe

The integral fast reactor fuels reprocessing laboratory at Argonne National Laboratory, Illinois

International Nuclear Information System (INIS)

Wolson, R.D.; Tomczuk, Z.; Fischer, D.F.; Slawecki, M.A.; Miller, W.E.

1986-09-01

The processing of Integral Fast Reactor (IFR) metal fuel utilizes pyrochemical fuel reprocessing steps. These steps include separation of the fission products from uranium and plutonium by electrorefining in a fused salt, subsequent concentration of uranium and plutonium for reuse, removal, concentration, and packaging of the waste material. Approximately two years ago a facility became operational at Argonne National Laboratory-Illinois to establish the chemical feasibility of proposed reprocessing and consolidation processes. Sensitivity of the pyroprocessing melts to air oxidation necessitated operation in atmosphere-controlled enclosures. The Integral Fast Reactor Fuels Reprocessing Laboratory is described

Evaluation of the Argonne National Laboratory servo-controlled calorimeter system

International Nuclear Information System (INIS)

Foster, L.A.

1997-01-01

The control system of a replacement mode, twin-bridge, water-bath calorimeter originally built by Mound EG ampersand G Applied Technologies was modified by Argonne National Laboratory. The calorimeter was upgraded with a PC-based computer control and data acquisition system. The system was redesigned to operate in a servo-control mode, and a preheater was constructed to allow pre-equilibration of samples. The instrument was sent to the Plutonium Facility at Los Alamos National Laboratory for testing and evaluation of its performance in the field using heat source standards and plutonium process materials. The important parameters for calorimeter operation necessary to satisfy the nuclear materials control and accountability requirements of the Plutonium Facility were evaluated over a period of several months. These parameters include calorimeter stability, measurement precision and accuracy, and average measurement time. The observed measurement precision and accuracy were found to be acceptable for most accountability measurements, although they were slightly larger than the values for calorimeters in routine use at the Plutonium Facility. Average measurement times were significantly shorter than measurement times for identical items in the Plutonium Facility calorimeters. Unexplained shifts in the baseline measurements were observed on numerous occasions. These shifts could lead to substantial measurement errors if they are not very carefully monitored by the operating facility. Detailed results of the experimental evaluation are presented in this report

Deployment of phytoremediation at the 317/319 area at Argonne National Laboratory - East

International Nuclear Information System (INIS)

Negri, M. C.; Hinchman, R. R.; Quinn, J.; Wozniak, J.

2000-01-01

The 317 and 319 Areas are located on the extreme southern end of the ANL-E site, immediately adjacent to the DuPage County Waterfall Glen Forest Preserve. The 317 Area is an active hazardous and radioactive waste processing and storage area. In the late 1950s, liquid waste was placed in the unit known as the French Drain. Since that time, this waste has migrated into underlying soil and groundwater. The principal environmental concern in the 317 Area is the presence of several VOCs in the soil and groundwater and low levels of tritium in the groundwater beneath and down gradient of the site. The 319 Area Landfill and French Drain are located immediately adjacent to the 317 Area. The principal environmental concern in the 319 Area is the presence of radioactive materials in the waste mound, in the leachate in the mound, and in the shallow groundwater immediately down gradient of the landfill. Several interim actions have already been implemented in this area, to reduce the VOC and tritium releases from these areas, as the result of the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) conducted from December 1994 through September 1996

Specialists' meeting on advanced controls for fast reactors, Argonne, Illinois, USA June 20-22, 1989

International Nuclear Information System (INIS)

1989-01-01

The Specialists' Meeting on ''Advanced Controls for Fast Reactors'' was held in Argonne, Illinois, USA, from June 20 to 22, 1989. The meeting was sponsored by the International Atomic Energy Agency on the recommendation of the IAEA International Working Group on Fast Reactors and was hosted by Argonne National Laboratory and the US Department of Energy. It was attended by 20 participants and observers from Argentina, France, Germany, Japan, India, the USSR, the United Kingdom, the United States of America, and the IAEA. The purpose of the meeting was to provide an opportunity for participating countries to review and discuss their views on design and technology for advanced control in fast reactors. During the meeting papers were presented by the participants on behalf of their countries and organizations. Presentations were followed by open discussions on the subjects covered by the papers and summaries of the discussions were drafted. After the formal sessions were completed, a final discussion session was held and summaries, general conclusions and recommendations were approved by consensus. A separate abstract was prepared for each of the 22 papers presented at this meeting. Refs, figs, tabs, diagrams and photos

AMORE Mo-99 Spike Test Results

Energy Technology Data Exchange (ETDEWEB)

Youker, Amanda J. [Argonne National Lab. (ANL), Argonne, IL (United States); Krebs, John F. [Argonne National Lab. (ANL), Argonne, IL (United States); Quigley, Kevin J. [Argonne National Lab. (ANL), Argonne, IL (United States); Byrnes, James P. [Argonne National Lab. (ANL), Argonne, IL (United States); Rotsch, David A [Argonne National Lab. (ANL), Argonne, IL (United States); Brossard, Thomas [Argonne National Lab. (ANL), Argonne, IL (United States); Wesolowski, Kenneth [Argonne National Lab. (ANL), Argonne, IL (United States); Alford, Kurt [Argonne National Lab. (ANL), Argonne, IL (United States); Chemerisov, Sergey [Argonne National Lab. (ANL), Argonne, IL (United States); Vandegrift, George F. [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-09-27

With funding from the National Nuclear Security Administrations Material Management and Minimization Office, Argonne National Laboratory (Argonne) is providing technical assistance to help accelerate the U.S. production of Mo-99 using a non-highly enriched uranium (non-HEU) source. A potential Mo-99 production pathway is by accelerator-initiated fissioning in a subcritical uranyl sulfate solution containing low enriched uranium (LEU). As part of the Argonne development effort, we are undertaking the AMORE (Argonne Molybdenum Research Experiment) project, which is essentially a pilot facility for all phases of Mo-99 production, recovery, and purification. Production of Mo-99 and other fission products in the subcritical target solution is initiated by putting an electron beam on a depleted uranium (DU) target; the fast neutrons produced in the DU target are thermalized and lead to fissioning of U-235. At the end of irradiation, Mo is recovered from the target solution and separated from uranium and most of the fission products by using a titania column. The Mo is stripped from the column with an alkaline solution. After acidification of the Mo product solution from the recovery column, the Mo is concentrated (and further purified) in a second titania column. The strip solution from the concentration column is then purified with the LEU Modified Cintichem process. A full description of the process can be found elsewhere [1–3]. The initial commissioning steps for the AMORE project include performing a Mo-99 spike test with pH 1 sulfuric acid in the target vessel without a beam on the target to demonstrate the initial Mo separation-and-recovery process, followed by the concentration column process. All glovebox operations were tested with cold solutions prior to performing the Mo-99 spike tests. Two Mo-99 spike tests with pH 1 sulfuric acid have been performed to date. Figure 1 shows the flow diagram for the remotely operated Mo-recovery system for the AMORE project

Performance of the Argonne Wakefield Accelerator Facility and initial experimental results

International Nuclear Information System (INIS)

Gai, W.; Conde, M.; Cox, G.; Konecny, R.; Power, J.; Schoessow, P.; Simpson, J.; Barov, N.

1996-01-01

The Argonne Wakefield Accelerator facility has begun its experimental program. It is designed to address advanced acceleration research requiring very short, intense electron bunches. It incorporates two photocathode based electron sources. One produces up to 100 nC, multi-kiloamp 'drive' bunches which are used to excite wakefields in dielectric loaded structures and in plasma. The second source produces much lower intensity 'witness' pulses which are used to probe the fields produced by the drive. The drive and witness pulses can be precisely timed as well as laterally positioned with respect to each other. This paper discusses commissioning, initial experiments, and outline plans for a proposed 1 GeV demonstration accelerator

Contributions to and expectations from the CRP - Argonne National Laboratory (USA)

International Nuclear Information System (INIS)

Cahalan, J.E.

2007-01-01

For us, the chief benefit of the CRP will be validation of multidimensional fluid dynamics capabilities for analysis of outlet plenum temperature distributions. As reactor designers seek new fuel handling features to reduce costs, upper internal structure configurations are becoming more compact, and higher fidelity analysis techniques are required to assess thermal stresses. Argonne currently has 1) a reactor systems analysis code with an experimentally-based model for plenum stratification, 2) the COMMIX code (parent of the JAEA AQUA code), and 3) commercial fluid dynamics analysis codes. It is anticipated that all or some combination of these capabilities will be employed to perform the CRP analysis

The Argonne beamline-B telescope control system: A study of adaptability

International Nuclear Information System (INIS)

Fuka, M.A.; Clout, P.N.; Conley, A.P.; Hill, J.O.; Rothrock, R.B.; Trease, L.L.; Zander, M.E.

1987-01-01

A beam-expanding telescope to study high-precision H - particle optics and beam sensing was designed by the Accelerator Technology Division at Los Alamos National Laboratory and will be installed on beamline-B at Argonne National Laboratory. The control system for this telescope was developed in a relatively short period of time using experience gained from building the Proton Storage Ring (PSR) control system. The designers modified hardware and software to take advantage of new technology as well as to meet the requirements of the new system. This paper discusses lessons learned in the process of adapting hardware and software from an existing control system to one with rather different requirements

Nuclear Accident Dosimetry at Argonne National Laboratory; Dosimetrie dans les Cas d'Accidents Nucleaires au Laboratoire National d'Argonne; 0421 041b 0423 0416 0411 0410 0414 ; Dosimetria en Casos de Accidente Nuclear en el Laboratorio Nacional de Argonne

Energy Technology Data Exchange (ETDEWEB)

Anderson, L. L.; Duffy, T. L.; Sedlet, J.; O' Neil, D. P. [Argonne National Laboratory, Argonne, IL (United States)

1965-06-15

This report summarizes current planning at Argonne National Laboratory with respect to dose determination following a criticality incident. The discussion relates chiefly to two types of commercially obtained dosimeter packages, and includes the results of independent calibrations performed at the Laboratory. The primary dosimeter system incorporates threshold detectors developed at Oak Ridge National Laboratory for neutron spectrum measurement. Fission foil decay calibration curves have been determined experimentally for scintillation counting equipment routinely used at Argonne. This equipment also has been calibrated for determination of sodium-24 activity in blood. Dosimeter units of the type designed at Savannah River Laboratory are deployed as secondary stations. Data from the neutron activation components of these units will be used to make corrections to, the neutron spectrum for intermediate as well as thermal energies. The epicadmium copper foil activation, for a given fluence of intermediate energy neutrons, has been shown relatively insensitive to neutron spectrum variations within the region, and a meaningful average of copper cross-section has been determined. Counter calibration factors determined at Argonne are presented for the copper, indium, and sulphur components. The total neutron fluence is computed using the corrected spectrum in conjunction with a capture probability function and the blood sodium result. One or more specifications of neutron dose then may be calculated by applying the spectral information to the appropriate conversion function. The gamma portion of the primary dosimeter package contains fluorescent rods and a thermoluminescent dosimeter in addition to a two-phase chemical dosimeter. The gamma dosimeter in the secondary package is a polyacrylamide solution which is degraded by exposure to gamma radiation. The absorbed dose is derived from a measured change insolution viscosity. Difficulties in evaluation, placement, and

Beam measurements on Argonne linac for collider injector design

International Nuclear Information System (INIS)

Mavrogenes, G.; James, M.B.; Koontz, R.F.; Miller, R.H.

1980-01-01

The 20 MeV electron linac at Argonne produces 5 x 10 10 electrons in a single bunch. This amount of charge per bunch is required for the proposed single pass collider at SLAC. For this reason the characteristics of the beam from this machine are of interest. The longitudinal charge distribution has been measured by a new technique. The technique is a variation on the deduction of bunch shape from a spectrum measurement. Under favorable conditions a resolution of about 1 0 of phase is possible, which is considerably better than can be achieved with streak cameras. The bunch length at 4.5 x 10 10 e - per bunch was measured to be 15 0 FWHM. The transverse emittance has also been measured using standard techniques. The emittance is 16 mm-mrad at 17.2 MeV. (Auth.)

76 FR 26694 - UChicago Argonne, LLC, et al.; Notice of Consolidated Decision on Applications for Duty-Free...

Science.gov (United States)

2011-05-09

... DEPARTMENT OF COMMERCE International Trade Administration UChicago Argonne, LLC, et al.; Notice of... viewed between 8:30 a.m. and 5 p.m. in Room 3720, U.S. Department of Commerce, 14th and Constitution Ave.... Reasons: Pertinent characteristics of this instrument include its modular deposition chamber in order that...

Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume II, Appendix B, Part 8: Argonne National Laboratory - East and New Brunswick Laboratory site assessment team report

International Nuclear Information System (INIS)

1994-09-01

The objective of the Plutonium ES ampersand H Vulnerability Assessment Project is to conduct a comprehensive assessment of the environmental, safety and health (ES ampersand H) vulnerabilities arising from the Department's storage and handling of Its current plutonium holdings. The term open-quote ES ampersand H vulnerabilitiesclose quotes is defined for the purpose of this project to mean conditions or weaknesses that could lead to unnecessary or increased radiation exposure of workers, release of radioactive materials to the environment, or radiation exposure of the public. The assessment will identify and prioritize ES ampersand H vulnerabilities, and will serve as an information base for identifying corrective actions and options for the safe management of fissile materials. The Argonne National Laboratory-East (ANL-E) Site Assessment Team (SAT) was formed from Department of Energy (DOE) Chicago Operations Office-Argonne Area Office Personnel, to conduct a self-assessment of the plutonium holdings and any associated ES ampersand H vulnerabilities at the ANL-E site

Generation of annular, high-charge electron beams at the Argonne wakefield accelerator

Science.gov (United States)

Wisniewski, E. E.; Li, C.; Gai, W.; Power, J.

2013-01-01

We present and discuss the results from the experimental generation of high-charge annular(ring-shaped)electron beams at the Argonne Wakefield Accelerator (AWA). These beams were produced by using laser masks to project annular laser profiles of various inner and outer diameters onto the photocathode of an RF gun. The ring beam is accelerated to 15 MeV, then it is imaged by means of solenoid lenses. Transverse profiles are compared for different solenoid settings. Discussion includes a comparison with Parmela simulations, some applications of high-charge ring beams,and an outline of a planned extension of this study.

Generation of annular, high-charge electron beams at the Argonne wakefield accelerator

Science.gov (United States)

Wisniewski, E. E.; Li, C.; Gai, W.; Power, J.

2012-12-01

We present and discuss the results from the experimental generation of high-charge annular(ring-shaped)electron beams at the Argonne Wakefield Accelerator (AWA). These beams were produced by using laser masks to project annular laser profiles of various inner and outer diameters onto the photocathode of an RF gun. The ring beam is accelerated to 15 MeV, then it is imaged by means of solenoid lenses. Transverse profiles are compared for different solenoid settings. Discussion includes a comparison with Parmela simulations, some applications of high-charge ring beams,and an outline of a planned extension of this study.

Δ degrees of freedom in trinuclei. III. The Argonne Δ model

International Nuclear Information System (INIS)

Picklesimer, A.; Rice, R.A.; Brandenburg, R.

1992-01-01

The Argonne Δ model is used to study the effect of one-Δ and ΔΔ degrees of freedom on the triton binding energy (E T ). Exploratory calculations decompose the J≤4 system of interest into restricted (JL2) calculations, with J≤2 and L(NΔ), L(ΔΔ)≤2, and a 130 keV attractive correction. A JL2 dispersive calculation yields E T =6.50 MeV, while a full JL2 calculation gives 7.16 MeV, revealing an attractive Δ three-body-force (3BF) contribution of 660 keV. Comparing to the nucleons-only value, E T =7.58 MeV, the size of the repulsive Δ dispersive effect is 1080 keV. The one-Δ and ΔΔ 3BF contributions are found to be 440 and 220 keV, respectively, while the corresponding full J≤4 values are 450 and 290 keV, respectively. The net J≤4 result is E T =7.29 MeV versus a nucleons-only value of 7.67 MeV: the attractive Δ 3BF contribution is not quite sufficient to cancel the 1120 keV repulsive Δ dispersive effect. The cancellation between dispersive and 3BF effects is similar to that found for the Hannover Δ model, although the residual Δ repulsive effect found for the Argonne model is non-negligible: Δ effects are found not to resolve the triton binding energy defect. It is also evident from these results that Δ dispersive effects are not adequately represented in nucleons-only models simply by force of fitting the NN data. Thus, the present results confirm the qualitative implications of our previous studies using the Hannover Δ model, including the fact that ΔΔ effects are appreciable

Performance of the Argonne Wakefield Accelerator facility and initial experimental results

International Nuclear Information System (INIS)

Gai, W.; Conde, M.; Cox, G.; Konecny, R.; Power, J.; Schoessow, P.; Simpson, J.; Barov, N.

1996-01-01

The Argonne Wakefield Accelerator (AWA) facility has begun its experimental program. This unique facility is designed to address advanced acceleration research which requires very short, intense electron bunches. The facility incorporates two photo-cathode based electron sources. One produces up to 100 nC, multi-kiloamp 'drive' bunches which are used to excite wakefields in dielectric loaded structures and in plasma. The second source produces much lower intensity 'witness' pulses which are used to probe the fields produced by the drive. The drive and witness pulses can be precisely timed as well as laterally positioned with respect to each other. We discuss commissioning, initial experiments, and outline plans for a proposed 1 GeV demonstration accelerator. (author)

Vibration considerations in the design of the Advanced Photon Source at Argonne National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Jendrzejczyk, J.A.; Wambsganss, M.W.

1991-01-01

The Advanced Photon Source (APS), a new synchrotron radiation facility being built at Argonne National Laboratory, will provide the world's most brilliant X-ray beams for research in a wide range of technical fields. Successful operation of the APS requires an extremely stable positron closed orbit. Vibration of the storage ring quadrupole magnets, even in the submicron range, can lead to distortion of the positron closed orbit and to potentially unacceptable beam emittance growth, which results in degraded performance. This paper presents an overview of the technical approach used to minimize vibration response, beginning at the conceptual stage, through design and construction, and on to successful operation. Acceptance criteria relating to maximum allowable quadrupole magnet vibration are discussed. Soil properties are used to determine resonant frequencies of foundations and to predict attenuation characteristics. Two sources are considered to have the potential to excite the foundation: far-field sources, which are produced external to the facility, and near-field sources, which are produced within the facility. Measurements of ambient ground motion, monitored to determine far- field excitation, are presented. Ambient vibration was measured at several operating facilities within Argonne to gain insight on typical near-field excitation sources. Discussion covers the dynamic response characteristics of a prototypic magnet support structure to various excitations, including ambient floor motion, coolant flow, and magnet power. 19 refs., 10 figs., 5 tabs.

Vibration considerations in the design of the Advanced Photon Source at Argonne National Laboratory

International Nuclear Information System (INIS)

Jendrzejczyk, J.A.; Wambsganss, M.W.

1991-01-01

The Advanced Photon Source (APS), a new synchrotron radiation facility being built at Argonne National Laboratory, will provide the world's most brilliant X-ray beams for research in a wide range of technical fields. Successful operation of the APS requires an extremely stable positron closed orbit. Vibration of the storage ring quadrupole magnets, even in the submicron range, can lead to distortion of the positron closed orbit and to potentially unacceptable beam emittance growth, which results in degraded performance. This paper presents an overview of the technical approach used to minimize vibration response, beginning at the conceptual stage, through design and construction, and on to successful operation. Acceptance criteria relating to maximum allowable quadrupole magnet vibration are discussed. Soil properties are used to determine resonant frequencies of foundations and to predict attenuation characteristics. Two sources are considered to have the potential to excite the foundation: far-field sources, which are produced external to the facility, and near-field sources, which are produced within the facility. Measurements of ambient ground motion, monitored to determine far- field excitation, are presented. Ambient vibration was measured at several operating facilities within Argonne to gain insight on typical near-field excitation sources. Discussion covers the dynamic response characteristics of a prototypic magnet support structure to various excitations, including ambient floor motion, coolant flow, and magnet power. 19 refs., 10 figs., 5 tabs

A preliminary assessment of sup(239,240)Pu concentrations in a stream near Argonne National Laboratory

International Nuclear Information System (INIS)

Singh, H.; Marshall, J.S.

1977-01-01

The plutonium levels in Sawmill Creek, a stream which flows through the site of the Argonne National Laboratory have been determined and are compared here with the environmental levels reported in related studies. The major source of artificial radioactivity in the creek is Argonne's nuclear facilities which produce low-level wastes following clean-up and dilution in the ANL sewage plant. Samples were collected within 1 mile upstream and 1 mile downstream of ANL's waste discharge into the creek. Samples consisted of filtered water, filterable solids, whole water, Cladophora sp., sunfish (gill and G.I. tracts), isopods, and sediments. Results showed that: (1) The filterable solids from the effluent water contained 99% of 239 Pu in contrast to 37% from the upstream water sample. (2) The downstream 239 Pu levels in the whole water of Sawmill Creek were much higher than those reported in related studies. (3) 239 Pu appears to be scavenged primarily by Cladophora sp. in the downstream water of the creek. (4) Fish G.I. tract and its content contained seven times more 239 Pu activity than fish gills. (U.K.)

Area radiation monitor at the intense pulsed-neutron source

International Nuclear Information System (INIS)

Eichholz, J.J.; Lynch, F.J.; Mundis, R.L.; Howe, M.L.; Dolecek, E.H.

1981-01-01

A tissue-equivalent ionization chamber with associated circuitry has been developed for area radiation monitoring in the Intense Pulsed-Neutron Source (IPNS) facility at Argonne National Laboratory. The conventional chamber configuration was modified in order to increase the electric field and effective volume thereby achieving higher sensitivity and linearity. The instrument provides local and remote radiation level indications and a high level alarm. Twenty-four of these instruments were fabricated for use at various locations in the experimental area of the IPNS-1 facility

Small Engine & Accessory Test Area

Data.gov (United States)

Federal Laboratory Consortium — The Small Engine and Accessories Test Area (SEATA) facilitates testaircraft starting and auxiliary power systems, small engines and accessories. The SEATA consists...

Supporting documents for LLL area 27 (410 area) safety analysis reports, Nevada Test Site

Energy Technology Data Exchange (ETDEWEB)

Odell, B. N. [comp.

1977-02-01

The following appendices are common to the LLL Safety Analysis Reports Nevada Test Site and are included here as supporting documents to those reports: Environmental Monitoring Report for the Nevada Test Site and Other Test Areas Used for Underground Nuclear Detonations, U. S. Environmental Protection Agency, Las Vegas, Rept. EMSL-LV-539-4 (1976); Selected Census Information Around the Nevada Test Site, U. S. Environmental Protection Agency, Las Vegas, Rept. NERC-LV-539-8 (1973); W. J. Hannon and H. L. McKague, An Examination of the Geology and Seismology Associated with Area 410 at the Nevada Test Site, Lawrence Livermore Laboratory, Livermore, Rept. UCRL-51830 (1975); K. R. Peterson, Diffusion Climatology for Hypothetical Accidents in Area 410 of the Nevada Test Site, Lawrence Livermore Laboratory, Livermore, Rept. UCRL-52074 (1976); J. R. McDonald, J. E. Minor, and K. C. Mehta, Development of a Design Basis Tornado and Structural Design Criteria for the Nevada Test Site, Nevada, Lawrence Livermore Laboratory, Livermore, Rept. UCRL-13668 (1975); A. E. Stevenson, Impact Tests of Wind-Borne Wooden Missiles, Sandia Laboratories, Tonopah, Rept. SAND 76-0407 (1976); and Hydrology of the 410 Area (Area 27) at the Nevada Test Site.

Status of rf superconductivity at Argonne National Laboratory

International Nuclear Information System (INIS)

Markovich, P.M.; Shepard, K.W.; Zinkann, G.P.

1987-01-01

This paper reports the status of hardware development for the linac portion of the Argonne tandem-linac accelerator system (ATLAS). The ATLAS superconducting linac consists of an independent-phased array of 45 superconducting niobium resonators of the split-ring type. The linac has been operating in its present form since 1985, on a 24-hours per day, 5 days per week schedule. An upgrade of the ATLAS system is currently under construction the positive-ion injector (PII). The PII system will consist of an ECR positive-ion source mounted on a high-voltage platform injecting a very-low-velocity superconducting linac. The completed system will provide for the acceleration of beams of mass up to uranium, and will replace the tandem electrostatic accelerator as the injector for ATLAS. The status of resonator development for the superconducting linac is reported in this paper. Accelerating gradients in the existing ATLAS linac are currently limited by excessive heating and rf loss in the fast-tuning system associated with each superconducting resonator. Development of an upgraded fast-tuning system is also reported here. 7 refs., 5 figs

200 area effluent treatment facility opertaional test report

International Nuclear Information System (INIS)

Crane, A.F.

1995-01-01

This document reports the results of the 200 Area Effluent Treatment Facility (200 Area ETF) operational testing activities. These Operational testing activities demonstrated that the functional, operational and design requirements of the 200 Area ETF have been met and identified open items which require retesting

Final Project Report on RCCS Testing with Air-based NSTF

Energy Technology Data Exchange (ETDEWEB)

Lisowski, Darius D. [Argonne National Lab. (ANL), Argonne, IL (United States); Gerardi, Craig D. [Argonne National Lab. (ANL), Argonne, IL (United States); Kilsdonk, Dennis J. [Argonne National Lab. (ANL), Argonne, IL (United States); Bremer, Nathan C. [Argonne National Lab. (ANL), Argonne, IL (United States); Lomperski, Stephen W. [Argonne National Lab. (ANL), Argonne, IL (United States); Hu, Rui [Argonne National Lab. (ANL), Argonne, IL (United States); Kraus, Adam R. [Argonne National Lab. (ANL), Argonne, IL (United States); Bucknor, Matthew D. [Argonne National Lab. (ANL), Argonne, IL (United States); Lv, Qiuping [Argonne National Lab. (ANL), Argonne, IL (United States); Lee, Taeseung [Argonne National Lab. (ANL), Argonne, IL (United States); Farmer, Mitchell T. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-08-01

The following report serves as a comprehensive summary of the air-based portion of the Natural convection Shutdown heat removal Test Facility (NSTF) program at Argonne National Laboratory (Argonne). Initiated in 2005 to generate validation data for the Next Generation Nuclear Plant (NGNP), the project was centered on an experimental testing program to study the behavior and bound the performance of Reactor Cavity Cooling System (RCCS) concepts. Parallel modeling and simulation efforts also have been performed to guide the design, fabrication, and operation of NSTF, as well as to assess the suitability of analysis methods for natural convection systems. The program operates under support from the Department of Energy (DOE) Office of Advanced Reactor Technologies (ART), and maintained compliance with NQA-1 2008 with 2009a in both administrative and technical portions of program activities.

Innovative environmental restoration and waste management technologies at Argonne National Laboratory

International Nuclear Information System (INIS)

Helt, J.E.

1993-01-01

Cleanup of contaminated sites and management of wastes have become major efforts of the US Department of Energy. Argonne National Laboratory (ANL) is developing several new technologies to meet the needs of this national effort. Some of these efforts are being done in collaboration with private sector firms. An overview of the ANL and private sector efforts will be presented. The following four specific technologies will be discussed in detail: (1) a minimum additive waste stabilization (MAWS) system for treating actinide-contaminated soil and groundwater; (2) a magnetic separation system, also for cleanup of actinide-contaminated soil and groundwater; (3) a mobile evaporator/concentrator system for processing aqueous radioactive and mixed waste; and (4) a continuous emission monitor for ensuring that waste incineration meets environmental goals

Transforming Argonne's waste management organization - the road to energy quality

International Nuclear Information System (INIS)

Torres, T.A.; Sodaro, M.A.; Thuot, J.R.

1996-01-01

Argonne National Laboratory's (ANL's) Waste Management Department began its journey to excellence in 1990. The department was organized to provide for waste cleanup, waste handling, decontamination, and other services. The staff was principally workers and foremen with few professional staff. The department has transitioned into a highly effective organization that has competed for the President's Energy Quality Award. The department is currently staffed by 58 people, including professional staff and waste mechanics. The department began by recognizing and addressing the problems that existed: There was no formal waste safety program or waste reduction culture. Formal procedures did not cover all aspects of waste operations, waste handling procedures and acceptance criteria were out of date, and the Waste Management Department did not have a customer-centered culture. The department began a step by step program to improve the waste management organization

FY 2017 Status of Sodium Freezing and Remelting Tests

Energy Technology Data Exchange (ETDEWEB)

Lv, Q. [Argonne National Lab. (ANL), Argonne, IL (United States); Boron, E. [Argonne National Lab. (ANL), Argonne, IL (United States); Momozaki, Y. [Argonne National Lab. (ANL), Argonne, IL (United States); Chojnowski, D. B. [Argonne National Lab. (ANL), Argonne, IL (United States); Sienicki, J. J. [Argonne National Lab. (ANL), Argonne, IL (United States); Reed, C. B. [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-09-15

The Sodium Freezing and Remelting experiment facility at Argonne National Laboratory has been significantly modified and improved. The main improvement was replacement of the two original stainless steel test sections that had strain gages limited by their bonds to the stainless steel to maximum temperatures of 350°C with a single new test section with strain gages that can be utilized up to 980°C and a thin wall to enhance measured strains. Wetting of stainless steel by sodium within a practical time of one to a few days is expected to require temperatures of 450°C or greater. Thus, the higher temperature strain gages enable wetting in a short time of a few days. Wetting below 350°C would have required an impractically long time of at least weeks. Other improvements included upgrading of the loop configuration, incorporation of a cold finger to purify sodium, a new data acquisition system, and reinstallation of the many heaters, heater controllers, and thermocouples. After the loop had been heated to 400°C for about two hours, an initial sodium freezing test was conducted. It is thought that the sodium might have at least partially wetted the stainless steel wall under these conditions. The strain gage measurements indicate that an incremental step inward deformation of the test section thin wall occurred as the temperature decreased through the sodium freezing temperature. This behavior is consistent with sodium initially adhering to the stainless steel inner wall but breaking away from the wall as the freezing sodium contracted. Conduct of additional sodium freezing tests under well wetted conditions was prevented as a result of stoppage of all electrical work at Argonne by the Laboratory Director on July 25, 2017. A pathway to resuming electrical work is now in place at Argonne and additional sodium freezing testing will resume next fiscal year.

Analysis of eight argonne premium coal samples by X-ray fluorescence spectrometry

Science.gov (United States)

Evans, J.R.; Sellers, G.A.; Johnson, R.G.; Vivit, D.V.; Kent, J.

1990-01-01

X-ray fluorescence spectrometric methods were used in the analysis of eight Argonne Premium Coal Samples. Trace elements (Cr, Ni, Cu, Zn, Rb, Sr, Y, Zr, Nb, Ba, La, and Ce) in coal ash were determined by energy-dispersive X-ray fluorescence spectrometry; major elements (Na, Mg, Al, Si, P, S, K, Ca, Ti, Mn, and Fe) in coal ash and trace elements (Cl and P) in whole coal were determined by wavelength-dispersive X-ray fluorescence spectrometry. The results of this study will be used in a geochemical database compiled for these materials from various analytical techniques. The experimental XRF methods and procedures used to determine these major and trace elements are described.

Status report on the Advanced Photon Source Project at Argonne National Laboratory

International Nuclear Information System (INIS)

Huebner, R.H. Sr.

1989-01-01

The Advanced Photon Source at Argonne National Laboratory is designed as a national synchrotron radiation user facility which will provide extremely bright, highly energetic x-rays for multidisciplinary research. When operational, the Advanced Photon Source will accelerate positrons to a nominal energy of 7 GeV. The positrons will be manipulated by insertion devices to produce x-rays 10,000 times brighter than any currently available for research. Accelerator components, insertion devices, optical elements, and optical-element cooling schemes have been and continue to be the subjects of intensive research and development. A call for Letters of Intent from prospective users of the Advanced Photon Source has resulted in a substantial response from industrial, university, and national laboratory researchers

Yucca Mountain Project - Argonne National Laboratory annual progress report, FY 1994

Energy Technology Data Exchange (ETDEWEB)

Bates, J.K.; Fortner, J.A.; Finn, P.A.; Wronkiewicz, D.J.; Hoh, J.C.; Emery, J.W.; Buck, E.C.; Wolf, S.F.

1995-02-01

This document reports on the work done by the Nuclear Waste Management Section of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1993-September 1994. Studies have been performed to evaluate the performance of nuclear waste glass and spent fuel samples under unsaturated conditions (low volume water contact) that are likely to exist in the Yucca Mountain environment being considered as a potential site for a high-level waste repository. Tests with simulated waste glasses have been in progress for over eight years and demonstrate that actinides from initially fresh glass surfaces will be released as a result of the spallation of reacted glass layers from the surface, as the small volume of water passes over the waste form. Studies are also underway to evaluate the performance of spent fuel samples and unirradiated UO{sub 2} in projected repository conditions. Tests with UO{sub 2} have been ongoing for nine years and show that the oxidation of UO{sub 2} occurs rapidly, and the resulting paragenetic sequence of secondary phases that form on the sample surface is similar to that observed in natural analogues. The reaction of spent fuel samples under conditions similar to those used with UO{sub 2} have been in progress for nearly two years, and the results suggest that spent fuel follows the same reaction progress as UO{sub 2}. The release of individual fission products and transuranic elements was not congruent, with the release being controlled by the formation of small particles or colloids that are suspended in solution and transported away from the waste form. The reaction progress depends on the composition of the spent fuel samples used and, likely, on the composition of the groundwater that contacts the waste form.

Reduced enrichment for research and test reactors: Proceedings

International Nuclear Information System (INIS)

1993-07-01

The 15th annual Reduced Enrichment for Research and Test Reactors (RERTR) international meeting was organized by Ris oe National Laboratory in cooperation with the International Atomic Energy Agency and Argonne National Laboratory. The topics of the meeting were the following: National Programs, Fuel Fabrication, Licensing Aspects, States of Conversion, Fuel Testing, and Fuel Cycle. Individual papers have been cataloged separately

Reduced enrichment for research and test reactors: Proceedings

Energy Technology Data Exchange (ETDEWEB)

1993-07-01

The 15th annual Reduced Enrichment for Research and Test Reactors (RERTR) international meeting was organized by Ris{o} National Laboratory in cooperation with the International Atomic Energy Agency and Argonne National Laboratory. The topics of the meeting were the following: National Programs, Fuel Fabrication, Licensing Aspects, States of Conversion, Fuel Testing, and Fuel Cycle. Individual papers have been cataloged separately.

Argonne National Laboratory high-performance network support of APS experiments

International Nuclear Information System (INIS)

Knott, M.J.; McMahon, R.J.

1995-01-01

Under the Scientific Facilities Initiative, IPNS is planning to double its operation to 32 weeks/yr. Additional scientific and technical support staff will be added for the greatly expanded user program. The IPNS Upgrade Feasibility Study was published in April 1995 and is a thoroughly documented study on a 1-MW pulsed spallation neutron source at Argonne, including cost and schedule. A new booster target ( 235 U-Mo alloy) has been designed that will increase the neutron flux by a factor of ∼3 and construction will begin soon. A new small angle diffractometer (SAND) is in the final stages of commissioning, a prototype inelastic scattering spectrometer for Chemical Excitations (CHEX) was recently constructed and an upgraded quasielastic spectrometer (QENS) has been designed. IPNS has gained considerable operating experience with solid methane moderators, including controlled heating at periodic intervals in order to anneal the accumulated radiation induced stored energy

Argonne National Laboratory high-performance network support of APS experiments

Energy Technology Data Exchange (ETDEWEB)

Knott, M.J.; McMahon, R.J.

1995-12-31

Under the Scientific Facilities Initiative, IPNS is planning to double its operation to 32 weeks/yr. Additional scientific and technical support staff will be added for the greatly expanded user program. The IPNS Upgrade Feasibility Study was published in April 1995 and is a thoroughly documented study on a 1-MW pulsed spallation neutron source at Argonne, including cost and schedule. A new booster target ({sup 235}U-Mo alloy) has been designed that will increase the neutron flux by a factor of {approximately}3 and construction will begin soon. A new small angle diffractometer (SAND) is in the final stages of commissioning, a prototype inelastic scattering spectrometer for Chemical Excitations (CHEX) was recently constructed and an upgraded quasielastic spectrometer (QENS) has been designed. IPNS has gained considerable operating experience with solid methane moderators, including controlled heating at periodic intervals in order to anneal the accumulated radiation induced stored energy.

Results of thermal test of metallic molybdenum disk target and fast-acting valve testing

Energy Technology Data Exchange (ETDEWEB)

Virgo, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Chemerisov, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Gromov, R. [Argonne National Lab. (ANL), Argonne, IL (United States); Jonah, C. [Argonne National Lab. (ANL), Argonne, IL (United States); Vandegrift, G. F. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-12-01

This report describes the irradiation conditions for thermal testing of helium-cooled metallic disk targets that was conducted on March 9, 2016, at the Argonne National Laboratory electron linac. The four disks in this irradiation were pressed and sintered by Oak Ridge National Laboratory from molybdenum metal powder. Two of those disks were instrumented with thermocouples. Also reported are results of testing a fast-acting-valve system, which was designed to protect the accelerator in case of a target-window failure.

Continuous Improvement in Battery Testing at the NASA/JSC Energy System Test Area

Science.gov (United States)

Boyd, William; Cook, Joseph

2003-01-01

The Energy Systems Test Area (ESTA) at the Lyndon B. Johnson Space Center in Houston, Texas conducts development and qualification tests to fulfill Energy System Division responsibilities relevant to ASA programs and projects. EST A has historically called upon a variety of fluid, mechanical, electrical, environmental, and data system capabilities spread amongst five full-service facilities to test human and human supported spacecraft in the areas of propulsion systems, fluid systems, pyrotechnics, power generation, and power distribution and control systems. Improvements at ESTA are being made in full earnest of offering NASA project offices an option to choose a thorough test regime that is balanced with cost and schedule constraints. In order to continue testing of enabling power-related technologies utilized by the Energy System Division, an especially proactive effort has been made to increase the cost effectiveness and schedule responsiveness for battery testing. This paper describes the continuous improvement in battery testing at the Energy Systems Test Area being made through consolidation, streamlining, and standardization.

200 Area treated effluent disposal facility operational test report

International Nuclear Information System (INIS)

Crane, A.F.

1995-01-01

This document reports the results of the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These completed operational testing activities demonstrated the functional, operational and design requirements of the 200 Area TEDF have been met

Computer-based accountability system (Phase I) for special nuclear materials at Argonne-West

International Nuclear Information System (INIS)

Ingermanson, R.S.; Proctor, A.E.

1982-05-01

An automated accountability system for special nuclear materials (SNM) is under development at Argonne National Laboratory-West. Phase I of the development effort has established the following basic features of the system: a unique file organization allows rapid updating or retrieval of the status of various SNM, based on batch numbers, storage location, serial number, or other attributes. Access to the program is controlled by an interactive user interface that can be easily understood by operators who have had no prior background in electronic data processing. Extensive use of structured programming techniques make the software package easy to understand and to modify for specific applications. All routines are written in FORTRAN

Increasing the transformer ratio at the Argonne wakefield accelerator

International Nuclear Information System (INIS)

Power, J.G.; Conde, M.; Liu, W.; Yusof, Z.; Gai, W.; Jing, C.; Kanareykin, A.

2011-01-01

The transformer ratio is defined as the ratio of the maximum energy gain of the witness bunch to the maximum energy loss experienced by the drive bunch (or a bunch within a multidrive bunch train). This plays an important role in the collinear wakefield acceleration scheme. A high transformer ratio is desirable since it leads to a higher overall efficiency under similar conditions (e.g. the same beam loading, the same structure, etc.). One technique to enhance the transformer ratio beyond the ordinary limit of 2 is to use a ramped bunch train. The first experimental demonstration observed a transformer ratio only marginally above 2 due to the mismatch between the drive microbunch length and the frequency of the accelerating structure (C. Jing, A. Kanareykin, J. Power, M. Conde, Z. Yusof, P. Schoessow, and W. Gai, Phys. Rev. Lett. 98, 144801 (2007)). Recently, we revisited this experiment with an optimized microbunch length using a UV laser stacking technique at the Argonne Wakefield Accelerator facility and measured a transformer ratio of 3.4. Measurements and data analysis from these experiments are presented in detail.

Radioactive waste isolation in salt: rationale and methodology for Argonne-conducted reviews of site characterization programs

International Nuclear Information System (INIS)

Harrison, W.; Ditmars, J.D.; Tisue, M.W.; Hambley, D.F.; Fenster, D.F.; Rote, D.M.

1985-07-01

Both regulatory and technical concerns must be addressed in Argonne-conducted peer reviews of site characterization programs for individual sites for a high-level radioactive waste repository in salt. This report describes the regulatory framework within which reviews must be conducted and presents background information on the structure and purpose of site characterization programs as found in US Nuclear Regulatory Commission (NRC) Regulatory Guide 4.17 and Title 10, Part 60, of the Code of Federal Regulations. It also presents a methodology to assist reviewers in addressing technical concerns relating to their respective areas of expertise. The methodology concentrates on elements of prime importance to the US Department of Energy's advocacy of a given salt repository system during the NRC licensing process. Instructions are given for reviewing 12 site characterization program elements, starting with performance objectives, performance issues, and levels of performance of repository subsystem components; progressing through performance assessment; and ending with plans for data acquisition and evaluation. The success of a site characterization program in resolving repository performance issues will be determined by judging the likelihood that the proposed data acquisition activities will reduce uncertainties in the performance predictions. 8 refs., 3 figs., 5 tabs

Safety analysis of IFR fuel processing in the Argonne National Laboratory Fuel Cycle Facility

International Nuclear Information System (INIS)

Charak, I; Pedersen, D.R.; Forrester, R.J.; Phipps, R.D.

1993-01-01

The Integral Fast Reactor (IFR) concept developed by Argonne National Laboratory (ANL) includes on-site processing and recycling of discharged core and blanket fuel materials. The process is being demonstrated in the Fuel Cycle Facility (FCF) at ANL's Idaho site. This paper describes the safety analyses that were performed in support of the FCF program; the resulting safety analysis report was the vehicle used to secure authorization to operate the facility and carry out the program, which is now under way. This work also provided some insights into safety-related issues of a commercial IFR fuel processing facility. These are also discussed

The Chemical Technology Division at Argonne National Laboratory: Applying chemical innovation to environmental problems

International Nuclear Information System (INIS)

1995-01-01

The Chemical Technology Division is one of the largest technical divisions at Argonne National Laboratory, a leading center for research and development related to energy and environmental issues. Since its inception in 1948, the Division has pioneered in developing separations processes for the nuclear industry. The current scope of activities includes R ampersand D on methods for disposing of radioactive and hazardous wastes and on energy conversion processes with improved efficiencies, lower costs, and reduced environmental impact. Many of the technologies developed by CMT can be applied to solve manufacturing as well as environmental problems of industry

Report to users of ATLAS [Argonne Tandem-Line Accelerator System

International Nuclear Information System (INIS)

Ahmad, I.; Glagola, B.

1987-03-01

The operation and development of ATLAS are reported, including accelerator improvements. Particularly noted is an upgrade to extend the mass range of projectiles up to uranium and to increase the beam intensity by at least two orders of magnitude for all ions. Meetings are discussed, particularly of the Program Advisory Committee and the User Group Executive Committee. Some basic information is provided for users planning to run experiments at ATLAS, including a table of beams available. The data acquisition system for ATLAS, DAPHNE, is discussed, as are the following experimental facilities: the Argonne-Notre Dame Gamma Ray Facility, a proposal submitted for constructing a large-acceptance Fragment Mass Analyzer. Brief summaries are provided of some recent experiments for which data analysis is complete. Experiments performed during the period from June 1, 1986 to January 31, 1987 are tabulated, providing the experiment number, scientists, institution, experiment name, number of days, beam, and energy

Report to users of ATLAS (Argonne Tandem-Line Accelerator System)

Energy Technology Data Exchange (ETDEWEB)

Ahmad, I.; Glagola, B. (eds.)

1987-03-01

The operation and development of ATLAS are reported, including accelerator improvements. Particularly noted is an upgrade to extend the mass range of projectiles up to uranium and to increase the beam intensity by at least two orders of magnitude for all ions. Meetings are discussed, particularly of the Program Advisory Committee and the User Group Executive Committee. Some basic information is provided for users planning to run experiments at ATLAS, including a table of beams available. The data acquisition system for ATLAS, DAPHNE, is discussed, as are the following experimental facilities: the Argonne-Notre Dame Gamma Ray Facility, a proposal submitted for constructing a large-acceptance Fragment Mass Analyzer. Brief summaries are provided of some recent experiments for which data analysis is complete. Experiments performed during the period from June 1, 1986 to January 31, 1987 are tabulated, providing the experiment number, scientists, institution, experiment name, number of days, beam, and energy. (LEW)

Argonne National Laboratory-east site environmental report for calendar year 1988

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.

1989-04-01

The results of the environmental monitoring program at Argonne National Laboratory (ANL) for 1988 are presented and discussed. Sample collections were made on the site, at the site boundary, and off the ANL site for comparison purposes. Measurements were made for a variety of radionuclides in air, surface water, ground water, soil, grass, bottom sediment, and milk. Samples were also analyzed for a variety of chemical constituents in surface water, ground water, and ANL effluent water. External penetrating radiation doses were also measured. The potential for radiation exposure to off-site population groups is estimated. The results of the program are interpreted in terms of the origin of the radioactive and chemical substances and are compared with applicable environmental quality standards. A United States Department of Energy dose calculation methodology, is used in this report. 28 refs., 9 figs., 81 tabs

Conceptual design of the Argonne 6-GeV synchrotron light source

International Nuclear Information System (INIS)

Cho, Y.; Crosbie, E.; Khoe, T.

1985-01-01

The Argonne National Laboratory Synchrotron Light Source Storage Ring is designed to have a natural emittance of 6.5 X 10 -9 m for circulating 6-GeV positrons. Thirty of the 32 long straight sections, each 6.5-m long, will be available for synchrotron light insertion devices. A circulating positron current of 300 mA can be injected in about 8 min. from a booster synchrotron operating with a repetition time of 1.2 sec. The booster synchrotron will contain two different rf systems. The lower frequency system (38.97 MHz) will accept positrons from a 360-MeV linac and will accelerate them to 2.25 GeV. The higher frequency system (350.76 MHz) will accelerate the positrons to 6 GeV. The positrons will be produced from a 300-MeV electron beam on a tungsten target

Radioactive waste isolation in salt: Peer review of the Office of Nuclear Waste Isolation's draft report on a multifactor test design to investigate uniform corrosion of low-carbon steel

International Nuclear Information System (INIS)

Paddock, R.A.; Lerman, A.; Ditmars, J.D.; Macdonald, D.D.; Peerenboom, J.P.; Was, G.S.; Harrison, W.

1987-01-01

This report documents Argonne National Laboratory's review of an internal technical memorandum prepared by Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) entitled Multifactor Test Design to Investigate Uniform Corrosion of Low-Carbon Steel in a Nuclear Waste Salt Repository Environment. The several major areas of concern identified by peer review panelists are important to the credibility of the test design proposed in the memorandum and are to adequately addressed there. These areas of concern, along with specific recommendations to improve their treatment, are discussed in detail in Sec. 2 of this report. The twenty recommendations, which were abstracted from those discussions, are presented essentially in the order in which they are introduced in Sec. 2

Argonne National Laboratory, High Energy Physics Division: Semiannual report of research activities, July 1, 1986-December 31, 1986

International Nuclear Information System (INIS)

1987-01-01

This paper discusses the research activity of the High Energy Physics Division at the Argonne National Laboratory for the period, July 1986-December 1986. Some of the topics included in this report are: high resolution spectrometers, computational physics, spin physics, string theories, lattice gauge theory, proton decay, symmetry breaking, heavy flavor production, massive lepton pair production, collider physics, field theories, proton sources, and facility development

ARDISC (Argonne Dispersion Code): computer programs to calculate the distribution of trace element migration in partially equilibrating media

International Nuclear Information System (INIS)

Strickert, R.; Friedman, A.M.; Fried, S.

1979-04-01

A computer program (ARDISC, the Argonne Dispersion Code) is described which simulates the migration of nuclides in porous media and includes first order kinetic effects on the retention constants. The code allows for different absorption and desorption rates and solves the coupled migration equations by arithmetic reiterations. Input data needed are the absorption and desorption rates, equilibrium surface absorption coefficients, flow rates and volumes, and media porosities

Proceedings of the 1988 International Meeting on Reduced Enrichment for Research and Test Reactors

Energy Technology Data Exchange (ETDEWEB)

1993-07-01

The international effort to develop and implement new research reactor fuels utilizing low-enriched uranium, instead of highly- enriched uranium, continues to make solid progress. This effort is the cornerstone of a widely shared policy aimed at reducing, and possibly eliminating, international traffic in highly-enriched uranium and the nuclear weapon proliferation concerns associated with this traffic. To foster direct communication and exchange of ideas among the specialists in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at Argonne National Laboratory, sponsored this meeting as the eleventh of a series which began 1978. Individual papers presented at the meeting have been cataloged separately.

Proceedings of the 1988 International Meeting on Reduced Enrichment for Research and Test Reactors

International Nuclear Information System (INIS)

1993-07-01

The international effort to develop and implement new research reactor fuels utilizing low-enriched uranium, instead of highly- enriched uranium, continues to make solid progress. This effort is the cornerstone of a widely shared policy aimed at reducing, and possibly eliminating, international traffic in highly-enriched uranium and the nuclear weapon proliferation concerns associated with this traffic. To foster direct communication and exchange of ideas among the specialists in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at Argonne National Laboratory, sponsored this meeting as the eleventh of a series which began 1978. Individual papers presented at the meeting have been cataloged separately

Survey of biomedical and environental data bases, models, and integrated computer systems at Argonne National Laboratory

International Nuclear Information System (INIS)

Murarka, I.P.; Bodeau, D.J.; Scott, J.M.; Huebner, R.H.

1978-08-01

This document contains an inventory (index) of information resources pertaining to biomedical and environmental projects at Argonne National Laboratory--the information resources include a data base, model, or integrated computer system. Entries are categorized as models, numeric data bases, bibliographic data bases, or integrated hardware/software systems. Descriptions of the Information Coordination Focal Point (ICFP) program, the system for compiling this inventory, and the plans for continuing and expanding it are given, and suggestions for utilizing the services of the ICFP are outlined

Survey of biomedical and environental data bases, models, and integrated computer systems at Argonne National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Murarka, I.P.; Bodeau, D.J.; Scott, J.M.; Huebner, R.H.

1978-08-01

This document contains an inventory (index) of information resources pertaining to biomedical and environmental projects at Argonne National Laboratory--the information resources include a data base, model, or integrated computer system. Entries are categorized as models, numeric data bases, bibliographic data bases, or integrated hardware/software systems. Descriptions of the Information Coordination Focal Point (ICFP) program, the system for compiling this inventory, and the plans for continuing and expanding it are given, and suggestions for utilizing the services of the ICFP are outlined.

Automated real-time testing (ARTT) for embedded control systems (ECS)

International Nuclear Information System (INIS)

Hawkins, J; Howard, R; Nguyen, H.

2001-01-01

Many of today's automated real-time testing systems for embedded systems were developed using expensive custom hardware and software. In this article they describe how to use commercially available off-the-shelf hardware and software to design and develop an automated real-time test systems for Embedded Programmable Logic Controller (PLC) Based Control Systems. The system development began with the implementation of the VALI/TEST Pro testing methodology as a means for structuring the testing. Using this methodology, they were able to decompose system requirement documents for a Personnel Safety System (PSS) into its high, intermediate and detail level requirements. next, the validation procedures for the PSS system were decomposed into testing units called builds, test runs and test cases. To measure the PSS system's test coverage three levels of system requirements were mapped to their respective unit level of test using a specially constructed validation matrix that was designed to handle over 150 test cases and requirements. All of the above work led to the development of an Automated Real-Time Test System (ARTTS) that is capable of performing complete black box testing in real-time for Embedded PLC Based Control Systems. Also note, that the PSS system under test and mentioned in this paper is located at the Advance Photon Source (APS) at Argonne National Laboratory Basic Energy Science Facility in Argonne, Illinois

ATLAS: a proposal for a precision heavy ion accelerator at Argonne National Laboratory

Energy Technology Data Exchange (ETDEWEB)

None

1978-02-01

The objective of the proposed Argonne Tandem-Linac Accelerator System (ATLAS) is to provide precision beams of heavy ions for nuclear physics research in the region of projectile energies comparable to nuclear binding energies (5-25 MeV/A). By using the demonstrated potential of superconducting rf technology, beams of exceptional quality and flexibility can be obtained. The system is designed to provide beams with tandem-like energy resolution and ease of energy variation, the energy range is comparable to that of a approx. 50 MV tandem and, in addition, the beam will be bunched into very short (approx. 50 psec) pulses, permitting fast-timing measurements that can open up major new experimental approaches.

ATLAS: a proposal for a precision heavy ion accelerator at Argonne National Laboratory

International Nuclear Information System (INIS)

1978-02-01

The objective of the proposed Argonne Tandem-Linac Accelerator System (ATLAS) is to provide precision beams of heavy ions for nuclear physics research in the region of projectile energies comparable to nuclear binding energies (5-25 MeV/A). By using the demonstrated potential of superconducting rf technology, beams of exceptional quality and flexibility can be obtained. The system is designed to provide beams with tandem-like energy resolution and ease of energy variation, the energy range is comparable to that of a approx. 50 MV tandem and, in addition, the beam will be bunched into very short (approx. 50 psec) pulses, permitting fast-timing measurements that can open up major new experimental approaches

Programmer's guide to the Argonne Coal Market Model. [USA; mathematical models

Energy Technology Data Exchange (ETDEWEB)

Guziel, K.A.; Krohm, G.C.; VanKuiken, J.C.; Macal, C.M.

1980-02-01

The Argonne Coal Market Model was developed as part of a comprehensive DOE study of coal-related environmental, health, and safety impacts. The model includes a high degree of regional detail on both supply and demand. Coal demand is input separately for industrial and utility users in each region, and coal supply in each region is characterized by a linearly increasing function relating increments of new mine capacity to the marginal cost of extraction. Rail transportation costs and control technology costs are estimated for each supply-demand link. A quadratic programming algorithm is used to optimize flow patterns for the system. This report documents the model for programmers and users interested in technical details of the computer code.

Seismic modifications to the hot suspect repair area Argonne National Laboratory, West

International Nuclear Information System (INIS)

Malik, L.E.; Harris, B.G.

1993-01-01

The ANL-W WIPP Waste Facility Enhancement Project required substantial remodeling and upgrades to the Hot Fuels Examination Facility (HFEF) building, including the Hot and Suspect Repair Area (HSRA). The HSRA is an enclosed single-stoned area inside the HFEF. It is separated into several compartments, some of which are used for handling radioactive materials. The HSRA roof consists of 18 GA steel Robertson Q decking with 1.5 in. concrete topping, and is utilized for storage. Braced steel frames support the HSRA roof, except at the north side, where the steel beams arc connected to the HFEF columns. The HSRA has hollow block masonry perimeter and interior walls. Seismic evaluations concluded that the HSRA did not have a competent seismic force resisting system. The structure was upgraded by decoupling it from the HFEF framing for N/S motions, modifying two existing braced frames, adding a now braced frame that can be removed temporarily during maintenance and strengthening the roof diaphragm by a unique modification consisting of special epoxy grout and steel plates installed over the existing concrete roof

400 Area/Fast Flux Test Facility

Data.gov (United States)

Federal Laboratory Consortium — The 400 Area at Hanford is home primarily to the Fast Flux Test Facility (FFTF), a DOE-owned, formerly operating, 400-megawatt (thermal) liquid-metal (sodium)-cooled...

Waste minimization and pollution prevention in D ampersand D operations at the Argonne National Laboratory-East site

International Nuclear Information System (INIS)

Boing, L.E.; Coffey, M.J.; Ditch, R.W.; Fellhauer, C.R.; Rose, R.W.

1996-01-01

Argonne National Laboratory (ANL) is implementing waste minimization and pollution prevention activities into its conduct of decontamination and decommissioning (D ampersand D) projects. Many of these activities are rather straight forward and simple approaches, yet they are often overlooked and not implemented as often as they should or could be. Specific activities involving recycling and reuse of materials and structures, which have proven useful in lowering decommissioning and disposal costs on D ampersand D projects at ANL are presented

Conceptual design of the Argonne 6-GeV synchrotron light source

International Nuclear Information System (INIS)

Cho, Y.; Crosbie, E.; Khoe, T.

1985-01-01

The Argonne National Laboratory Synchrotron Light Source Storage Ring is designed to have a natural emittance of 6.5 x 10 -9 m for circulating 6-GeV positrons. Thirty of the 32 long straight sections, each 6.5-m long, will be available for synchrotron light insertion devices. A circulating positron current of 300 mA can be injected in about 8 min. from a booster synchrotron operating with a repetition time of 1.2 sec. The booster synchrotron will contain two different RF systems. The lower frequency system (38.97 MHz) will accept positrons from a 360-MeV linac and will accelerate them to 2.25 GeV. The higher frequency system (350.76 MHz) will accelerate the positrons to 6 GeV. The positrons will be produced from a 300-MeV electron beam on a tungsten target. A conceptual layout is shown

Testing of pyrochemical centrifugal contactors

International Nuclear Information System (INIS)

Chow, L.S.; Carls, E.L.; Basco, J.K.; Johnson, T.R.

1996-01-01

A centrifugal contactor that performs oxidation and reduction exchange reactions between molten metals and salts at 500 degrees Centigrade has been tested successfully at Argonne National Laboratory (ANL). The design is based on contactors for aqueous- organic systems operation near room temperature. In tests to demonstrate the performance of the pyrocontactor, cadmium and LICl-KCl eutectic salt were the immiscible solvent phases, and rare earths were the distributing solutes. The tests showed that the pyrocontactor mixed and separated the phases well, with stage efficiencies approaching 99% at rotor speeds near 2700 rpm. The contactor ran smoothly and reliably over the entire range of speeds that was tested

Central Nevada Test Area Monitoring Report

International Nuclear Information System (INIS)

Brad Lyles; Jenny Chapman; John Healey; David Gillespie

2006-01-01

Water level measurements were performed and water samples collected from the Central Nevada Test Area model validation wells in September 2006. Hydraulic head measurements were compared to previous observations; the MV wells showed slight recovery from the drilling and testing operation in 2005. No radioisotopes exceeded limits set in the Corrective Action Decision Document/Corrective Action Plan, and no significant trends were observed when compared to previous analyses

Neutron source investigations in support of the cross section program at the Argonne Fast-Neutron Generator

International Nuclear Information System (INIS)

Meadows, J.W.; Smith, D.L.

1980-05-01

Experimental methods related to the production of neutrons for cross section studies at the Argonne Fast-Neutron Generator are reviewed. Target assemblies commonly employed in these measurements are described, and some of the relevant physical properties of the neutron source reactions are discussed. Various measurements have been performed to ascertain knowledge about these source reaction that is required for cross section data analysis purposes. Some results from these studies are presented, and a few specific examples of neutron-source-related corrections to cross section data are provided. 16 figures, 3 tables

Conceptual design of superconducting magnet systems for the Argonne Tokamak Experimental Power Reactor

International Nuclear Information System (INIS)

Wang, S.T.; Turner, L.R.; Mills, F.E.; DeMichele, D.W.; Smelser, P.; Kim, S.H.

1976-01-01

As an integral effort in the Argonne Tokamak Experimental Power Reactor Conceptual Design, the conceptual design of a 10-tesla, pure-tension superconducting toroidal-field (TF) coil system has been developed in sufficient detail to define a realistic design for the TF coil system that could be built based upon the current state of technology with minimum technological extrapolations. A conceptual design study on the superconducting ohmic-heating (OH) coils and the superconducting equilibrium-field (EF) coils were also completed. These conceptual designs are developed in sufficient detail with clear information on high current ac conductor design, cooling, venting provision, coil structural support and zero loss poloidal coil cryostat design. Also investigated is the EF penetration into the blanket and shield

100 Area excavation treatability test plan

International Nuclear Information System (INIS)

1993-08-01

This test plan documents the requirements for a treatability study on field radionuclide analysis and dust control techniques. These systems will be used during remedial actions involving excavation. The data from this treatability study will be used to support the feasibility study (FS) process. Excavation is one of the high-priority, near-term, treatability study needs identified in the program plan (DOE-RL 1992f). Excavation of contaminated soils and buried solid wastes is included in several of the alternatives identified in the 100 Area FS. Although a common activity, excavation has only been used occasionally at the Hanford Site for waste removal applications. The most recent applications are excavation of the 618-9 burial ground and partial remediation of the 316-5 process trenches (DOE-RL 1992a, 1992b). Both projects included excavation of soil and dust control (using water sprays). Excavation is a well-developed technology and equipment is readily available; however, certain aspects of the excavation process require testing before use in full-scale operations. These include the following: Measurement and control of excavation-generated dust and airborne contamination; verification of field analytical system capabilities; demonstration of soil removal techniques specific to the 100 Area waste site types and configurations. The execution of this treatability test may produce up to 500 yd 3 of contaminated soil, which will be used for future treatability tests. These tests may include soil washing with vitrification of the soil washing residuals. Other tests will be conducted if soil washing is not a viable alternative

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

International Nuclear Information System (INIS)

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

1993-01-01

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

Design Report for the ½ Scale Air-Cooled RCCS Tests in the Natural convection Shutdown heat removal Test Facility (NSTF)

Energy Technology Data Exchange (ETDEWEB)

Lisowski, D. D. [Argonne National Lab. (ANL), Argonne, IL (United States); Farmer, M. T. [Argonne National Lab. (ANL), Argonne, IL (United States); Lomperski, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Kilsdonk, D. J. [Argonne National Lab. (ANL), Argonne, IL (United States); Bremer, N. [Argonne National Lab. (ANL), Argonne, IL (United States); Aeschlimann, R. W. [Argonne National Lab. (ANL), Argonne, IL (United States)

2014-06-01

The Natural convection Shutdown heat removal Test Facility (NSTF) is a large scale thermal hydraulics test facility that has been built at Argonne National Laboratory (ANL). The facility was constructed in order to carry out highly instrumented experiments that can be used to validate the performance of passive safety systems for advanced reactor designs. The facility has principally been designed for testing of Reactor Cavity Cooling System (RCCS) concepts that rely on natural convection cooling for either air or water-based systems. Standing 25-m in height, the facility is able to supply up to 220 kW at 21 kW/m² to accurately simulate the heat fluxes at the walls of a reactor pressure vessel. A suite of nearly 400 data acquisition channels, including a sophisticated fiber optic system for high density temperature measurements, guides test operations and provides data to support scaling analysis and modeling efforts. Measurements of system mass flow rate, air and surface temperatures, heat flux, humidity, and pressure differentials, among others; are part of this total generated data set. The following report provides an introduction to the top level-objectives of the program related to passively safe decay heat removal, a detailed description of the engineering specifications, design features, and dimensions of the test facility at Argonne. Specifications of the sensors and their placement on the test facility will be provided, along with a complete channel listing of the data acquisition system.

200 Area Treated Effluent Disposal Facility operational test specification. Revision 2

International Nuclear Information System (INIS)

Crane, A.F.

1995-01-01

This document identifies the test specification and test requirements for the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These operational testing activities, when completed, demonstrate the functional, operational and design requirements of the 200 Area TEDF have been met. The technical requirements for operational testing of the 200 Area TEDF are defined by the test requirements presented in Appendix A. These test requirements demonstrate the following: pump station No.1 and associated support equipment operate both automatically and manually; pump station No. 2 and associated support equipment operate both automatically and manually; water is transported through the collection and transfer lines to the disposal ponds with no detectable leakage; the disposal ponds accept flow from the transfer lines with all support equipment operating as designed; and the control systems operate and status the 200 Area TEDF including monitoring of appropriate generator discharge parameters

Radioactive waste isolation in salt: Peer review of the Office of Nuclear Waste Isolation's draft report on a multifactor test design to investigate uniform corrosion of low-carbon steel

Energy Technology Data Exchange (ETDEWEB)

Paddock, R.A.; Lerman, A.; Ditmars, J.D.; Macdonald, D.D.; Peerenboom, J.P.; Was, G.S.; Harrison, W.

1987-01-01

This report documents Argonne National Laboratory's review of an internal technical memorandum prepared by Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) entitled Multifactor Test Design to Investigate Uniform Corrosion of Low-Carbon Steel in a Nuclear Waste Salt Repository Environment. The several major areas of concern identified by peer review panelists are important to the credibility of the test design proposed in the memorandum and are to adequately addressed there. These areas of concern, along with specific recommendations to improve their treatment, are discussed in detail in Sec. 2 of this report. The twenty recommendations, which were abstracted from those discussions, are presented essentially in the order in which they are introduced in Sec. 2.

Small UAS Test Area at NASA's Dryden Flight Research Center

Science.gov (United States)

Bauer, Jeffrey T.

2008-01-01

This viewgraph presentation reviews the areas that Dryden Flight Research Center has set up for testing small Unmanned Aerial Systems (UAS). It also reviews the requirements and process to use an area for UAS test.

Routine environmental reaudit of the Argonne National Laboratory - West

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

This report documents the results of the Routine Environmental Reaudit of the Argonne National Laboratory - West (ANL-W), Idaho Falls, Idaho. During this audit, the activities conducted by the audit team included reviews of internal documents and reports from previous audits and assessments; interviews with U.S. Department of Energy (DOE), U.S. Environmental Protection Agency (EPA), State of Idaho Department of Health and Welfare (IDHW), and DOE contractor personnel; and inspections and observations of selected facilities and operations. The onsite portion of the audit was conducted from October 11 to October 22, 1993, by the DOE Office of Environmental Audit (EH-24), located within the Office of Environment, Safety and Health (EH). DOE 5482.113, {open_quotes}Environment, Safety, and Health Appraisal Program,{close_quotes} established the mission of EH-24 to provide comprehensive, independent oversight of Department-wide environmental programs on behalf of the Secretary of Energy. The ultimate goal of EH-24 is enhancement of environmental protection and minimization of risk to public health and the environment. EH-24 accomplishes its mission by conducting systematic and periodic evaluations of the Department`s environmental programs within line organizations, and by utilizing supplemental activities that serve to strengthen self-assessment and oversight functions within program, field, and contractor organizations.

Argonne National Laboratory's thermal plume measurements: instruments and techniques

International Nuclear Information System (INIS)

Van Loon, L.S.; Frigo, A.A.; Paddock, R.A.

1977-12-01

Instrumentation and techniques were developed at Argonne National Laboratory for measuring the three-dimensional temperature structure of thermal plumes from power plants, along with the limnological, meteorological, and plant operating conditions affecting their behavior. The equipment and procedures were designed to provide field data for use in evaluating predictive models that describe thermal plume behavior, and over 100 sets of these data have been collected. The instrument systems and techniques employed in a typical thermal discharge survey are highly integrated. Continuous monitoring of ambient and plant conditions is coupled with plume mapping from a moving survey boat. The instantaneous location of the boat together with subsurface temperature measurements from a towed thermistor chain provide a quasisynoptic view of the plume structure. Real-time, onboard display of the boat path and vertical temperatures supply feedback to investigators for determining the extent and spatial resolution of measurements required. The unique design, reliability, accuracy, calibration, and historical development of the components of these integrated systems are described. Survey system interfaces with data handling and processing techniques are also explained. Special supportive studies to investigate plume dynamics, values of eddy diffusivities, time-temperature histories of water parcels in thermal plumes, and rapid changes in plume shape are also described along with instrumentation used

Routine environmental reaudit of the Argonne National Laboratory - West

International Nuclear Information System (INIS)

1996-01-01

This report documents the results of the Routine Environmental Reaudit of the Argonne National Laboratory - West (ANL-W), Idaho Falls, Idaho. During this audit, the activities conducted by the audit team included reviews of internal documents and reports from previous audits and assessments; interviews with U.S. Department of Energy (DOE), U.S. Environmental Protection Agency (EPA), State of Idaho Department of Health and Welfare (IDHW), and DOE contractor personnel; and inspections and observations of selected facilities and operations. The onsite portion of the audit was conducted from October 11 to October 22, 1993, by the DOE Office of Environmental Audit (EH-24), located within the Office of Environment, Safety and Health (EH). DOE 5482.113, open-quotes Environment, Safety, and Health Appraisal Program,close quotes established the mission of EH-24 to provide comprehensive, independent oversight of Department-wide environmental programs on behalf of the Secretary of Energy. The ultimate goal of EH-24 is enhancement of environmental protection and minimization of risk to public health and the environment. EH-24 accomplishes its mission by conducting systematic and periodic evaluations of the Department's environmental programs within line organizations, and by utilizing supplemental activities that serve to strengthen self-assessment and oversight functions within program, field, and contractor organizations

An Aerial Radiological Survey of Selected Areas of Area 18 - Nevada Test Site

International Nuclear Information System (INIS)

Lyons, Craig

2009-01-01

As part of the proficiency training for the Radiological Mapping mission of the Aerial Measuring System (AMS), a survey team from the Remote Sensing Laboratory-Nellis (RSL-Nellis) conducted an aerial radiological survey of selected areas of Area 18 of the Nevada Test Site (NTS) for the purpose of mapping man-made radiation deposited as a result of the Johnnie Boy and Little Feller I tests. The survey area centered over the Johnnie Boy ground zero but also included the ground zero and deposition area of the Little Feller I test, approximately 7,000 feet (2133 meters) southeast of the Johnnie Boy site. The survey was conducted in one flight. The completed survey covered a total of 4.0 square miles. The flight lines (with the turns) over the surveyed areas are presented in Figure 1. One 2.5-hour-long flight was performed at an altitude of 100 ft above ground level (AGL) with 200 foot flight-line spacing. A test-line flight was conducted near the Desert Rock Airstrip to ensure quality control of the data. The test line is not shown in Figure 1. However, Figure 1 does include the flight lines for a ''perimeter'' flight. The path traced by the helicopter flying over distinct roads within the survey area can be used to overlay the survey data on a base map or image. The flight survey lines were flown in an east-west orientation perpendicular to the deposition patterns for both sites. This technique provides better spatial resolution when contouring the data. The data were collected by the AMS data acquisition system (REDAR V) using an array of twelve 2-inch x 4-inch x 16-inch sodium iodide (NaI) detectors flown on-board a twin-engine Bell 412 helicopter. Data, in the form of gamma energy spectra, were collected every second over the course of the survey and were geo-referenced using a differential Global Positioning System. Spectral data allows the system to distinguish between ordinary fluctuations in natural background radiation levels and the signature produced by man

Closure plan for the Test Area North-726 chromate water storage and Test Area North-726A chromate treatment units

International Nuclear Information System (INIS)

Smith, P.J.; Van Brunt, K.M.

1992-11-01

This document describes the proposed plan for closure of the Test Area North-726 chromate water storage and Test Area North-726A chromate treatment units at the Idaho National Engineering Laboratory in accordance with the Resource Conservation and Recovery Act interim status closure requirements. The location, size, capacity, and history of the units are described, and their current status is discussed. The units will be closed by treating remaining waste in storage, followed by thorough decontamination of the systems. Sufficient sampling and analysis, and documentation of all activities will be performed to demonstrate clean closure

A comparative study of the systems for neutronics calculations used in Los Alamos Scientific Laboratory (LASL) and Argonne National Laboratory (ANL)

International Nuclear Information System (INIS)

Amorim, E.S. do; D'Oliveira, A.B.; Oliveira, E.C. de.

1980-11-01

A comparative study of the systems for neutronics calculations used in Los Alamos Scientific Laboratory (LASL) and Argonne National Laboratory (ANL) has been performed using benchmark results available in the literature, in order to analyse tghe convenience of using the respective codes MINX/NJOY and ETOE/MC 2 -2 for performing neutronics calculations in course at the Divisao de Estudos Avancados. (Author) [pt

Idaho National Engineering Laboratory waste area groups 1--7 and 10 Technology Logic Diagram

International Nuclear Information System (INIS)

O'Brien, M.C.; Meservey, R.H.; Little, M.; Ferguson, J.S.; Gilmore, M.C.

1993-09-01

The Technology Logic Diagram was developed to provide technical alternatives for environmental restoration projects at the Idaho National Engineering Laboratory. The diagram (three volumes) documents suggested solutions to the characterization, retrieval, and treatment phases of cleanup activities at contaminated sites within 8 of the laboratory's 10 waste area groups. Contaminated sites at the laboratory's Naval Reactor Facility and Argonne National Laboratory-West are not included in this diagram

Testing activities at the National Battery Test Laboratory

Science.gov (United States)

Hornstra, F.; Deluca, W. H.; Mulcahey, T. P.

The National Battery Test Laboratory (NBTL) is an Argonne National Laboratory facility for testing, evaluating, and studying advanced electric storage batteries. The facility tests batteries developed under Department of Energy programs and from private industry. These include batteries intended for future electric vehicle (EV) propulsion, electric utility load leveling (LL), and solar energy storage. Since becoming operational, the NBTL has evaluated well over 1400 cells (generally in the form of three- to six-cell modules, but up to 140-cell batteries) of various technologies. Performance characterization assessments are conducted under a series of charge/discharge cycles with constant current, constant power, peak power, and computer simulated dynamic load profile conditions. Flexible charging algorithms are provided to accommodate the specific needs of each battery under test. Special studies are conducted to explore and optimize charge procedures, to investigate the impact of unique load demands on battery performance, and to analyze the thermal management requirements of battery systems.

Argonne National Laboratory as an interface between physics and industry

International Nuclear Information System (INIS)

Sachs, R.G.

1976-01-01

Application of physics to industry requires the involvement of many other disciplines, including chemistry, material sciences, and many other fields of engineering; and the national laboratories in the United States have a mix of such disciplines particularly conducive to such transfer. They have participated in one of the most striking transfers of physics to industry in history, namely, the development of the nuclear power industry. Scientific feasibility of nuclear power was established when the first chain reaction was demonstrated at the Metallurgical Laboratory. Argonne National Laboratory as the successor to the Metallurgical Laboratory has played a major role in transferring the results of this physics experiment to industry, especially in demonstrating engineering feasibility of nuclear power. Major developments in industrial instrumentation have taken place in parallel with the development of nuclear energy, and many of these developments are applicable to other industrial systems as well. The responsibilities of the national laboratories have recently been extended into many energy technologies other than nuclear, offering them the opportunity to serve as an interface for transfer of physics into many new industries. A number of examples are cited. (author)

Benchmark physics tests in the metallic-fuelled assembly ZPPR-15

International Nuclear Information System (INIS)

McFarlane, H.F.; Brumbach, S.B.; Carpenter, S.G.; Collins, P.J.

1987-01-01

In the last two years a shift in emphasis to inherent safety and economic competitiveness has led to a resurgence in US interest in metallic-alloy fuels for LMRs. Argonne National Laboratory initiated an extensive testing program for metallic-fuelled LMR technology that has included benchmark physics as one component. The tests done in the ZPPR-15 Program produced the first physics results in over 20 years for a metal-composition LMR core

Reduced enrichment for research and test reactors: Proceedings

Energy Technology Data Exchange (ETDEWEB)

1988-05-01

The international effort to develop new research reactor fuel materials and designs based on the use of low-enriched uranium, instead of highly-enriched uranium, has made much progress during the eight years since its inception. To foster direct communication and exchange of ideas among the specialist in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the ninth of a series which began in 1978. All previous meetings of this series are listed on the facing page. The focus of this meeting was on the LEU fuel demonstration which was in progress at the Oak Ridge Research (ORR) reactor, not far from where the meeting was held. The visit to the ORR, where a silicide LEU fuel with 4.8 g A/cm/sup 3/ was by then in routine use, illustrated how far work has progressed.

Reduced enrichment for research and test reactors: Proceedings

International Nuclear Information System (INIS)

1988-05-01

The international effort to develop new research reactor fuel materials and designs based on the use of low-enriched uranium, instead of highly-enriched uranium, has made much progress during the eight years since its inception. To foster direct communication and exchange of ideas among the specialist in this area, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the ninth of a series which began in 1978. All previous meetings of this series are listed on the facing page. The focus of this meeting was on the LEU fuel demonstration which was in progress at the Oak Ridge Research (ORR) reactor, not far from where the meeting was held. The visit to the ORR, where a silicide LEU fuel with 4.8 g A/cm 3 was by then in routine use, illustrated how far work has progressed

Argonne National Laboratory-East site environmental report for calendar year 1989

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.

1990-04-01

This report discusses the results of the environmental monitoring program at Argonne National Laboratory (ANL) for 1989. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared. A variety of radionuclides were measured in air, surface water, groundwater, soil, grass, bottom sediment, and milk samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the monitoring program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations, is used in this report. This report also discusses progress being made on corrective actions and restoration projects from past activities. 27 refs., 7 figs., 75 tabs

Development of the rf linear accelerator test bed for heavy-ion fusion

International Nuclear Information System (INIS)

Watson, J.M.

1981-01-01

The amount of absorbed energy required by high gain deuterium-tritium targets for inertial confinement fusion reactors is now projected to be greater than 1 Megajoule. It has become apparent that a heavy ion fusion driver is the preferred choice in this scenario. To demonstrate this accelerator-based option, the national program has established two test beds: one at Argonne for the rf linac/storage ring approach, and one at Lawrence Berkeley Laboratory developing an induction linac. The Argonne Beam Development Facility (BDF) would consist of a 40 mA rf linac for Xe + 8 , a storage ring, and a 10 GeV synchrotron. The design and status of the BDF is described as well as future program options to demonstrate as many solutions as possible of the issues involved in this approach

Beam tests of the 12 MHz RFQ RIB injector for ATLAS

International Nuclear Information System (INIS)

Kaye, R. A.

1999-01-01

In recent tests without beam, the Argonne 12 MHz split-coaxial radio-frequency quadruple (RFQ) achieved a cw intervane voltage of more than 100 kV, the design operating voltage for the device. This voltage is sufficient for the RFQ to function as the first stage of a RIB injector for the Argonne Tandem Linear Accelerator System (ATLAS). Previously reported beam dynamics calculations for the structure predict longitudinal emittance growth of only a few keV·ns for beams of mass 132 and above with transverse emittance of 0.27 π mm·mrad (normalized). Such beam quality is not typical of RFQ devices. The work reported here is preparation for tests with beams of mass up to 132. Beam diagnostic stations are being developed to measure the energy gain and beam quality of heavy ions accelerated by the RFQ using the Dynamitron accelerator facility at the ANL Physics Division as the injector. Beam diagnostic development includes provisions for performing the measurements with both a Si charged-particle detector and an electrostatic energy spectrometer system

Prototype steam generator test at SCTI/ETEC. Acoustic program test plan

International Nuclear Information System (INIS)

Greene, D.A.; Thiele, A.; Claytor, T.N.

1981-10-01

This document is an integrated test plan covering programs at General Electric (ARSD), Rockwell International (RI) and Argonne National Laboratory (CT). It provides an overview of the acoustic leak detection test program which will be completed in conjunction with the prototype LMFBR steam generator at the Energy Technology Engineering Laboratory. The steam generator is installed in the Sodium Components Test Installation (SCTI). Two acoustic detection systems will be used during the test program, a low frequency system developed by GE-ARSD (GAAD system) and a high frequency system developed by RI-AI (HALD system). These systems will be used to acquire data on background noise during the thermal-hydraulic test program. Injection devices were installed during fabrication of the prototype steam generator to provide localized noise sources in the active region of the tube bundle. These injectors will be operated during the steam generator test program, and it will be shown that they are detected by the acoustic systems

Run-Beyond-Cladding-Breach (RBCB) test results for the Integral Fast Reactor (IFR) metallic fuels program

International Nuclear Information System (INIS)

Batte, G.L.; Hoffman, G.L.

1990-01-01

In 1984 Argonne National Laboratory (ANL) began an aggressive program of research and development based on the concept of a closed system for fast-reactor power generation and on-site fuel reprocessing, exclusively designed around the use of metallic fuel. This is the Integral Fast Reactor (IFR). Although the Experimental Breeder Reactor-II (EBR-II) has used metallic fuel since its creation 25 yeas ago, in 1985 ANL began a study of the characteristics and behavior of an advanced-design metallic fuel based on uranium-zirconium (U-Zr) and uranium-plutonium-zirconium (U-Pu-Zr) alloys. During the past five years several areas were addressed concerning the performance of this fuel system. In all instances of testing the metallic fuel has demonstrated its ability to perform reliably to high burnups under varying design conditions. This paper will present one area of testing which concerns the fuel system's performance under breach conditions. It is the purpose of this paper to document the observed post-breach behavior of this advanced-design metallic fuel. 2 figs., 1 tab

100 area excavation treatability test plan

International Nuclear Information System (INIS)

1993-05-01

This test plan documents the requirements for a treatability study on field radionuclide analysis and dust control techniques. These systems will be used during remedial actions involving excavation. The data from this treatability study will be used to support the feasibility study (FS) process. Development and screening of remedial alternatives for the 100 Area, using existing data, have been completed and are documented in the 100 Area Feasibility Study, Phases 1 and 2 (DOE-RL 1992a). Based on the results of the FS, the Treatability Study Program Plan (DOE-RL 1992b) identifies and prioritizes treatability studies for the 100 Area. The data from the treatability study program support future focused FS, interim remedial measures (IRM) selection, operable unit final remedy selection, remedial design, and remedial actions. Excavation is one of the high-priority, near-term, treatability study needs identified in the program plan (DOE-RL 1992b). Excavation of contaminated soils and buried solid wastes is included in several of the alternatives identified in the 100 Area FS. Although a common activity, excavation has only been used occasionally at the Hanford Site for waste removal applications

Determination of area reduction rate by continuous ball indentation test

International Nuclear Information System (INIS)

Zou, Bin; Guan, Kai Shu; Wu, Sheng Bao

2016-01-01

Rate of area reduction is an important mechanical property to appraise the plasticity of metals, which is always obtained from the uniaxial tensile test. A methodology is proposed to determine the area reduction rate by continuous ball indentation test technique. The continuum damage accumulation theory has been adopted in this work to identify the failure point in the indentation. The corresponding indentation depth of this point can be obtained and used to estimate the area reduction rate. The local strain limit criterion proposed in the ASME VIII-2 2007 alternative rules is also adopted in this research to convert the multiaxial strain of indentation test to uniaxial strain of tensile test. The pile-up and sink-in phenomenon which can affect the result significantly is also discussed in this paper. This method can be useful in engineering practice to evaluate the material degradation under severe working condition due to the non-destructive nature of ball indentation test. In order to validate the method, continuous ball indentation test is performed on ferritic steel 16MnR and ASTM (A193B16), then the results are compared with that got from the traditional uniaxial tensile test.

Pure tension superconducting toroidal-field coil system design studies for the Argonne Experimental Power Reactor

International Nuclear Information System (INIS)

Wang, S.T.; Purcell, J.R.; Demichele, D.W.; Turner, L.R.

1975-11-01

As part of the Argonne Tokamak Experimental Power Reactor (TEPR) design studies, a toroidal field (TF) coil system has been designed. NbTi was chosen as the most suitable superconductor and 8T was regarded as a practical peak field level in this study. The 16-coil design was chosen as a reasonable compromise between 2 percent field ripple and 3 m access gap. To minimize the coil structure and the bending moments on the conductor, a pure tension coil shape is necessary. A correct approach for determining the pure tension coil profile in a bumpy TF coil system is given. Verification of the pure tension coil by a three-dimensional stress analysis is presented. For coil quench protection, a series-connected scheme is proposed

Effects of potential geothermal development in the Corwin Springs Known Geothermal Resources Area, Montana, on the thermal features of Yellowstone National Park. Water Resources Investigation

International Nuclear Information System (INIS)

Sorey, M.L.

1991-01-01

A two-year study by the U.S. Geological Survey, in collaboration with the National Park Service, Argonne National Laboratory, and Los Alamos National Laboratory was initiated in 1988 to determine the effects of potential geothermal development in the Corwin Springs Known Geothermal Resources Area (KGRA), Montana, on the thermal features of Yellowstone National Park. The study addressed three principal issues: (1) the sources of thermal water in the hot springs at Mammoth, La Duke, and Bear Creek; (2) the degree of subsurface connection between these areas; and (3) the effects of geothermal development in the Corwin Springs KGRA on the Park's thermal features. The authors investigations included, but were not limited to, geologic mapping, electrical geophysical surveys, chemical sampling and analyses of waters and rocks, determinations of the rates of discharge of various thermal springs, and hydrologic tracer tests

Argonne National Laboratory site environmental report for calendar year 2004.

Energy Technology Data Exchange (ETDEWEB)

Golchert, N. W.; Kolzow, R. G.

2005-09-02

This report discusses the accomplishments of the environmental protection program at Argonne National Laboratory (ANL) for calendar year 2004. The status of ANL environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with the progress of environmental corrective actions and restoration projects. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A U.S. Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the U.S. Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report.

Initial results of the new high intensity electron gun at the Argonne Wakefield Accelerator

International Nuclear Information System (INIS)

Conde, M. E.; Gai, W.; Konecny, R.; Power, J. G.; Schoessow, P.; Sun, X.

2000-01-01

The authors report on the status of the new short bunch, high intensity electron gun at the Argonne Wakefield Accelerator. The 1-1/2 cell L-band photocathode RF gun is expected to produce 10--100 nC bunches with 2--5 ps rms pulse length and normalized emittance less than 100 mm mrad. The beam energy at the exit of the gun cavity will be in the range 7.5--10 MeV. A standing-wave linac structure operating at the same frequency (1.3 GHz) will increase the beam energy to about 15 MeV. This beam will be used in wakefield acceleration experiments with dielectric loaded structures. These travelling-wave dielectric loaded structures, operating at 7.8 and 15.6 GHz, will be excited by the propagation of single bunches or by trains of up to 32 electron bunches

Human-health effects of radium: an epidemiolgic perspective of research at Argonne National Laboratory

International Nuclear Information System (INIS)

Stebbings, J.H.

1982-01-01

The topic of health effects of radium has recently been considerably broadened by the identification of multiple myeloma as a specific outcome of bone-seeking radionuclides, and by evidence that the incidence of breast cancer may be significantly increased by radium exposure. All soft-tissue tumors are now suspect, especially leukemias. Concepts of dose-response need to be broadened to include the concept of risk factors, or, if one prefers, of susceptible subgroups. Biological factors relating to radium uptake and retention require study, as do risk factors modifying risk of both the clasical tumors, osteosarcoma and nasal sinus/mastoid, and the more recently suspect soft-tissue tumors. The history, organization, and current research activities in epidemiology at Argonne National Laboratory are described, and findings of the last decade and a half reviewed. Plans for future research are briefly discussed

Human health effects of radium: an epidemiologic perspective of research at Argonne National Laboratory

International Nuclear Information System (INIS)

Stebbings, J.H.

1982-01-01

The topic of health effects of radium has recently been considerably broadened by the identification of multiple myeloma as a specific outcome of bone-seeking radionuclides, and by evidence that the incidence of breast cancer may be significantly increased by radium exposure. All soft-tissue tumors are now suspect, especially leukemias. Concepts of dose-response need to be broadened to include the concept of risk factors, or, if one prefers, of susceptible subgroups. Biological factors relating to radium uptake and retention require study, as do risk factors modifying risk of both the classical tumors, osteosarcoma and nasal sinus/mastoid, and the more recently suspect soft-tissue tumors. The history, organization, and current research activities in epidemiology at Argonne National Laboratory are described, and findings of the last decade and a half reviewed. Plans for future research are briefly discussed

Human-health effects of radium: an epidemiolgic perspective of research at Argonne National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Stebbings, J.H.

1982-01-01

The topic of health effects of radium has recently been considerably broadened by the identification of multiple myeloma as a specific outcome of bone-seeking radionuclides, and by evidence that the incidence of breast cancer may be significantly increased by radium exposure. All soft-tissue tumors are now suspect, especially leukemias. Concepts of dose-response need to be broadened to include the concept of risk factors, or, if one prefers, of susceptible subgroups. Biological factors relating to radium uptake and retention require study, as do risk factors modifying risk of both the clasical tumors, osteosarcoma and nasal sinus/mastoid, and the more recently suspect soft-tissue tumors. The history, organization, and current research activities in epidemiology at Argonne National Laboratory are described, and findings of the last decade and a half reviewed. Plans for future research are briefly discussed.

Argonne National Laboratory-East site environmental report for calendar year 1992

International Nuclear Information System (INIS)

Golchert, N.W.; Kolzow, R.G.

1993-05-01

This report discusses the results of the Environmental Protection Program at Argonne National Laboratory-East (ANL) for 1992. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed

Argonne National Laboratory-East site environmental report for calendar year 1992

Energy Technology Data Exchange (ETDEWEB)

Golchert, N.W.; Kolzow, R.G.

1993-05-01

This report discusses the results of the Environmental Protection Program at Argonne National Laboratory-East (ANL) for 1992. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed.

Argonne National Laboratory, east hazardous waste shipment data validation

International Nuclear Information System (INIS)

Casey, C.; Graden, C.; Coveleskie, A.

1995-09-01

At the request of EM-331, the Radioactive Waste Technical Support Program (TSP) is conducting an evaluation of data regarding past hazardous waste shipments from DOE sites to commercial TSDFs. The intent of the evaluation is to find out if, from 1984 to 1991, DOE sites could have shipped hazardous waste contaminated with DOE-added radioactivity to commercial TSDFs not licensed to receive radioactive material. A team visited Argonne National Laboratory, East (ANL-E) to find out if any data existed that would help to make such a determination at ANL-E. The team was unable to find any relevant data. The team interviewed personnel who worked in waste management at the time. All stated that ANL-E did not sample and analyze hazardous waste shipments for radioactivity. Waste generators at ANL-E relied on process knowledge to decide that their waste was not radioactive. Also, any item leaving a building where radioisotopes were used was surveyed using hand-held instrumentation. If radioactivity above the criteria in DOE Order 5400.5 was found, the item was considered radioactive. The only documentation still available is the paperwork filled out by the waste generator and initialed by a health physics technician to show no contamination was found. The team concludes that, since all waste shipped offsite was subjected at least once to health physics instrumentation scans, the waste shipped from ANL-E from 1984 to 1991 may be considered clean

The Sodium Process Facility at Argonne National Laboratory-West

International Nuclear Information System (INIS)

Michelbacher, J.A.; Henslee, S.P.; McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

1998-01-01

Argonne National Laboratory-West (ANL-W) has approximately 680,000 liters of raw sodium stored in facilities on site. As mandated by the State of Idaho and the US Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The sodium will be processed in three separate and distinct campaigns: the 290,000 liters of Fermi-1 primary sodium, the 50,000 liters of the Experimental Breeder Reactor-II (EBR-II) secondary sodium, and the 330,000 liters of the EBR-II primary sodium. The Fermi-1 and the EBR-II secondary sodium contain only low-level of radiation, while the EBR-II primary sodium has radiation levels up to 0.5 mSv (50 mrem) per hour at 1 meter. The EBR-II primary sodium will be processed last, allowing the operating experience to be gained with the less radioactive sodium prior to reacting the most radioactive sodium. The sodium carbonate will be disposed of in 270 liter barrels, four to a pallet. These barrels are square in cross-section, allowing for maximum utilization of the space on a pallet, minimizing the required landfill space required for disposal

The Sodium Process Facility at Argonne National Laboratory-West

Energy Technology Data Exchange (ETDEWEB)

Michelbacher, J.A.; Henslee, S.P. McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

1998-07-01

Argonne National Laboratory-West (ANL-W) has approximately 680,000 liters of raw sodium stored in facilities on site. As mandated by the State of Idaho and the US Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The sodium will be processed in three separate and distinct campaigns: the 290,000 liters of Fermi-1 primary sodium, the 50,000 liters of the Experimental Breeder Reactor-II (EBR-II) secondary sodium, and the 330,000 liters of the EBR-II primary sodium. The Fermi-1 and the EBR-II secondary sodium contain only low-level of radiation, while the EBR-II primary sodium has radiation levels up to 0.5 mSv (50 mrem) per hour at 1 meter. The EBR-II primary sodium will be processed last, allowing the operating experience to be gained with the less radioactive sodium prior to reacting the most radioactive sodium. The sodium carbonate will be disposed of in 270 liter barrels, four to a pallet. These barrels are square in cross-section, allowing for maximum utilization of the space on a pallet, minimizing the required landfill space required for disposal.

The beam bunching and transport system of the Argonne positive ion injector

International Nuclear Information System (INIS)

Den Hartog, P.K.; Bogaty, J.M.; Bollinger, L.M.; Clifft, B.E.; Pardo, R.C.; Shepard, K.W.

1989-01-01

A new positive ion injector (PII) is currently under construction at Argonne that will replace the existing 9-MV tandem electrostatic accelerator as an injector into ATLAS. It consists of an electron-cyclotron resonance-ion source on a 350-kV platform injecting into a superconducting linac optimized for very slow (β ≤ .007 c) ions. This combination can potentially produce even higher quality heavy-ion beams than are currently available from the tandem since the emittance growth within the linac is largely determined by the quality of the bunching and beam transport. The system we have implemented uses a two-stage bunching system, composed of a 4-harmonic gridded buncher located on the ECR high-voltage platform and a room temperature spiral-loaded buncher of novel design. A sinusoidal beam chopper is used for removal of tails. The beam transport is designed to provide mass resolution of M/ΔM > 250 and a doubly-isochronous beamline is used to minimize time spread due to path length differences. 4 refs., 2 figs

The beam bunching and transport system of the Argonne positive ion injector

Energy Technology Data Exchange (ETDEWEB)

Den Hartog, P.K.; Bogaty, J.M.; Bollinger, L.M.; Clifft, B.E.; Pardo, R.C.; Shepard, K.W.

1989-01-01

A new positive ion injector (PII) is currently under construction at Argonne that will replace the existing 9-MV tandem electrostatic accelerator as an injector into ATLAS. It consists of an electron-cyclotron resonance-ion source on a 350-kV platform injecting into a superconducting linac optimized for very slow (..beta.. less than or equal to .007 c) ions. This combination can potentially produce even higher quality heavy-ion beams than are currently available from the tandem since the emittance growth within the linac is largely determined by the quality of the bunching and beam transport. The system we have implemented uses a two-stage bunching system, composed of a 4-harmonic gridded buncher located on the ECR high-voltage platform and a room temperature spiral-loaded buncher of novel design. A sinusoidal beam chopper is used for removal of tails. The beam transport is designed to provide mass resolution of M/..delta..M > 250 and a doubly-isochronous beamline is used to minimize time spread due to path length differences. 4 refs., 2 figs.

Centrifugal contractors for laboratory-scale solvent extraction tests

International Nuclear Information System (INIS)

Leonard, R.A.; Chamberlain, D.B.; Conner, C.

1995-01-01

A 2-cm contactor (minicontactor) was developed and used at Argonne National Laboratory for laboratory-scale testing of solvent extraction flowsheets. This new contactor requires only 1 L of simulated waste feed, which is significantly less than the 10 L required for the 4-cm unit that had previously been used. In addition, the volume requirements for the other aqueous and organic feeds are reduced correspondingly. This paper (1) discusses the design of the minicontactor, (2) describes results from having applied the minicontactor to testing various solvent extraction flowsheets, and (3) compares the minicontactor with the 4-cm contactor as a device for testing solvent extraction flowsheets on a laboratory scale

Percolation testing at the F- and H-Area Seepage Basins

International Nuclear Information System (INIS)

McHood, M.D.

1993-01-01

The design of the F- and H-Area Seepage Basin contaminated groundwater remediation system requires information from multiple well pump tests (Reference 1). Soil percolation rates are needed in order to support the multiple well pump test planning. The objective of this task was to determine characteristic percolation rates for soils in four select areas where infiltration galleries are proposed. These infiltration galleries will be temporary installations built on the ground surface and used to disposes of water from the multiple well pump tests. A procedure defining the specific work process for collecting percolation rate data is contained in Appendix 3. Results from these percolation tests will be used in the design of infiltration galleries for the disposal of well water extracted during the multiple well pump tests

Preliminary investigation Area 12 fleet operations steam cleaning discharge area Nevada Test Site

International Nuclear Information System (INIS)

1996-07-01

This report documents the characterization activities and findings of a former steam cleaning discharge area at the Nevada Test Site. The former steam cleaning site is located in Area 12 east of Fleet Operations Building 12-16. The characterization project was completed as a required condition of the ''Temporary Water Pollution Control Permit for the Discharge From Fleet Operations Steam Cleaning Facility'' issued by the Nevada Division of Environmental Protection. The project objective was to collect shallow soil samples in eight locations in the former surface discharge area. Based upon field observations, twelve locations were sampled on September 6, 1995 to better define the area of potential impact. Samples were collected from the surface to a depth of approximately 0.3 meters (one foot) below land surface. Discoloration of the surface soil was observed in the area of the discharge pipe and in localized areas in the natural drainage channel. The discoloration appeared to be consistent with the topographically low areas of the site. Hydrocarbon odors were noted in the areas of discoloration only. Samples collected were analyzed for bulk asbestos, Toxicity Characteristic Leaching Procedure (TCLP) metals, total petroleum hydrocarbons (TPHs), volatile organic compounds (VOCs), semi-volatile organic compounds (Semi-VOCs), and gamma scan

East Area Irradiation Test Facility: Preliminary FLUKA calculations

CERN Document Server

Lebbos, E; Calviani, M; Gatignon, L; Glaser, M; Moll, M; CERN. Geneva. ATS Department

2011-01-01

In the framework of the Radiation to Electronics (R2E) mitigation project, the testing of electronic equipment in a radiation field similar to the one occurring in the LHC tunnel and shielded areas to study its sensitivity to single even upsets (SEU) is one of the main topics. Adequate irradiation test facilities are therefore required, and one installation is under consideration in the framework of the PS East area renovation activity. FLUKA Monte Carlo calculations were performed in order to estimate the radiation field which could be obtained in a mixed field facility using the slowly extracted 24 GeV/c proton beam from the PS. The prompt ambient dose equivalent as well as the equivalent residual dose rate after operation was also studied and results of simulations are presented in this report.

100 Area soil washing bench-scale test procedures

International Nuclear Information System (INIS)

Freeman, H.D.; Gerber, M.A.; Mattigod, S.V.; Serne, R.J.

1993-03-01

This document describes methodologies and procedures for conducting soil washing treatability tests in accordance with the 100 Area Soil Washing Treatability Test Plan (DOE-RL 1992, Draft A). The objective of this treatability study is to evaluate the use of physical separation systems and chemical extraction methods as a means of separating chemically and radioactively contaminated soil fractions from uncontaminated soil fractions. These data will be primarily used for determining feasibility of the individual unit operations and defining the requirements for a system, or systems, for pilot-scale testing

Quality Assurance Program: Argonne peer review activities for the salt host-rock portion of the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

Edgar, D.E.

1986-01-01

This Quality Assurance (QA) Program sets forth the methods, controls, and procedures used to ensure that the results of Argonne National Laboratory's peer review activities are consistently of the highest quality and responsive to Salt Repository Project Office's needs and directives. Implementation of the QA procedures described herein establishes an operational framework so that task activities are traceable and the activities and decisions that influence the overall quality of the peer review process and results are fully documented. 56 refs., 5 figs., 6 tabs

Interim measure conceptual design for remediation at the former CCC/USDA grain storage facility at Centralia, Kansas : pilot test and remedy implementation.

Energy Technology Data Exchange (ETDEWEB)

LaFreniere, L. M.; Environmental Science Division

2007-11-09

This document presents an Interim Measure Work Plan/Design for the short-term, field-scale pilot testing and subsequent implementation of a non-emergency Interim Measure (IM) at the site of the former grain storage facility operated by the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) in Centralia, Kansas. The IM is recommended to mitigate both (1) localized carbon tetrachloride contamination in the vadose zone soils beneath the former facility and (2) present (and potentially future) carbon tetrachloride contamination identified in the shallow groundwater beneath and in the immediate vicinity of the former CCC/USDA facility. Investigations conducted on behalf of the CCC/USDA by Argonne National Laboratory have demonstrated that groundwater at the Centralia site is contaminated with carbon tetrachloride at levels that exceed the Kansas Tier 2 Risk-Based Screening Level (RBSL) and the U.S. Environmental Protection Agency's maximum contaminant level of 5.0 {micro}g/L for this compound. Groundwater sampling and analyses conducted by Argonne under a monitoring program approved by the Kansas Department of Health and Environment (KDHE) indicated that the carbon tetrachloride levels at several locations in the groundwater plume have increased since twice yearly monitoring of the site began in September 2005. The identified groundwater contamination currently poses no unacceptable health risks, in view of the absence of potential human receptors in the vicinity of the former CCC/USDA facility. Carbon tetrachloride contamination has also been identified at Centralia in subsurface soils at concentrations on the order of the Kansas Tier 2 RBSL of 200 {micro}g/kg in soil for the soil-to-groundwater protection pathway. Soils contaminated at this level might pose some risk as a potential source of carbon tetrachloride contamination to groundwater. To mitigate the existing contaminant levels and decrease the potential future concentrations of

Tomographic imaging of severely disrupted fuel assemblies tested in TREAT

International Nuclear Information System (INIS)

Morman, J.A.; Froehle, P.H.; Holland, J.W.; Bennett, J.D.

1990-01-01

A series of CT codes is under development in the Reactor Analysis and Safety Division of Argonne National Laboratory for use as a post-test examination tool to analyze segments of the final fuel-bundle configuration of TREAT tests. This paper presents the results of CT analysis for fuel assemblies using neutron radiography. Fuel relocation following overpower transients in the TREAT reactor is examined for sections of the assemblies, and results are compared to metallographic sections. Further improvements are expected to increase the use and reliability of CT analysis as a standard post-test examination tool

Preliminary investigation of the 317 Area, ANL-E

International Nuclear Information System (INIS)

Wescott, J.; Moos, L.; Remeikis, A.

1995-01-01

The 317 Area at Argonne National Laboratory-East (ANL-E) is scheduled to undergo a Resource Conservation and Recovery Act (RCRA) Facility Investigation, Act or RFI. Prior to the formal RFI, a voluntary, preliminary characterization of the 317 Area was conducted by ANL-E. The characterization results were used to formulate the RFI work plan and provided a better focus for the formal investigation. This site presents a difficult engineering challenge. The nature of the waste disposed at this site in the past includes both liquid chemicals and radioactive waste. The 317 Area is classified as a radiologically controlled area because of operations currently performed there. Present Department of Energy policy stipulates that waste material from such an area must be considered radioactive. The possible presence of hazardous constituents in the soil and groundwater would require the investigation-derived waste generated at the site be disposed as radioactive mixed waste. Besides the nature of the waste possibly contaminating this site, the geology of the site poses an equally enigmatic situation. The ANL-E site is located in a region of recessional glacial moraine deposits

Radioactive contamination of former Semipalatinsk test site area

International Nuclear Information System (INIS)

Artem'ev, O.I.; Akhmetov, M.A.; Ptitskaya, L.D.

2001-01-01

The nuclear weapon infrastructure elimination activities and related surveys of radioactive contamination are virtually accomplished at the Semipalatinsk test site (STS). The radioecological surveys accompanied closure of tunnels which were used for underground nuclear testing at Degelen technical field and elimination of intercontinental ballistic missile silo launchers at Balapan technical field. At the same time a ground-based route survey was carried out at the Experimental Field where aboveground tests were conducted and a ground-based area survey was performed in the south of the test site where there are permanent and temporary inhabited settlements. People dwelling these settlements are mainly farmers. The paper presents basic results of radiological work conducted in the course of elimination activities. (author)

Characterization and durability testing of a glass-bonded ceramic waste form

International Nuclear Information System (INIS)

Johnson, S. G.

1998-01-01

Argonne National Laboratory is developing a glass bonded ceramic waste form for encapsulating the fission products and transuranics from the conditioning of metallic reactor fuel. This waste form is currently being scaled to the multi-kilogram size for encapsulation of actual high level waste. This paper will present characterization and durability testing of the ceramic waste form. An emphasis on results from application of glass durability tests such as the Product Consistency Test and characterization methods such as X-ray diffraction and scanning electron microscopy. The information presented is based on a suite of tests utilized for assessing product quality during scale-up and parametric testing

Evaluation of NDE Round-Robin Exercises Using the NRC Steam Generator Mockup at Argonne National Laboratory

International Nuclear Information System (INIS)

Muscara, Joseph; Kupperman, David S.; Bakhtiari, Sasab; Park, Jang-Yul; Shack, William J.

2002-01-01

This paper discusses round-robin exercises using the NRC steam generator (SG) mock-up at Argonne National Laboratory to assess inspection reliability. The purpose of the round robins was to assess the current reliability of SG tubing inservice inspection, determine the probability of detection (POD) as function of flaw size or severity, and assess the capability for sizing of flaws. For the round robin and subsequent evaluation completed in 2001, eleven teams participated. Bobbin and rotating coil mock-up data collected by qualified industry personnel were evaluated. The mock-up contains hundreds of cracks and simulations of artifacts such as corrosion deposits and tube support plates that make detection and characterization of cracks more difficult in operating steam generators than in most laboratory situations. An expert Task Group from industry, Argonne National Laboratory, and the NRC have reviewed the signals from the laboratory-grown cracks used in the mock-up to ensure that they provide reasonable simulations of those obtained in the field. The mock-up contains 400 tube openings. Each tube contains nine 22.2-mm (7/8-in.) diameter, 30.5-cm (1-ft) long, Alloy 600 test sections. The flaws are located in the tube sheet near the roll transition zone (RTZ), in the tube support plate (TSP), and in the free-span. The flaws are primarily intergranular stress corrosion cracks (axial and circumferential, ID and OD) though intergranular attack (IGA) wear and fatigue cracks are also present, as well as cracks in dents. In addition to the simulated tube sheet and TSP the mock-up has simulated sludge and magnetite deposits. A multiparameter eddy current algorithm, validated for mock-up flaws, provided a detailed isometric plot for every flaw and was used to establish the reference state of defects in the mock-up. The detection results for the 11 teams were used to develop POD curves as a function of maximum depth, voltage and the parameter m p, for the various types of

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

International Nuclear Information System (INIS)

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

1989-12-01

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

Physics with fast molecular-ion beams. Proceedings of workshop held at Argonne National Laboratory, August 20-21, 1979

International Nuclear Information System (INIS)

Gemmell, D.S.

1979-01-01

The Workshop on Physics with Fast Molecular-Ion Beams was held in the Physics Division, Argonne National Laboratory on August 20 and 21, 1979. The meeting brought together representatives from several groups studying the interactions of fast (MeV) molecular-ion beams with matter. By keeping the Workshop program sharply focussed on current work related to the interactions of fast molecular ions, it was made possible for the participants to engage in vigorous and detailed discussions concerning such specialized topics as molecular-ion dissociation and transmission, wake effects, ionic charge states, cluster stopping powers, beam-foil spectroscopy, electron-emissions studies with molecular-ion beams, and molecular-ion structure determinations

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

Energy Technology Data Exchange (ETDEWEB)

Boing, L.E.; Henley, D.R. (Argonne National Lab., IL (USA)); Manion, W.J.; Gordon, J.W. (Nuclear Energy Services, Inc., Danbury, CT (USA))

1989-12-01

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

Argonne National Laboratory-East site environmental report for calendar year 1999

International Nuclear Information System (INIS)

Golchert, N. W.; Kolzow, R. G.

2000-01-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1999. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the US Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed, along with the progress of environmental corrective actions and restoration projects

Argonne National Laboratory-East site environmental report for calendar year 1998

International Nuclear Information System (INIS)

Golchert, N.W.; Kolzow, R.G.

1999-01-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1998. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the US Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed, along with the progress of environmental corrective actions and restoration projects

Argonne National Laboratory-East site environmental report for calendar year 1996

International Nuclear Information System (INIS)

Golchert, N.W.; Kolzow, R.G.

1997-09-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1996. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects

Argonne National Laboratory-East site environmental report for calendar year 1993

International Nuclear Information System (INIS)

Golchert, N.W.; Kolzow, R.G.

1994-05-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1993. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

Argonne National Laboratory-East site environmental report for calendar year 1994

International Nuclear Information System (INIS)

Golchert, N.W.; Kolzow, R.G.

1995-05-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1994. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK COMPUTER CODE, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects

Argonne National Laboratory-East site environmental report for calendar year 1994

Energy Technology Data Exchange (ETDEWEB)

Golchert, N.W.; Kolzow, R.G.

1995-05-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1994. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK COMPUTER CODE, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects.

Argonne National Laboratory--East site environmental report for calendar year 1990

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Moos, L.P.

1991-07-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1990. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, bottom sediment, and milk samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

Argonne National Laboratory-East site environmental report for calendar year 1991

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Moos, L.P.

1992-05-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1991. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. Chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

Argonne National Laboratory-East site environmental report for calendar year 1996

Energy Technology Data Exchange (ETDEWEB)

Golchert, N.W.; Kolzow, R.G.

1997-09-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1996. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects.

Class 1 overview of cultural resources for the Western Area Power Administration Salt Lake City Area Integrated Projects electric power marketing environmental impact statement

Energy Technology Data Exchange (ETDEWEB)

Moeller, K.L.; Malinowski, L.M.; Hoffecker, J.F.; Walitschek, D.A.; Shogren, L.; Mathews, J.E.; Verhaaren, B.T.

1993-11-01

Argonne National Laboratory conducted an inventory of known archaeological and historic sites in areas that could be affected by the hydropower operation alternatives under analysis in the power marketing environmental impact statement for the Western Area Power Administration`s Salt Lake City Area Integrated Projects. The study areas included portions of the Green River (Flaming Gorge Dam to Cub Creek) in Utah and Colorado and the Gunnison River (Blue Mesa Reservoir to Crystal Dam) in Colorado. All previous archaeological surveys and previously recorded prehistoric and historic sites, structures, and features were inventoried and plotted on maps (only survey area maps are included in this report). The surveys were classified by their level of intensity, and the sites were classified according to their age, type, and contents. These data (presented here in tabular form) permit a general assessment of the character and distribution of archaeological remains in the study areas, as well as an indication of the sampling basis for such an assessment. To provide an adequate context for the descriptions of the archaeological and historic sites, this report also presents overviews of the environmental setting and the regional prehistory, history, and ethnography for each study area.

Data qualification summary for 1985 L-Area AC Flow Tests

International Nuclear Information System (INIS)

Edwards, T.B.; Eghbali, D.A.; Liebmann, M.L.; Shine, E.P.

1992-03-01

The 1985 L-Area AC Flow Tests were conducted to provide an extended data base for upgrading the reactor system models employed in predicting normal process water flows. This report summarizes the results of the recently completed, formal, technical review of the data from the 1985 L-Area AC Flow Tests as detailed in document SCS-CMAS-910045. The purpose of that review was to provide corroborating technical information as to the quality (fitness for use) of these experimental data. Reference [1] required three volumes to fully document the results of that Data Qualification process. This report has been prepared to provide the important conclusions from that process in a manageable and understandable format. Consult reference [1] if any additional information or detail is needed. This report provides highlights from that study: an overview of the tests and data, a description of the instrumentation used, an explanation of the data qualification methods employed to review the data, and the important conclusions reached from the study. Reference 1: Edwards, T.B., D.A. Eghbali, M.L. Liebmann, and E.P. Shine, open-quotes Data Qualification for 1985 L-Area AC Flow Tests,close quotes SCS-CMAS-910045, December 31, 1991

Mechanical properties test data for structural materials. Quarterly progress report for period ending October 31, 1976

Energy Technology Data Exchange (ETDEWEB)

Hill, M R [comp.

1976-12-01

Test data on heat resisting reactor materials are presented. These data were obtained in research at EG and G Idaho, Argonne National Laboratory, Oak Ridge National Laboratory, Naval Research Laboratory, Hanford Engineering Development Laboratory, Westinghouse Advanced Reactors Division, General Electric Company, University of Cincinnati, and University of California at Los Angeles. (JRD)

Radioactive waste isolation in salt: Peer review of the Golder Associates draft test plan for in situ testing in an exploratory shaft in salt

International Nuclear Information System (INIS)

Hambley, D.F.; Mraz, D.Z.; Unterberter, R.R.

1987-01-01

This report documents the peer review conducted by Argonne National Laboratory of a document entitled ''Draft Test Plan for In Situ Testing in an Exploratory Shaft in Salt,'' prepared for Battelle Memorial Institute's Office of Nuclear Waste Isolation by Golder Associates, Inc. In general, the peer review panelists found the test plan to be technically sound, although some deficiencies were identified. Recommendations for improving the test plan are presented in this review report. A microfiche copy of the following unpublished report is attached to the inside back cover of this report: ''Draft Test Plan for In Situ Testing in an Exploratory Shaft in Salt,'' prepared by Golder Associates, Inc., for Office of Nuclear Waste Isolation, Battelle Memorial Institute, Columbus, Ohio (March 1985)

Do you want to build such a machine? : Designing a high energy proton accelerator for Argonne National Laboratory

International Nuclear Information System (INIS)

Paris, E.

2004-01-01

Argonne National Laboratory's efforts toward researching, proposing and then building a high-energy proton accelerator have been discussed in a handful of studies. In the main, these have concentrated on the intense maneuvering amongst politicians, universities, government agencies, outside corporations, and laboratory officials to obtain (or block) approval and/or funds or to establish who would have control over budgets and research programs. These ''top-down'' studies are very important but they can also serve to divorce such proceedings from the individuals actually involved in the ground-level research which physically served to create theories, designs, machines, and experiments. This can lead to a skewed picture, on the one hand, of a lack of effect that so-called scientific and technological factors exert and, on the other hand, of the apparent separation of the so-called social or political from the concrete practice of doing physics. An exception to this approach can be found in the proceedings of a conference on ''History of the ZGS'' held at Argonne at the time of the Zero Gradient Synchrotron's decommissioning in 1979. These accounts insert the individuals quite literally as they are, for the most part, personal reminiscences of those who took part in these efforts on the ground level. As such, they are invaluable raw material for historical inquiry but generally lack the rigor and perspective expected in a finished historical work. The session on ''Constructing Cold War Physics'' at the 2002 annual History of Science Society Meeting served to highlight new approaches circulating towards history of science and technology in the post-WWII period, especially in the 1950s. There is new attention towards the effects of training large numbers of scientists and engineers as well as the caution not to equate ''national security'' with military preparedness, but rather more broadly--at certain points--with the explicit ''struggle for the hearts and minds of

In situ ion irradiation/implantation studies in the HVEM-Tandem Facility at Argonne National Laboratory

International Nuclear Information System (INIS)

Allen, C.W.; Funk, L.L.; Ryan, E.A.; Taylor, A.

1988-09-01

The HVEM-Tandem User Facility at Argonne National Laboratory interfaces two ion accelerators, a 2 MV tandem accelerator and a 650 kV ion implanter, to a 1.2 MV high voltage electron microscope. This combination allows experiments involving simultaneous ion irradiation/ion implantation, electron irradiation and electron microscopy/electron diffraction to be performed. In addition the availability of a variety of microscope sample holders permits these as well as other types of in situ experiments to be performed at temperatures ranging from 10-1300 K, with the sample in a stressed state or with simultaneous determination of electrical resistivity of the specimen. This paper summarizes the details of the Facility which are relevant to simultaneous ion beam material modification and electron microscopy, presents several current applications and briefly describes the straightforward mechanism for potential users to access this US Department of Energy supported facility. 7 refs., 1 fig., 1 tab

Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology

Energy Technology Data Exchange (ETDEWEB)

NONE

1983-08-01

The international effort to develop new fuel materials and designs which will make it feasible to fuel research and test reactors throughout the world with low-enrichment uranium, instead of high-enrichment uranium, has made significant progress during the past year. This progress has taken place at research centers located in many different countries, and is of crucial interest to reactor operators and licensors whose geographical distribution is even more varied. It is appropriate, therefore, that international meetings be held periodically to foster direct communication among the specialists in this area. To achieve this purpose, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the third of a series which begun in 1978. The papers presented at this meeting were divided into sessions according to relevant subject: status of RERTR program and safety issues; development of new fuel types; testing of new fuel elements; specific reactor applications. These proceedings were edited by various members of the RERTR Program.

Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology

International Nuclear Information System (INIS)

1983-08-01

The international effort to develop new fuel materials and designs which will make it feasible to fuel research and test reactors throughout the world with low-enrichment uranium, instead of high-enrichment uranium, has made significant progress during the past year. This progress has taken place at research centers located in many different countries, and is of crucial interest to reactor operators and licensors whose geographical distribution is even more varied. It is appropriate, therefore, that international meetings be held periodically to foster direct communication among the specialists in this area. To achieve this purpose, the Reduced Enrichment Research and Test Reactor (RERTR) Program, at the Argonne National Laboratory, sponsored this meeting as the third of a series which begun in 1978. The papers presented at this meeting were divided into sessions according to relevant subject: status of RERTR program and safety issues; development of new fuel types; testing of new fuel elements; specific reactor applications. These proceedings were edited by various members of the RERTR Program

Contamination source review for Building E2370, Edgewood Area, Aberdeen Proving Ground, Maryland

Energy Technology Data Exchange (ETDEWEB)

O`Reilly, D.P.; Glennon, M.A.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

1995-09-01

The US Army Aberdeen Proving Ground (APG) commissioned Argonne National Laboratory (ANL) to conduct a contamination source review to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of APG buildings. The information obtained from this review may be used to assist the US Army in planning for the future use or disposition of the buildings. The contamination source review consisted of the following tasks: historical records search, physical inspection, photographic documentation, and geophysical investigation. This report provides the results of the contamination source review for Building E2370. Many of the APG facilities constructed between 1917 and the 1960s are no longer used because of obsolescence and their poor state of repair. Because many of these buildings were used for research, development, testing, and/or pilot-scale production of chemical warfare agents and other military substances, the potential exists for portions of the buildings to be contaminated with these substances, their degradation products, and other laboratory or industrial chemicals. These buildings and associated structures or appurtenances may contribute to environmental concerns at APG.

Corrective action investigation plan for Central Nevada Test Area, CAU No. 417

International Nuclear Information System (INIS)

1997-04-01

This Corrective Action Investigation Plan (CAIP) is part of a US Department of Energy (DOE)-funded environmental investigation of the Central Nevada Test Area (CNTA). This CAIP addresses the surface investigation and characterization of 15 identified Corrective Action Sites (CASs). In addition, several other areas of the CNTA project area have surface expressions that may warrant investigation. These suspect areas will be characterized, if necessary, in subsequent CAIPs or addendums to this CAIP prepared to address these sites. This CAIP addresses only the 15 identified CASs as shown in Table 2-1 that are associated with the drilling and construction of a number of testing wells designed as part of an underground nuclear testing program. The purpose of the wells at the time of construction was to provide subsurface access for the emplacement, testing, and post detonation evaluations of underground nuclear devices. If contamination is found at any of the 15-surface CASs, the extent of contamination will be determined in order to develop an appropriate corrective action

Retaining of botanical diversity of steppe ecosystems at the Semipalatinsk test site area

International Nuclear Information System (INIS)

Sultanova, B.M.

2005-01-01

The nuclear tests conducted on the STS area have an effect on steppe biome. Regime of military secrecy allowed retaining extensive diversity of steppe vegetation at the area of the former Semipalatinsk test site, although the vegetation was liquidated in the most part of Kazakhstan. Unique biologic diversity of the steppe vegetation requires status of particularly secured vegetation of the STS area. (author)

Characterization and testing of a 238Pu loaded ceramic waste form

International Nuclear Information System (INIS)

Johnson, S. G.

1998-01-01

This paper will describe the preparation and progress of the effort at Argonne National Laboratory-West to produce ceramic waste forms loaded with 238 Pu. The purpose of this study is to determine the extent of damage, if any, that alpha decay events will play over time to the ceramic waste form under development at Argonne. The ceramic waste form is glass-bonded sodalite. The sodalite is utilized to encapsulate the fission products and transuranics which are present in a chloride salt matrix which results from a spent fuel conditioning process. 238 Pu possesses approximately 250 times the specific activity of 239 Pu and thus allows for a much shorter time frame to address the issue. In preparation for production of 238 Pu loaded waste forms 239 Pu loaded samples were produced. Data is presented for samples produced with typical reactor grade plutonium. X-ray diffraction, scanning electron micrographs and durability test results will be presented. The ramifications for the production of the 238 Pu loaded samples will be discussed

Tracer Testing for Estimating Heat Transfer Area in Fractured Reservoirs

Energy Technology Data Exchange (ETDEWEB)

Pruess, Karsten; van Heel, Ton; Shan, Chao

2004-05-12

A key parameter governing the performance and life-time of a Hot Fractured Rock (HFR) reservoir is the effective heat transfer area between the fracture network and the matrix rock. We report on numerical modeling studies into the feasibility of using tracer tests for estimating heat transfer area. More specifically, we discuss simulation results of a new HFR characterization method which uses surface-sorbing tracers for which the adsorbed tracer mass is proportional to the fracture surface area per unit volume. Sorption in the rock matrix is treated with the conventional formulation in which tracer adsorption is volume-based. A slug of solute tracer migrating along a fracture is subject to diffusion across the fracture walls into the adjacent rock matrix. Such diffusion removes some of the tracer from the fluid in the fractures, reducing and retarding the peak in the breakthrough curve (BTC) of the tracer. After the slug has passed the concentration gradient reverses, causing back-diffusion from the rock matrix into the fracture, and giving rise to a long tail in the BTC of the solute. These effects become stronger for larger fracture-matrix interface area, potentially providing a means for estimating this area. Previous field tests and modeling studies have demonstrated characteristic tailing in BTCs for volatile tracers in vapor-dominated reservoirs. Simulated BTCs for solute tracers in single-phase liquid systems show much weaker tails, as would be expected because diffusivities are much smaller in the aqueous than in the gas phase, by a factor of order 1000. A much stronger signal of fracture-matrix interaction can be obtained when sorbing tracers are used. We have performed simulation studies of surface-sorbing tracers by implementing a model in which the adsorbed tracer mass is assumed proportional to the fracture-matrix surface area per unit volume. The results show that sorbing tracers generate stronger tails in BTCs, corresponding to an effective

Decontamination and decommissioning of the Argonne National Laboratory Building 350 Plutonium Fabrication Facility. Final report

International Nuclear Information System (INIS)

Kline, W.H.; Moe, H.J.; Lahey, T.J.

1985-02-01

In 1973, Argonne National Laboratory began consolidating and upgrading its plutonium-handling operations with the result that the research fuel-fabrication facility located in Building 350 was shut down and declared surplus. Sixteen of the twenty-three gloveboxes which comprised the system were disassembled and relocated for reuse or placed into controlled storage during 1974 but, due to funding constraints, full-scale decommissioning did not start until 1978. Since that time the fourteen remaining contaminated gloveboxes, including all internal and external equipment as well as the associated ventilation systems, have been assayed for radioactive content, dismantled, size reduced to fit acceptable packaging and sent to a US Department of Energy (DOE) transuranic retrievable-storage site or to a DOE low-level nuclear waste burial ground. The project which was completed in 1983, required 5 years to accomplish, 32 man years of effort, produced some 540 m 3 (19,000 ft 3 ) of radioactive waste of which 60% was TRU, and cost 2.4 million dollars

Decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East. Project final report

International Nuclear Information System (INIS)

Fellhauer, C.R.; Clark, F.R.

1997-10-01

The decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East (ANL-E) was completed in October 1997. Descriptions and evaluations of the activities performed and analyses of the results obtained during the JANUS D and D Project are provided in this Final Report. The following information is included: objective of the JANUS D and D Project; history of the JANUS Reactor facility; description of the ANL-E site and the JANUS Reactor facility; overview of the D and D activities performed; description of the project planning and engineering; description of the D and D operations; summary of the final status of the JANUS Reactor facility based upon the final survey results; description of the health and safety aspects of the project, including personnel exposure and OSHA reporting; summary of the waste minimization techniques utilized and total waste generated by the project; and summary of the final cost and schedule for the JANUS D and D Project

Design and Testing of Subsystems for Mo-99 Production

Energy Technology Data Exchange (ETDEWEB)

Gromov, R. [Argonne National Lab. (ANL), Argonne, IL (United States); Bailey, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Virgo, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Chemerisov, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Vandegrift, G. F. [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-01-01

Argonne National Laboratory, in cooperation with Los Alamos National Laboratory, is developing technology with NorthStar Medical Technologies to produce ⁹⁹Mo from the γ,n reaction on a ¹⁰⁰Mo target in an electron accelerator. During production runs and thermal testing of the helium-cooled target, it became obvious that a production-scale beam-line configuration would need a collimator to protect the target from accidental beam misplacement or a beam-profile change. A prototype high-power collimator and beam stop were designed and fabricated. Testing indicated that they will be able to operate at full power in the production-scale accelerator.

STREAMLINED APPROACH FOR ENVIRONMENTAL RESTORATION PLAN FOR CORRECTIVE ACTION UNIT 116: AREA 25 TEST CELL C FACILITY NEVADA TEST SITE, NEVADA

International Nuclear Information System (INIS)

2006-01-01

This Streamlined Approach for Environmental Restoration Plan identifies the activities required for the closure of Corrective Action Unit 116, Area 25 Test Cell C Facility. The Test Cell C Facility is located in Area 25 of the Nevada Test Site approximately 25 miles northwest of Mercury, Nevada

Beam test of a large area silicon drift detector

International Nuclear Information System (INIS)

Castoldi, A.; Chinnici, S.; Gatti, E.; Longoni, A.; Palma, F.; Sampietro, M.; Rehak, P.; Ballocchi, G.; Kemmer, J.; Holl, P.; Cox, P.T.; Giacomelli, P.; Vacchi, A.

1992-01-01

The results from the tests of the first large area (4 x 4 cm 2 ) planar silicon drift detector prototype in a pion beam are reported. The measured position resolution in the drift direction is (σ=40 ± 10)μm

Hanford 100-D Area Biostimulation Treatability Test Results

Energy Technology Data Exchange (ETDEWEB)

Truex, Michael J.; Vermeul, Vincent R.; Fritz, Brad G.; Mackley, Rob D.; Mendoza, Donaldo P.; Elmore, Rebecca P.; Mitroshkov, Alexandre V.; Sklarew, Deborah S.; Johnson, Christian D.; Oostrom, Martinus; Newcomer, Darrell R.; Brockman, Fred J.; Bilskis, Christina L.; Hubbard, Susan S.; Peterson, John E.; Williams, Kenneth H.; Gasperikova, E.; Ajo-Franklin, J.

2009-09-30

Pacific Northwest National Laboratory conducted a treatability test designed to demonstrate that in situ biostimulation can be applied to help meet cleanup goals in the Hanford Site 100-D Area. In situ biostimulation has been extensively researched and applied for aquifer remediation over the last 20 years for various contaminants. In situ biostimulation, in the context of this project, is the process of amending an aquifer with a substrate that induces growth and/or activity of indigenous bacteria for the purpose of inducing a desired reaction. For application at the 100-D Area, the purpose of biostimulation is to induce reduction of chromate, nitrate, and oxygen to remove these compounds from the groundwater. The in situ biostimulation technology is intended to provide supplemental treatment upgradient of the In Situ Redox Manipulation (ISRM) barrier previously installed in the Hanford 100-D Area and thereby increase the longevity of the ISRM barrier. Substrates for the treatability test were selected to provide information about two general approaches for establishing and maintaining an in situ permeable reactive barrier based on biological reactions, i.e., a biobarrier. These approaches included 1) use of a soluble (miscible) substrate that is relatively easy to distribute over a large areal extent, is inexpensive, and is expected to have moderate longevity; and 2) use of an immiscible substrate that can be distributed over a reasonable areal extent at a moderate cost and is expected to have increased longevity.

Global climate change and international security. Report on a conference held at Argonne National Laboratory, May 8--10, 1991

Energy Technology Data Exchange (ETDEWEB)

Rice, M.

1991-12-31

On May 8--10, 1991, the Midwest Consortium of International Security Studies (MCISS) and Argonne National Laboratory cosponsored a conference on Global Climate Change and International Security. The aim was to bring together natural and social scientists to examine the economic, sociopolitical, and security implications of the climate changes predicted by the general circulation models developed by natural scientists. Five themes emerged from the papers and discussions: (1) general circulation models and predicted climate change; (2) the effects of climate change on agriculture, especially in the Third World; (3) economic implications of policies to reduce greenhouse gas emissions; (4) the sociopolitical consequences of climate change; and (5) the effect of climate change on global security.

Waste reduction efforts through the evaluation and procurement of a digital camera system for the Alpha-Gamma Hot Cell Facility at Argonne National Laboratory-East

International Nuclear Information System (INIS)

Bray, T. S.; Cohen, A. B.; Tsai, H.; Kettman, W. C.; Trychta, K.

1999-01-01

The Alpha-Gamma Hot Cell Facility (AGHCF) at Argonne National Laboratory-East is a research facility where sample examinations involve traditional photography. The AGHCF documents samples with photographs (both Polaroid self-developing and negative film). Wastes generated include developing chemicals. The AGHCF evaluated, procured, and installed a digital camera system for the Leitz metallograph to significantly reduce labor, supplies, and wastes associated with traditional photography with a return on investment of less than two years

Laboratory directed research and development. FY 1991 program activities: Summary report

Energy Technology Data Exchange (ETDEWEB)

1991-11-15

The purposes of Argonne`s Laboratory Directed Research and Development (LDRD) Program are to encourage the development of novel concepts, enhance the Laboratory`s R&D capabilities, and further the development of its strategic initiatives. Among the aims of the projects supported by the Program are establishment of engineering ``proof-of-principle``; development of an instrumental prototype, method, or system; or discovery in fundamental science. Several of these project are closely associated with major strategic thrusts of the Laboratory as described in Argonne`s Five Year Institutional Plan, although the scientific implications of the achieved results extend well beyond Laboratory plans and objectives. The projects supported by the Program are distributed across the major programmatic areas at Argonne. Areas of emphasis are (1) advanced accelerator and detector technology, (2) x-ray techniques in biological and physical sciences, (3) advanced reactor technology, (4) materials science, computational science, biological sciences and environmental sciences. Individual reports summarizing the purpose, approach, and results of projects are presented.

Selection of areas for testing in the Eleana formation: Paleozoic geology of western Yucca Flat

Energy Technology Data Exchange (ETDEWEB)

Sweeney, J J

1984-07-01

The Paleozoic geology of NTS is reviewed to select an area for underground nuclear testing in shale. Constraints on possible areas, dictated by test program requirements and economics, are areas with topographic slope less than 5/sup 0/, depths to working point less than 3000 ft., and working points above the water table. The rock formation selected is Unit J (argillite) of the Mississippian age Eleana Formation. Within NTS, Western Yucca Flat is selected as the best area to meet the requirements. Details of the Paleozoic structure of western Yucca Flat are presented. The interpretation is based on published maps, cross-sections, and reports as well as borehole, refraction seismic, and gravity data. In terms of subsurface structure and areas where Eleana Formation Unit J occurs at depths between 500 ft to 3000 ft, four possible testing areas are identified. The areas are designated here as A, B, C and the Gravity High. Available data on the water table (static water level) is reviewed for western Yucca Flat area. Depth to the water table increases from 500 to 600 ft in Area A to 1500 ft or more in the Gravity High area. Review of the water table data rules out area A and B for testing in argillite above the water table. Area C is relatively unexplored and water conditions are unknown there. Thus, the Gravity High is selected as the most promising area for selecting testing sites. There is a dolomite thrust sheet of unknown thickness overlying the argillite in the Gravity High area. An exploration program is proposed to better characterize this structure. Finally, recommendations are made for procedures to follow for eventual site characterization of a testing site in argillite. 22 references, 12 figures, 1 table.

Do you want to build such a machine? : Designing a high energy proton accelerator for Argonne National Laboratory.

Energy Technology Data Exchange (ETDEWEB)

Paris, E.

2004-04-05

Argonne National Laboratory's efforts toward researching, proposing and then building a high-energy proton accelerator have been discussed in a handful of studies. In the main, these have concentrated on the intense maneuvering amongst politicians, universities, government agencies, outside corporations, and laboratory officials to obtain (or block) approval and/or funds or to establish who would have control over budgets and research programs. These ''top-down'' studies are very important but they can also serve to divorce such proceedings from the individuals actually involved in the ground-level research which physically served to create theories, designs, machines, and experiments. This can lead to a skewed picture, on the one hand, of a lack of effect that so-called scientific and technological factors exert and, on the other hand, of the apparent separation of the so-called social or political from the concrete practice of doing physics. An exception to this approach can be found in the proceedings of a conference on ''History of the ZGS'' held at Argonne at the time of the Zero Gradient Synchrotron's decommissioning in 1979. These accounts insert the individuals quite literally as they are, for the most part, personal reminiscences of those who took part in these efforts on the ground level. As such, they are invaluable raw material for historical inquiry but generally lack the rigor and perspective expected in a finished historical work. The session on ''Constructing Cold War Physics'' at the 2002 annual History of Science Society Meeting served to highlight new approaches circulating towards history of science and technology in the post-WWII period, especially in the 1950s. There is new attention towards the effects of training large numbers of scientists and engineers as well as the caution not to equate ''national security'' with military preparedness, but rather

An investigation on impacts of scheduling configurations on Mississippi biology subject area testing

Science.gov (United States)

Marchette, Frances Lenora

The purpose of this mixed modal study was to compare the results of Biology Subject Area mean scores of students on a 4 x 4 block schedule, A/B block schedule, and traditional year-long schedule for 1A to 5A size schools. This study also reviewed the data to determine if minority or gender issues might influence the test results. Interviews with administrators and teachers were conducted about the type of schedule configuration they use and the influence that the schedule has on student academic performance on the Biology Subject Area Test. Additionally, this research further explored whether schedule configurations allow sufficient time for students to construct knowledge. This study is important to schools, teachers, and administrators because it can assist them in considering the impacts that different types of class schedules have on student performance and if ethnic or gender issues are influencing testing results. This study used the causal-comparative method for the quantitative portion of the study and constant comparative method for the qualitative portion to explore the relationship of school schedules on student academic achievement on the Mississippi Biology Subject Area Test. The aggregate means of selected student scores indicate that the Mississippi Biology Subject Area Test as a measure of student performance reveals no significant difference on student achievement for the three school schedule configurations. The data were adjusted for initial differences of gender, minority, and school size on the three schedule configurations. The results suggest that schools may employ various schedule configurations and expect student performance on the Mississippi Biology Subject Area Test to be unaffected. However, many areas of concern were identified in the interviews that might impact on school learning environments. These concerns relate to effective classroom management, the active involvement of students in learning, the adequacy of teacher education

Lyme disease testing in children in an endemic area.

Science.gov (United States)

Al-Sharif, Bashar; Hall, Matthew C

2011-10-01

The purpose of this study was to determine clinician adherence to recommendations regarding diagnostic testing for Lyme disease (LD). The specific aims were to determine the rate of inappropriate test ordering for a diagnosis of erythema migrans and tack of confirmatory test ordering for positive LD screening tests. Using the data warehouse of Marshfield Clinic Research Foundation's Bioinformatics Research Center, cases were identified from 2002 through 2007. A retrospective chart abstraction was performed using Marshfield Clinic's electronic medical record. The study involved children (testing occurred after a clinical diagnosis of erythema migrans was made. Patients with any symptom in addition to erythema migrans were more likely to have testing (odds ratio (OR) = 3.52, 1.75-7.08). A positive LD screening test was not confirmed 24% of the time. Lack of ordering confirmatory testing was not associated with any clinical factors or site of the evaluation. This study found that some clinicians in an LD-endemic area do not follow guidelines for diagnosing children suspected to have Lyme disease.

Evolution of the Argonne Tandem Linear Accelerator System (ATLAS) control system

International Nuclear Information System (INIS)

Power, M.; Munson, F.

2012-01-01

Given that the Argonne Tandem Linear Accelerator System (ATLAS) recently celebrated its 25. anniversary, this paper will explore the past, present, and future of the ATLAS Control System, and how it has evolved along with the accelerator and control system technology. ATLAS as we know it today, originated with a Tandem Van de Graff in the sixties. With the addition of the Booster section in the late seventies, came the first computerized control. ATLAS itself was placed into service on June 25, 1985, and was the world's first superconducting linear accelerator for ions. Since its dedication as a National User Facility, more than a thousand experiments by more than 2,000 users worldwide, have taken advantage of the unique capabilities it provides. Today, ATLAS continues to be a user facility for physicists who study the particles that form the heart of atoms. Its most recent addition, CARIBU (Californium Rare Isotope Breeder Upgrade), creates special beams that feed into ATLAS. ATLAS is similar to a living organism, changing and responding to new technological challenges and research needs. As it continues to evolve, so does the control system: from the original days using a DEC PDP-11/34 computer and two CAMAC crates, to a DEC Alpha computer running Vsystem software and more than twenty CAMAC crates, to distributed computers and VME systems. Future upgrades are also in the planning stages that will continue to evolve the control system. (authors)

An activated barrier for protection of special nuclear materials in vital areas

International Nuclear Information System (INIS)

Timm, R.E.; Miranda, J.E.

1984-01-01

The Argonne National Laboratory and Sandia National Laboratory have recently installed an activated barrier, the Access Denial System (ADS) for the upgrade of safeguards of special nuclear materials. The technology of this system was developed in the late 70's by Sandia National Laboratory-Albuquerque. The installation was the first for the Department of Energy. Subsequently, two additional installations have been completed. The Access Denial System, combined with physical restraints, provide the system delay. The principal advantages of the activated barrier are: (1) it provides an order of magnitude improvement in delay over that of a fixed barrier, (2) it can be added to existing vital areas with a minimum of renovations, (3) existing operations are minimally impacted, and (4) health and safety risks are virtually nonexistent. Hardening of the vital areas using the ADS was accomplished in a costeffective manner

The Department of Energy Nevada Test Site Remote Area Monitoring System

International Nuclear Information System (INIS)

Sanders, L.D.; Hart, O.F.

1993-01-01

The Remote Area Monitoring System was developed by Los Alamos National Laboratory (LANL) for DOE test directors at the Nevada Test Site (NTS) to verify radiological conditions are safe after a nuclear test. In the unlikely event of a venting as a result of a nuclear test, this system provides radiological and meteorological data to Weather Service Nuclear Support Office (WSNSO) computers where mesoscale models are used to predict downwind exposure rates. The system uses a combination of hardwired radiation sensors and satellite based data acquisition units with their own radiation sensors to measure exposure rates in remote areas of the NTS. The satellite based data acquisition units are available as small, Portable Remote Area Monitors (RAMs) for rapid deployment, and larger, Semipermanent RAMs that can have meteorological towers. The satellite based stations measure exposure rates and transmit measurements to the GOES (Geostationary Operational Environmental Satellite) where they are relayed to Direct Readout Ground Stations (DRGS) at the NTS and Los Alamos. Computers process the data and display results in the NTS Operations Coordination Center. Los Alamos computers and NTS computers are linked together through a wide area network, providing remote redundant system capability. Recently, LANL, expanded the system to take radiological and meteorological measurements in communities in the western United States. The system was also expanded to acquire data from Remote Automatic Weather Stations (RAWS) that transmit through GOES. The addition of Portable and Semipermanent RAMs to the system has vastly expanded monitoring capabilities at NTS and can be used to take measurements anywhere in this hemisphere

Nevada Test Site 2008 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

2009-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2008 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities

Activated barrier for protection of special nuclear materials in vital areas

International Nuclear Information System (INIS)

Timm, R.E.; Miranda, J.E.; Reigle, D.L.; Valente, A.D.

1984-01-01

The Argonne National Laboratory and Sandia National Laboratory have recently installed an activated barrier, the Access Denial System (ADS) for the upgrade of safeguards of special nuclear materials. The technology of this system was developed in the late 70's by Sandia National Laboratory-Albuquerque. The installation was the first for the Department of Energy. Subsequently, two additional installations have been completed. The Access Denial System, combined with physical restraints, provide the system delay. The principal advantages of the activated barrier are: (1) it provides an order of magnitude improvement in delay over that of a fixed barrier, (2) it can be added to existing vital areas with a minimum of renovations, (3) existing operations are minimally impacted, and (4) health and safety risks are virtually nonexistent. Hardening of the vital areas using the ADS was accomplished in a cost-effective manner. 3 references, 1 figure, 1 table

Aerial radiation survey techniques for efficient characterization of large areas

International Nuclear Information System (INIS)

Sydelko, T.; Riedhauser, S.

2006-01-01

Full text: Accidental or intentional releases of radioactive isotopes over potentially very large surface areas can pose serious health risks to humans and ecological receptors. Timely and appropriate responses to these releases depend upon rapid and accurate characterization of impacted areas. These characterization efforts can be adversely impacted by heavy vegetation, rugged terrain, urban environments, and the presence of unknown levels of radioactivity. Aerial survey techniques have proven highly successful in measuring gamma emissions from radiological contaminates of concern quickly, efficiently, and safely. Examples of accidental releases include the unintentional distribution of uranium mining ores during transportation, the loss of uranium processing and waste materials, unintentional nuclear power plant emissions into the atmosphere, and the distribution of isotopes during major flooding events such as the one recently occurring in New Orleans. Intentional releases have occurred during the use of deleted uranium ammunition test firing and war time use by military organizations. The threat of radiological dispersion device (dirty bomb) use by terrorists is currently a major concern of many major cities worldwide. The U.S. Department of Energy, in cooperation with its Remote Sensing Laboratory and Argonne National Laboratory, has developed a sophisticated aerial measurement system for identifying the locations, types, and quantities of gamma emitting radionuclides over extremely large areas. Helicopter mounted Nal detectors are flown at low altitude and constant speed along parallel paths measuring the full spectrum of gamma activity. Analytical procedures are capable of distinguishing between radiological contamination and changes in natural background emissions. Mapped and tabular results of these accurate, timely and cost effective aerial gamma radiation surveys can be used to assist with emergency response actions, if necessary, and to focus more

Waste characterization for radioactive liquid waste evaporators at Argonne National Laboratory - West

International Nuclear Information System (INIS)

Christensen, B. D.

1999-01-01

Several facilities at Argonne National Laboratory - West (ANL-W) generate many thousand gallons of radioactive liquid waste per year. These waste streams are sent to the AFL-W Radioactive Liquid Waste Treatment Facility (RLWTF) where they are processed through hot air evaporators. These evaporators remove the liquid portion of the waste and leave a relatively small volume of solids in a shielded container. The ANL-W sampling, characterization and tracking programs ensure that these solids ultimately meet the disposal requirements of a low-level radioactive waste landfill. One set of evaporators will process an average 25,000 gallons of radioactive liquid waste, provide shielding, and reduce it to a volume of six cubic meters (container volume) for disposal. Waste characterization of the shielded evaporators poses some challenges. The process of evaporating the liquid and reducing the volume of waste increases the concentrations of RCIU regulated metals and radionuclides in the final waste form. Also, once the liquid waste has been processed through the evaporators it is not possible to obtain sample material for characterization. The process for tracking and assessing the final radioactive waste concentrations is described in this paper, The structural components of the evaporator are an approved and integral part of the final waste stream and they are included in the final waste characterization

Photoinjector optimization using a derivative-free, model-based trust-region algorithm for the Argonne Wakefield Accelerator

Science.gov (United States)

Neveu, N.; Larson, J.; Power, J. G.; Spentzouris, L.

2017-07-01

Model-based, derivative-free, trust-region algorithms are increasingly popular for optimizing computationally expensive numerical simulations. A strength of such methods is their efficient use of function evaluations. In this paper, we use one such algorithm to optimize the beam dynamics in two cases of interest at the Argonne Wakefield Accelerator (AWA) facility. First, we minimize the emittance of a 1 nC electron bunch produced by the AWA rf photocathode gun by adjusting three parameters: rf gun phase, solenoid strength, and laser radius. The algorithm converges to a set of parameters that yield an emittance of 1.08 μm. Second, we expand the number of optimization parameters to model the complete AWA rf photoinjector (the gun and six accelerating cavities) at 40 nC. The optimization algorithm is used in a Pareto study that compares the trade-off between emittance and bunch length for the AWA 70MeV photoinjector.

Interim report on flash floods, Area 5 - Nevada Test Site

International Nuclear Information System (INIS)

French, R.H.

1980-09-01

Examination of the presently available data indicates that consideration must be given to the possibility of flash floods when siting waste management facilities in Area 5 of the Nevada Test Site. 6 figures, 7 tables

Use of the ''MURA'' transformation to generate the fields and calculate the motion of protons in the designed Argonne Mini-ASPUN FFAG Spiral Sector Accelerator

International Nuclear Information System (INIS)

Crosbie, E.A.

1985-01-01

As a long range goal for the production of high intensity neutrons, Argonne National Laboratory has proposed the construction of a 1.5 GeV FFAG Spiral Sector Accelerator called ASPUN. The 500-MeV injector for this proposed accelerator is a smaller FFAG Spiral Sector Accelerator named Mini-ASPUN. Until such a time as the larger machine could be built, it was planned that Mini-ASPUN would replace the present RCS now being used for the IPNS program at Argonne. In order to obtain an accurate estimation of the orbits and betatron oscillations in such a machine, it is necessary that realistic field values be used in the equations of motion. Obtaining these fields from 3-dimensional relaxation calculations is both time consuming and costly. However, because of the required scaling of the machine, the field-generating potential of three variables can be separated into a known function of the radius and a function of two variables. The second order differential equation satisfied by this function can be solved by ordinary relaxation methods. The fields generated from a mesh of values for this function will be accurate except for the extreme inside and outside orbits, which will be affected by the necessary termination of the inside and outside ends of the magnet. 2 refs., 4 figs., 1 tab

100 Area soil washing treatability test plan

International Nuclear Information System (INIS)

1993-03-01

This test plan describes specifications, responsibilities, and general methodology for conducting a soil washing treatability study as applied to source unit contamination in the 100 Area. The objective ofthis treatability study is to evaluate the use of physical separation systems and chemical extraction methods as a means of separating chemically and radioactively contaminated soil fractions from uncontaminated soil fractions. The purpose of separating these fractions is to minimize the volume of soil requiring permanent disposal. It is anticipated that this treatability study will be performed in two phases of testing, a remedy screening phase and a remedy selection phase. The remedy screening phase consists of laboratory- and bench-scale studies performed by Battelle Pacific Northwest laboratories (PNL) under a work order issued by Westinghouse Hanford Company (Westinghouse Hanford). This phase will be used to provide qualitative evaluation of the potential effectiveness of the soil washing technology. The remedy selection phase, consists of pilot-scale testing performed under a separate service contract to be competitively bid under Westinghouse Hanford direction. The remedy selection phase will provide data to support evaluation of the soil washing technology in future feasibility studies for Interim Remedial Measures (IRMs) or final operable unit (OU) remedies. Performance data from these tests will indicate whether applicable or relevant and appropriate requirements (ARARs) or cleanup goals can be met at the site(s) by application of soil washing. The remedy selection tests wig also allow estimation of costs associated with implementation to the accuracy required for the Feasibility Study

Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests

International Nuclear Information System (INIS)

Liu, Y.Y.; Tsai, H.; Billone, M.C.; Holland, J.W.; Kramer, J.M.

1992-11-01

This report discusses three furnace heating tests which were conducted with irradiated, HT9-clad and U-19wt.%Pu-l0wt.%Zr-alloy fuel, Mk-V-type fuel elements in the Alpha-Gamma Hot Cell Facility at Argonne National Laboratory, Illinois. In general, very significant safety margins for fuel-element cladding breaching have been demonstrated in these tests, under conditions that would envelop a bounding unlikely loss-of-flow event in EBR-II. Highlights of the test results will be given, as well as discussions of the cladding breaching mechanisms, axial fuel motion, and fuel surface liquefaction found in high-temperature testing of irradiated metallic fuel elements

Advanced liquid metal reactor development at Argonne National Laboratory during the 1980s

International Nuclear Information System (INIS)

Wade, D.C.

1990-01-01

Argonne National Laboratory's (ANL'S) effort to pursue the exploitation of liquid metal cooled reactor (LMR) characteristics has given rise to the Integral Fast Reactor (IFR) concept, and has produced substantial technical advancement in concept implementation which includes demonstration of high burnup capability of metallic fuel, demonstration of injection casting fabrication, integral demonstration of passive safety response, and technical feasibility of pyroprocessing. The first half decade of the 90's will host demonstration of the IFR closed fuel cycle technology at the prototype scale. The EBR-II reactor will be fueled with ternary alloy fuel in HT-9 cladding and ducts, and pyroprocessing and injection casting refabrication of EBR-II fuel will be conducted using near-commercial sized equipment at the Fuel cycle Facility (FCF) which is co-located adjacent to EBR-II. Demonstration will start in 1992. The demonstration of passive safety response achievable with the IFR design concept, (already done in EBR-II in 1986) will be repeated in the mid 90's using the IFR prototype recycle fuel from the FCF. The demonstration of scrubbing of the reprocessing fission product waste stream, with recycle of the transuranics to the reactor for consumption, will also occur in the mid 90's. 30 refs

Development of a portable system to test area monitors for neutrons

International Nuclear Information System (INIS)

Souza, Luciane de Rezende

2011-02-01

The objective is to develop a portable system to test the reliability in terms of calibration of area monitors for neutrons. For the production of this system, thickness and location of the source within the system were simulated using the code of radiation transport MCNP5. The thicknesses were set for a 241 Am-Be source with an activity of 395 mCi, which will be in a polyethylene cylinder which will provide a ambient dose equivalent rate chosen through the points of calibration settings' used by the Laboratory of Neutrons (IRD / CNEN). The results obtained in this study show the feasibility of mounting the portable system as a tool to test the area monitors for neutrons, which will provide the user of neutron area monitors to check the instrument's response in the same field of operation, thus avoiding the use of an inadequate equipment. (author)

Development and pilot demonstration program of a waste minimization plan at Argonne National Laboratory

International Nuclear Information System (INIS)

Peters, R.W.; Wentz, C.A.; Thuot, J.R.

1991-01-01

In response to US Department of Energy directives, Argonne National Laboratory (ANL) has developed a waste minimization plan aimed at reducing the amount of wastes at this national research and development laboratory. Activities at ANL are primarily research- oriented and as such affect the amount and type of source reduction that can be achieved at this facility. The objective of ANL's waste minimization program is to cost-effectively reduce all types of wastes, including hazardous, mixed, radioactive, and nonhazardous wastes. The ANL Waste Minimization Plan uses a waste minimization audit as a systematic procedure to determine opportunities to reduce or eliminate waste. To facilitate these audits, a computerized bar-coding procedure is being implemented at ANL to track hazardous wastes from where they are generated to their ultimate disposal. This paper describes the development of the ANL Waste Minimization Plan and a pilot demonstration of the how the ANL Plan audited the hazardous waste generated within a selected divisions of ANL. It includes quantitative data on the generation and disposal of hazardous waste at ANL and describes potential ways to minimize hazardous wastes. 2 refs., 5 figs., 8 tabs

Management of wildlife causing damage at Argonne National Laboratory-East, DuPage County, Illinois

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

The DOE, after an independent review, has adopted an Environmental Assessment (EA) prepared by the US Department of Agriculture (USDA) which evaluates use of an Integrated Wildlife Damage Management approach at Argonne National Laboratory-East (ANL-E) in DuPage County, Illinois (April 1995). In 1994, the USDA issued a programmatic Environmental Impact Statement (EIS) that covers nationwide animal damage control activities. The EA for Management of Wildlife Causing Damage at ANL-E tiers off this programmatic EIS. The USDA wrote the EA as a result of DOE`s request to USDA to prepare and implement a comprehensive Wildlife Management Damage Plan; the USDA has authority for animal damage control under the Animal Damage Control Act of 1931, as amended, and the Rural Development, Agriculture and Related Agencies Appropriations Act of 1988. DOE has determined, based on the analysis in the EA, that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, the preparation of an EIS is not required. This report contains the Environmental Assessment, as well as the Finding of No Significant Impact (FONSI).

Evaluation of the single-pass flow-through test to support a low-activity waste specification

International Nuclear Information System (INIS)

McGrail, B.P.; Peeler, D.K.

1995-09-01

A series of single-pass flow-through (SPFT) tests was performed on five reference low-activity waste glasses and a reference glass from the National Institute of Standards and Technology to support a product specification for low-activity waste (LAW) forms. The results showed that the SPFT test provides a means to quantitatively distinguish among LAW glass forms in terms of their forward reaction rate at a given temperature and solution pH. Two of the test glasses were also subjected to SPFT testing at Argonne National Laboratory (ANL). Forward reaction rate constants calculated from the ANL test data were 100 to over 1,000 times larger than the values obtained from the SPFT tests conducted at PNL. An analysis of the ANL results showed that they were inconsistent with independent measurements done on glasses of similar composition, the known pH-dependence of the forward rate, and with the results from low surface-area-to-volume, short duration product consistency tests. Because the data set obtained from the SPFT tests done at PNL was consistent with each of these same factors, a detailed examination of the test procedures used at both laboratories was performed to determine the cause(s) of the discrepancy. The omission of background subtraction in the data analysis procedure and the short-duration (on the order of hours) of the ANL tests are factors that may have significantly affected the calculated rates

Contamination source review for Building E3236, Edgewood Area, Aberdeen Proving Ground, Maryland

Energy Technology Data Exchange (ETDEWEB)

Zellmer, S.D.; Smits, M.P.; Draugelis, A.K.; Glennon, M.A.; Rueda, J.; Zimmerman, R.E.

1995-09-01

The US Army Aberdeen Proving Ground (APG) commissioned Argonne National Laboratory (ANL) to conduct a contamination source review to identify and define areas of toxic or hazardous contaminants and to assess the physical condition and accessibility of APG buildings. The information obtained from the review may be used to assist the US Army in planning for the future use or disposition of the buildings. The contamination source review consisted of the following tasks: historical records search, physical inspection, photographic documentation, geophysical investigation, and review of available records regarding underground storage tanks associated with each building. This report provides the results of the contamination source review for Building E3236. Many of the APG facilities constructed between 1917 and the 1960s are no longer used because of obsolescence and their poor state of repair. Because many of these buildings were used for research, development, testing, and/or pilot- scale production of chemical warfare agents and other military substances, the potential exists for portions of the buildings to be contaminated with these substances, their degradation products, and other laboratory or industrial chemicals. These buildings and associated structures or appurtenances may contribute to environmental concerns at APG.

Recommendations for Filler Material Composition and Delivery Method for Bench-Scale Testing

Energy Technology Data Exchange (ETDEWEB)

Hardin, Ernest [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brady, Patrick Vane [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2018-03-01

This report supplements Joint Workplan on Filler Investigations for DPCs (SNL 2017) providing new and some corrected information for use in planning Phase 1 laboratory testing of slurry cements as possible DPC fillers. The scope description is to "Describe a complete laboratory testing program for filler composition, delivery, emplacement in surrogate canisters, and post-test examination. To the extent possible specify filler material and equipment sources." This report includes results from an independent expert review (Dr. Arun Wagh, retired from Argonne National Laboratory and contracted by Sandia) that helped to narrow the range of cement types for consideration, and to provide further guidance on mix variations to optimize injectability, durability, and other aspects of filler performance.

Testing the ability of a semidistributed hydrological model to simulate contributing area

Science.gov (United States)

Mengistu, S. G.; Spence, C.

2016-06-01

A dry climate, the prevalence of small depressions, and the lack of a well-developed drainage network are characteristics of environments with extremely variable contributing areas to runoff. These types of regions arguably present the greatest challenge to properly understanding catchment streamflow generation processes. Previous studies have shown that contributing area dynamics are important for streamflow response, but the nature of the relationship between the two is not typically understood. Furthermore, it is not often tested how well hydrological models simulate contributing area. In this study, the ability of a semidistributed hydrological model, the PDMROF configuration of Environment Canada's MESH model, was tested to determine if it could simulate contributing area. The study focused on the St. Denis Creek watershed in central Saskatchewan, Canada, which with its considerable topographic depressions, exhibits wide variation in contributing area, making it ideal for this type of investigation. MESH-PDMROF was able to replicate contributing area derived independently from satellite imagery. Daily model simulations revealed a hysteretic relationship between contributing area and streamflow not apparent from the less frequent remote sensing observations. This exercise revealed that contributing area extent can be simulated by a semi-distributed hydrological model with a scheme that assumes storage capacity distribution can be represented with a probability function. However, further investigation is needed to determine if it can adequately represent the complex relationship between streamflow and contributing area that is such a key signature of catchment behavior.

Closure report for CAU 339: Area 12 Fleet Operations steam-cleaning discharge area, Nevada Test Site

International Nuclear Information System (INIS)

1997-12-01

This Closure Report (CR) provides documentation of the completed corrective action at the Area 12 Fleet Operations site located in the southeast portion of the Area 12 Camp at the Nevada Test Site (NTS). Field work was performed in July 1997 as outlined in the Corrective Action Plan (CAP). The CAP was approved by the Nevada Division of Environmental Protection (NDEP) in June 1997. This site is identified in the Federal Facility Agreement and Consent Order (FFACO) as Corrective Action Site (CAS) Number 12-19-01 and is the only CAS in Corrective Action Unit (CAU) 339. The former Area 12 Fleet Operations Building 12-16 functioned as a maintenance facility for light- and heavy-duty vehicles from approximately 1965 to January 1993. Services performed at the site included steam-cleaning, tire service, and preventative maintenance on vehicles and equipment. Past activities impacted the former steam-cleaning discharge area with volatile organic compounds (VOCs) and total petroleum hydrocarbons (TPH) as oil

Underground test area subproject waste management plan. Revision No. 1

International Nuclear Information System (INIS)

1996-08-01

The Nevada Test Site (NTS), located in southern Nevada, was the site of 928 underground nuclear tests conducted between 1951 and 1992. The tests were performed as part of the Atomic Energy Commission and U.S. Department of Energy (DOE) nuclear weapons testing program. The NTS is managed by the DOE Nevada Operations Office (DOE/NV). Of the 928 tests conducted below ground surface at the NTS, approximately 200 were detonated below the water table. As an unavoidable consequence of these testing activities, radionuclides have been introduced into the subsurface environment, impacting groundwater. In the few instances of groundwater sampling, radionuclides have been detected in the groundwater; however, only a very limited investigation of the underground test sites and associated shot cavities has been conducted to date. The Underground Test Area (UGTA) Subproject was established to fill this void and to characterize the risk posed to human health and the environment as a result of underground nuclear testing activities at the NTS. One of its primary objectives is to gather data to characterize the deep aquifer underlying the NTS

Nevada Test Site Area 25. Radiological survey and cleanup project, 1974-1983. Final report

International Nuclear Information System (INIS)

McKnight, R.K.; Rosenberry, C.E.; Orcutt, J.A.

1984-01-01

This report describes radiological survey, decontamination and decommissioning of the Nevada Test Site (NTS) Area 25 facilities and land areas incorporated in the Nuclear Rocket Development Station (NRDS). Buildings, facilities and support systems used after 1959 for nuclear reactor and engine testing were surveyed for the presence of radioactive contamination. The cleanup was part of the Surplus Facilities Management Program funded by the Department of Energy's Richland Operations Office. The radiological survey portion of the project encompassed portable instrument surveys and removable contamination surveys (swipe) for alpha and beta plus gamma radiation contamination of facilities, equipment and land areas. Soil sampling was also accomplished. The majority of Area 25 facilities and land areas have been returned to unrestricted use. Remaining radiologically contaminated areas are posted with warning signs and barricades. 12 figures

Hydrologic resources management program and underground test area operable unit fy 1997

Energy Technology Data Exchange (ETDEWEB)

Smith, D. F., LLNL

1998-05-01

This report present the results of FY 1997 technical studies conducted by the Lawrence Livermore National Laboratory (LLNL) as part of the Hydrology and Radionuclide Migration Program (HRMP) and Underground Test Area Operable Unit (UGTA). The HRMP is sponsored by the US Department of Energy to assess the environmental (radiochemical and hydrologic) consequences of underground nuclear weapons testing at the Nevada Test Site.

Corrective action investigation plan for CAU Number 453: Area 9 Landfill, Tonopah Test Range

International Nuclear Information System (INIS)

1997-01-01

This Corrective Action Investigation Plan (CAIP) contains the environmental sample collection objectives and criteria for conducting site investigation activities at the Area 9 Landfill, Corrective Action Unit (CAU) 453/Corrective Action (CAS) 09-55-001-0952, which is located at the Tonopah Test Range (TTR). The TTR, included in the Nellis Air Force Range, is approximately 255 kilometers (140 miles) northwest of Las Vegas, Nevada. The Area 9 Landfill is located northwest of Area 9 on the TTR. The landfill cells associated with CAU 453 were excavated to receive waste generated from the daily operations conducted at Area 9 and from range cleanup which occurred after test activities

Beliefs about chlamydia testing amongst young people living in relatively deprived areas.

Science.gov (United States)

Booth, A R; Harris, P R; Goyder, E; Norman, P

2013-06-01

This study uses the theory of planned behaviour (TPB) as a framework to investigate salient beliefs about chlamydia testing, amongst young people living in relatively deprived areas. These beliefs may form targets for intervention to increase testing in this high-risk population. Participants recruited from colleges in deprived areas of a UK city, completed open-ended questions designed to elicit salient beliefs. Responses were content analysed and categorized as describing behavioural, normative or control beliefs. Beliefs were elicited from 128 respondents (51% male; median age = 17). The commonest behavioural belief, which could have a positive or negative impact on screening intentions, was that testing provides information about health status. Partners were referred to most commonly amongst the normative beliefs. Practical aspects and concerns about social implications of testing were common control beliefs. References to several negative emotions emerged throughout. This study indicates that raising awareness of chlamydia as a serious sexual health problem may not be the best way to increase the uptake of testing in a high-risk population. Promoting chlamydia testing as potentially providing reassurance may be an alternative. It may also be important to reduce perceptions of social disapproval as well as negative emotion regarding chlamydia testing.

User's manual for the ARMLID (Argonne metallic lithium/isotopic dilution) tritium assay system

International Nuclear Information System (INIS)

Porges, K.G.; Bretscher, M.M.; Bennett, E.F.; DiIorio, G.; Mattas, R.F.; Lewandowski, E.F.

1992-08-01

The Argonne Metallic Lithium - Isotopic Dilution (ARMLID) system described in this report, originally developed at ANL for other purposes, was recently redeployed to measure the tritium production rate (TPR) in a series of US/Japanese collaborative fusion blanket integral experiments, involving large assemblies of fusion breeder blanket materials that were irradiated with a fusion neutron source at FNS/JAERI, Japan. Whereas previous uses of the ARMUD scheme involved just a few samples, its application infusion blanket TPR mapping called for large sample numbers per experiment, implying a commensurate scale of sample fabrication and encapsulation, on one hand, and tritium extraction and counting on the other hand. To shorten the time required for these various tasks, yet still yield reliable and accurate results, both the sample fabrication - encapsulation facility and the tritium extraction system had to be extensively revised from original versions that were designed for accuracy, but not necessarily for speed. The present report describes overall revisions in sufficient detail to serve as a User's Manual for this facility, and/or suggest how a new system might be put together. Either possibility may develop in the near future, in support of ITER design studies. Preliminary and partial descriptions of various aspects and features of the system were presented orally, in the course of annual ANL/JAERI/UCLA ''workshops'', over the last 34 years, as well as elsewhere

Large-area photogrammetry based testing of wind turbine blades

Science.gov (United States)

Poozesh, Peyman; Baqersad, Javad; Niezrecki, Christopher; Avitabile, Peter; Harvey, Eric; Yarala, Rahul

2017-03-01

An optically based sensing system that can measure the displacement and strain over essentially the entire area of a utility-scale blade leads to a measurement system that can significantly reduce the time and cost associated with traditional instrumentation. This paper evaluates the performance of conventional three dimensional digital image correlation (3D DIC) and three dimensional point tracking (3DPT) approaches over the surface of wind turbine blades and proposes a multi-camera measurement system using dynamic spatial data stitching. The potential advantages for the proposed approach include: (1) full-field measurement distributed over a very large area, (2) the elimination of time-consuming wiring and expensive sensors, and (3) the need for large-channel data acquisition systems. There are several challenges associated with extending the capability of a standard 3D DIC system to measure entire surface of utility scale blades to extract distributed strain, deflection, and modal parameters. This paper only tries to address some of the difficulties including: (1) assessing the accuracy of the 3D DIC system to measure full-field distributed strain and displacement over the large area, (2) understanding the geometrical constraints associated with a wind turbine testing facility (e.g. lighting, working distance, and speckle pattern size), (3) evaluating the performance of the dynamic stitching method to combine two different fields of view by extracting modal parameters from aligned point clouds, and (4) determining the feasibility of employing an output-only system identification to estimate modal parameters of a utility scale wind turbine blade from optically measured data. Within the current work, the results of an optical measurement (one stereo-vision system) performed on a large area over a 50-m utility-scale blade subjected to quasi-static and cyclic loading are presented. The blade certification and testing is typically performed using International

ENVIRONMENTAL REVIEWS AND CASE STUDIES: Addressing the Public Outreach Responsibilities of the National Historic Preservation Act: Argonne National Laboratory’s Box Digital Display Platform

Energy Technology Data Exchange (ETDEWEB)

O’Rourke, Daniel J.; Weber, Cory C.; Richmond, Pamela D.

2016-07-29

Federal agencies are made responsible for managing the historic properties under their jurisdiction by the National Historic Preservation Act of 1966, as amended. A component of this responsibility is to mitigate the effect of a federal undertaking on historic properties through mitigation often through documentation. Providing public access to this documentation has always been a challenge. To address the issue of public access to mitigation information, personnel from Argonne National Laboratory created the Box Digital Display Platform, a system for communicating information about historic properties to the public. The platform, developed for the US Army Dugway Proving Ground, uses short introductory videos to present a topic but can also incorporate photos, drawings, GIS information, and documents. The system operates from a small, self-contained computer that can be attached to any digital monitor via an HDMI cable. The system relies on web-based software that allows the information to be republished as a touch-screen device application or as a website. The system does not connect to the Internet, and this increases security and eliminates the software maintenance fees associated with websites. The platform is designed to incorporate the products of past documentation to make this information more accessible to the public; specifically those documentations developed using the Historic American Building Survey/ Historic American Engineering Record (HABS/HAER) standards. Argonne National Laboratory’s Box Digital Display Platform can assist federal agencies in complying with the requirements of the National Historic Preservation Act.

Environmental Practice 18: 209–213 (2016)

Vibrodynamical tests of RP equipment with application of imitation area of WWER-1000 reactor

International Nuclear Information System (INIS)

Khajretdinov, V.U.; Tarkhanov, V.V.; Rodionova, I.N.

2015-01-01

Performance of preoperational tests and measurements with application of imitation area of the reactor is a distinctive characteristic of putting into operation of NPP Units with WWER-1000/1200. The imitation area consists of 163 full-scale FA models, where fuel matrixes made of nuclear-fissionable material, are replaced by leaden simulators. Vibrodynamic tests involve inspection of hydrodynamic disturbances in the primary circuit (dynamic impact on the inspected elements), characteristics of vibration response of the main equipment stress-deformed state of bearing structure, and also parameters of moving and geometry of the inspected objects (boundary conditions at process simulation). Preoperational tests and measurements on the simulated area of WWER-1000/1200 are obligatory and performed at every unit of NPP of this type [ru

Operational experience of a large area x-ray camera for protein crystallography

International Nuclear Information System (INIS)

Joachimiak, A.; Jorden, A. R.; Loeffen, P. W.; Naday, I.; Sanishvili, R.; Westbrook, E. M.

1999-01-01

After 3 years experience of operating very large area (210mm x 210mm) CCD-based detectors at the Advanced Photon Source, operational experience is reported. Four such detectors have been built, two for Structural Biology Center (APS-1 and SBC-2), one for Basic Energy Sciences Synchrotrons Radiation Center (Gold-2) at Argonne National Laboratory's Advanced Photon Source and one for Osaka University by Oxford Instruments, for use at Spring 8 (PX-21O). The detector is specifically designed as a high resolution and fast readout camera for macromolecular crystallography. Design trade-offs for speed and size are reviewed in light of operational experience and future requirements are considered. Operational data and examples of crystallography data are presented, together with plans for more development

An implementation and test platform for wide area stability assessment methods

DEFF Research Database (Denmark)

Wittrock, Martin Lindholm; Jóhannsson, Hjörtur

2013-01-01

Units (PMU) can be very time consuming, especially if the testing procedure is not carried out in a systematic and automatic manner. The test platform overcomes this problem by automatically importing system model parameters, topology and simulation output from a time domain simulation of an instability...... scenario and automatically generating synthetic PMU snapshots of the system conditions. To demonstrate the platform’s potential for supporting research and development of wide area algorithms, a method to detect voltage instability is implemented and tested, giving results consistent with results from...

The time-of-flight small-angle neutron diffractometer (SAD) at IPNS, Argonne National Laboratory

International Nuclear Information System (INIS)

Thiyagarajan, P.; Epperson, J.E.; Crawford, R.K.; Carpenter, J.M.; Klippert, T.E.; Wozniak, D.G.

1997-01-01

The design, development and performance of the time-of-flight (TOF) small-angle diffractometer (SAD) at the Intense Pulsed Neutron Source (IPNS) at Argonne National Laboratory are described. Similar TOF-SANS instruments are in operation at the pulsed neutron sources at Los Alamos National Laboratory, USA, at Rutherford Appleton Laboratory, England, and at KEK, Japan. These instruments have an advantage by comparison with their steady-state counterparts in that a relatively wide range of momentum transfer (q) can be monitored in a single experiment without the need to alter the collimation or the sample-to-detector distance. This feature makes SANS experiments easy and very effective for studying systems such as those undergoing phase transitions under different conditions, samples that cannot be easily reproduced for repetitive experiments, and systems under high temperature, pressure or shear. Three standard samples are used to demonstrate that the quality of the SANS data from SAD is comparable with those from other established steady-state SANS facilities. Two examples are given to illustrate that the wide q region accessible in a single measurement at SAD is very effective for following the time-dependent phase transitions in paraffins and temperature- and pressure-dependent phase transitions in model biomembranes. (orig.)

Evolution of thermal-hydraulics testing in EBR-II

International Nuclear Information System (INIS)

Golden, G.H.; Planchon, H.P.; Sackett, J.I.; Singer, R.M.

1987-01-01

A thermal-hydraulics testing and modeling program has been underway at the Experimental Breeder Reactor-II (EBR-II) for 12 years. This work culminated in two tests of historical importance to commercial nuclear power, a loss of flow without scram and a loss of heat sink wihout scram, both from 100% initial power. These tests showed that natural processes will shut EBR-II down and maintain cooling without automatic control rod action or operator intervention. Supporting analyses indicate that these results are characteristic of a range of sizes of liquid metal cooled reactors (LMRs), if these reactors use metal driver fuel. This type of fuel is being developed as part of the Integral Fast Reactor Program at Argonne National Laboratory. Work is now underway at EBR-II to exploit the inherent safety of metal-fueled LMRs with regard to development of improved plant control strategies. (orig.)

Initial SVE Well Testing for the A-Area Miscellaneous Rubble Pile (ARP) Trenches Area

International Nuclear Information System (INIS)

RIHA, BRIAN

2004-01-01

The A-Area Miscellaneous Rubble Pile (ARP) is a 5.9 acre unit located at the southern end of A/M Area at the Savannah River Site (SRS). Disposal activities at ARP began in the early 1950s. The exact dates of operation and material disposed in the unit remain unknown. Within the ARP exists a smaller, approximately 2 acre, sub unit identified as the Trenches Area. The Trenches Area is dominated by a T-shaped trench (approximately 50 feet wide) containing 8 to 12 feet of ash material. This T-shaped trench will be referred to as the ARP Trench. Vegetation has been removed from the Trenches Area and a lower permeability earthen cover now covers the ARP Trench. The ARP active soil vapor extraction (ASVE) remediation system consists of seven extraction wells and twelve monitoring wells that were pushed into the vadose zone of the ARP Trench. The remediation system was designed based on the pre-design study conducted in 2002. The purpose of the initial soil vapor extraction (SVE) well testing was to verify the integrity and functionality of the nineteen wells installed in the ARP Trench. The well integrity was evaluated based on the flow rate, vacuum, and indication that soil gas and not surface air was pulled from the well. Soil gas was defined as gas with levels of carbon dioxide (CO2) above ambient concentrations (400-700 ppmv). Volatile organic compound (VOC) concentrations were measured at each well to determine the initial distribution of the contamination. In addition, the subsurface vacuum distribution was measured around each extraction well as a relative measure of the influence of each well

James Webb Space Telescope Core 2 Test - Cryogenic Thermal Balance Test of the Observatorys Core Area Thermal Control Hardware

Science.gov (United States)

Cleveland, Paul; Parrish, Keith; Thomson, Shaun; Marsh, James; Comber, Brian

2016-01-01

The James Webb Space Telescope (JWST), successor to the Hubble Space Telescope, will be the largest astronomical telescope ever sent into space. To observe the very first light of the early universe, JWST requires a large deployed 6.5-meter primary mirror cryogenically cooled to less than 50 Kelvin. Three scientific instruments are further cooled via a large radiator system to less than 40 Kelvin. A fourth scientific instrument is cooled to less than 7 Kelvin using a combination pulse-tube Joule-Thomson mechanical cooler. Passive cryogenic cooling enables the large scale of the telescope which must be highly folded for launch on an Ariane 5 launch vehicle and deployed once on orbit during its journey to the second Earth-Sun Lagrange point. Passive cooling of the observatory is enabled by the deployment of a large tennis court sized five layer Sunshield combined with the use of a network of high efficiency radiators. A high purity aluminum heat strap system connects the three instrument's detector systems to the radiator systems to dissipate less than a single watt of parasitic and instrument dissipated heat. JWST's large scale features, while enabling passive cooling, also prevent the typical flight configuration fully-deployed thermal balance test that is the keystone of most space missions' thermal verification plans. This paper describes the JWST Core 2 Test, which is a cryogenic thermal balance test of a full size, high fidelity engineering model of the Observatory's 'Core' area thermal control hardware. The 'Core' area is the key mechanical and cryogenic interface area between all Observatory elements. The 'Core' area thermal control hardware allows for temperature transition of 300K to approximately 50 K by attenuating heat from the room temperature IEC (instrument electronics) and the Spacecraft Bus. Since the flight hardware is not available for test, the Core 2 test uses high fidelity and flight-like reproductions.

Design of neutron beams at the Argonne Continuous Wave Linac (ACWL) for boron neutron capture therapy and neutron radiography

International Nuclear Information System (INIS)

Zhou, X.L.; McMichael, G.E.

1994-01-01

Neutron beams are designed for capture therapy based on p-Li and p-Sc reactions using the Argonne Continuous Wave Linac (ACWL). The p-Li beam will provide a 2.5 x 10 9 n/cm 2 s epithermal flux with 7 x 10 5 γ/cm 2 s contamination. On a human brain phantom, this beam allows an advantage depth (AD) of 10 cm, an advantage depth dose rate (ADDR) of 78 cGy/min and an advantage ratio (AR) of 3.2. The p-Sc beam offers 5.9 x 10 7 n/cm 2 s and a dose performance of AD = 8 cm and AR = 3.5, suggesting the potential of near-threshold (p,n) reactions such as the p-Li reaction at E p = 1.92 MeV. A thermal radiography beam could also be obtained from ACWL

Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas

International Nuclear Information System (INIS)

1990-01-01

This report describes the Offsite Radiation Safety Program conducted during 1990 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory -- Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of animals, food crops, and humans. Personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each nuclear weapons test to implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any occurrence of radioactivity release

Progress report and technical evaluation of the ISCR pilot test conducted at the former CCC/USDA grain storage facility in Centralia, Kansas.

Energy Technology Data Exchange (ETDEWEB)

LaFreniere, L. M.; Environmental Science Division

2009-01-14

In October, 2007, the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) presented the document Interim Measure Conceptual Design (Argonne 2007a) to the Kansas Department of Health and Environment, Bureau of Environmental Remediation (KDHE/BER), for a proposed non-emergency Interim Measure (IM) at the site of the former CCC/USDA grain storage facility in Centralia, Kansas (Figure 1.1). The IM was recommended to mitigate existing levels of carbon tetrachloride contamination identified in the vadose zone soils beneath the former facility and in the groundwater beneath and in the vicinity of the former facility, as well as to moderate or decrease the potential future concentrations of carbon tetrachloride in the groundwater. The Interim Measure Conceptual Design (Argonne 2007a) was developed in accordance with the KDHE/BER Policy No.BERRS-029, Policy and Scope of Work: Interim Measures (KDHE 1996). The hydrogeologic, geochemical, and contaminant distribution characteristics of the Centralia site, as identified by the CCC/USDA, factored into the development of the nonemergency IM proposal. These characteristics were summarized in the Interim Measure Conceptual Design (Argonne 2007a) and were discussed in detail in previous Argonne reports (Argonne 2002a, 2003, 2004, 2005a,b,c, 2006a,b, 2007b). The identified remedial goals of the proposed IM were as follows: (1) To reduce the existing concentrations of carbon tetrachloride in groundwater in three 'hot spot' areas identified at the site (at SB01, SB05, and SB12-MW02; Figure 1.2) to levels acceptable to the KDHE. (2) To reduce carbon tetrachloride concentrations in the soils near the location of former soil boring SB12 and existing monitoring well MW02 (Figure 1.2) to levels below the KDHE Tier 2 Risk-Based Screening Level (RBSL) of 200 {micro}g/kg for this contaminant. To address these goals, the potential application of an in situ chemical reduction (ISCR) treatment technology

Treatability Test Plan for 300 Area Uranium Stabilization through Polyphosphate Injection

International Nuclear Information System (INIS)

Vermeul, Vince R.; Williams, M. D.; Fritz, Brad G.; Mackley, Rob D.; Mendoza, Donaldo P.; Newcomer, Darrell R.; Rockhold, Mark L.; Williams, Bruce A.; Wellman, Dawn M.

2007-01-01

The U.S. Department of Energy has initiated a study into possible options for stabilizing uranium at the 300 Area using polyphosphate injection. As part of this effort, PNNL will perform bench- and field-scale treatability testing designed to evaluate the efficacy of using polyphosphate injections to reduced uranium concentrations in the groundwater to meet drinking water standards (30 (micro)g/L) in situ. This technology works by forming phosphate minerals (autunite and apatite) in the aquifer that directly sequester the existing aqueous uranium in autunite minerals and precipitates apatite minerals for sorption and long term treatment of uranium migrating into the treatment zone, thus reducing current and future aqueous uranium concentrations. Polyphosphate injection was selected for testing based on technology screening as part of the 300-FF-5 Phase III Feasibility Study for treatment of uranium in the 300-Area

Treatability Test Plan for 300 Area Uranium Stabilization through Polyphosphate Injection

Energy Technology Data Exchange (ETDEWEB)

Vermeul, Vincent R.; Williams, Mark D.; Fritz, Brad G.; Mackley, Rob D.; Mendoza, Donaldo P.; Newcomer, Darrell R.; Rockhold, Mark L.; Williams, Bruce A.; Wellman, Dawn M.

2007-06-01

The U.S. Department of Energy has initiated a study into possible options for stabilizing uranium at the 300 Area using polyphosphate injection. As part of this effort, PNNL will perform bench- and field-scale treatability testing designed to evaluate the efficacy of using polyphosphate injections to reduced uranium concentrations in the groundwater to meet drinking water standards (30 ug/L) in situ. This technology works by forming phosphate minerals (autunite and apatite) in the aquifer that directly sequester the existing aqueous uranium in autunite minerals and precipitates apatite minerals for sorption and long term treatment of uranium migrating into the treatment zone, thus reducing current and future aqueous uranium concentrations. Polyphosphate injection was selected for testing based on technology screening as part of the 300-FF-5 Phase III Feasibility Study for treatment of uranium in the 300-Area.

June 2012 Groundwater Sampling at the Central Nevada Test Area (Data Validation Package)

International Nuclear Information System (INIS)

2013-01-01

The U.S. Department of Energy Office of Legacy Management conducted annual sampling at the Central Nevada Test Area (CNTA) on June 26-27, 2012, in accordance with the 2004 Correction Action Decision Document/Corrective Action Plan for Corrective Action Unit 443: Central Nevada Test Area (CNTA)-Subsurface and the addendum to the 'Corrective Action Decision Document/Corrective Action Plan' completed in 2008. Sampling and analysis were conducted as specified in the Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites (LMS/PLN/S04351), continually updated).

May 2011 Groundwater Sampling at the Central Nevada Test Area (Data Validation Package)

International Nuclear Information System (INIS)

2011-01-01

The U.S. Department of Energy Office of Legacy Management conducted annual sampling at the Central Nevada Test Area (CNTA) on May 10-11, 2011, in accordance with the 2004 Correction Action Decision Document/Corrective Action Plan for Corrective Action Unit 443: Central Nevada Test Area (CNTA)-Subsurface and the addendum to the 'Corrective Action Decision Document/Corrective Action Plan' completed in 2008. Sampling and analysis were conducted as specified in the Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites (LMS/PLN/S04351), continually updated)

Nevada Test 1999 Waste Management Monitoring Report, Area 3 and Area 5 radioactive waste management sites

International Nuclear Information System (INIS)

Yvonne Townsend

2000-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS). These monitoring data include radiation exposure, air, groundwater, meteorology, vadose zone, and biota data. Although some of these media (radiation exposure, air, and groundwater) are reported in detail in other Bechtel Nevada reports (Annual Site Environmental Report [ASER], the National Emissions Standard for Hazardous Air Pollutants [NESHAP] report, and the Annual Groundwater Monitoring Report), they are also summarized in this report to provide an overall evaluation of RWMS performance and environmental compliance. Direct radiation monitoring data indicate that exposure at and around the RWMSs is not above background levels. Air monitoring data indicate that tritium concentrations are slightly above background levels, whereas radon concentrations are not above background levels. Groundwater monitoring data indicate that the groundwater in the alluvial aquifer beneath the Area 5 RWMS has not been affected by the facility. Meteorology data indicate that 1999 was a dry year: rainfall totaled 3.9 inches at the Area 3 RWMS (61 percent of average) and 3.8 inches at the Area 5 RWMS (75 percent of average). Vadose zone monitoring data indicate that 1999 rainfall infiltrated less than one foot before being returned to the atmosphere by evaporation. Soil-gas tritium data indicate very slow migration, and tritium concentrations in biota were insignificant. All 1999 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing as expected at isolating buried waste

Aquifer pumping test report for the burn site groundwater area of concern

Energy Technology Data Exchange (ETDEWEB)

Skelly, Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ferry, Robert [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-12-01

The Aquifer Pumping Test Report for the Burn Site Groundwater (BSG) Area of Concern is being submitted by National Technology and Engineering Solutions of Sandia, LLC and the U.S. Department of Energy (DOE)/National Nuclear Security Administration to describe the results of the aquifer pumping test program and related field activities that were completed at the BSG Area of Concern. This report summarizes the results of the field work and data analyses, and is being submitted to the New Mexico Environment Department (NMED) Hazardous Waste Bureau, as required by the April 14, 2016 letter, Summary of Agreements and Proposed Milestones Pursuant to the Meeting of July 20, 2015, (NMED April 2016).

BWR recirculation loop discharge line break LOCA tests with break areas of 50 and 100% assuming HPCS failure at ROSA-III test facility

International Nuclear Information System (INIS)

Suzuki, Mitsuhiro; Tasaka, Kanji; Yonomoto, Taisuke; Anoda, Yoshinari; Kumamaru, Hiroshige; Nakamura, Hideo; Murata, Hideo; Shiba, Masayoshi; Iriko, Masanori.

1985-03-01

This report presents the experimental results of RUN 962 and RUN 963 in ROSA-III program, which are 50 and 100 % break LOCA tests at the BWR recirculation pump discharge line, respectively. The ROSA-III test facility simulates a volumetrically scaled (1/424) BWR system and has four half-length electrically heated fuel bundles, two active recirculation loops, three types of ECCSs and steam and feedwater systems. The experimental data of RUN 962 and RUN 963 were compared with those of RUN 961, a 200 % discharge line break test to study the break area effects on the transient thermal hydraulic phenomena. The least flow areas at the jet pump drive nozzles and recirculation pump discharge nozzle in the broken recirculation loop limitted the discharge flows from the pressure vessel and the depressurization rate in the 100 and 200 % break tests, whereas the least flow area at break nozzle limitted the depressurization rate in the 50 % break test. The highest PCT was observed in the 50 % break test among the three tests. (author)

Pilot-scale ultrafiltration testing for the F and H area effluent treatment facility

International Nuclear Information System (INIS)

Kessler, J.L.

1984-01-01

An F and H Area Effluent Treatment Facility (F/H ETF) is being designed to treat low activity aqueous effluents which are produced from F and H Area daily operations. The treatment scheme for the F/H ETF will include pretreatment (pH adjustment and filtration) followed by Reverse Osmosis and/or Ion Exchange to remove dissolved species. Several alternative treatment processes are being considered for the F/H ETF. One of the alternatives in the pretreatment step is tubular Ultrafiltration (UF), using a dynamically formed zirconium oxide membrane supported on a porous stainless steel backing. Pilot-scale testing with a single membrane module (13 ft 2 area) and 200-Area effluent simulant has demonstrated that UF is a viable filtration option for the F/H ETF. UF testing at TNX has defined the operating conditions necessary for extended operation and also demonstrated excellent filtration performance (filtrate SDI 2 /day) flux and will provide excellent pretreatment for both reverse osmosis and ion exchange. 2 refs

Beam tests and operation of superconducting cavities

International Nuclear Information System (INIS)

Akai, Kazunori

1990-01-01

Beam tests and operation of superconducting cavities conducted since the third workshop on RF superconductivity (Argonne, Sep. 1987) are reported in this paper. The paper is concerned particularly with electron machines. Storage and acceleration of the beam are discussed, focusing on the CERN test in SPS, the DESY test in PETRA, the superconducting injector at Darmstadt, and the KEK beam tests in T-AR. Then, long-term performance of the cavity in the ring is discussed focusing on Eacc (max) and O-value, environmental conditions, and operational experience in T-MR. RF controllability is addressed, centering on the Robinson stability, cavity tuning loop, quench detection and interlocks, recovery procedure, field calibration, and phase adjustment. Higher order modes are also discussed. Superconducting cavities have been operated successfully in accelerators. It has been confirmed that the superconducting cavities can be used stably for experimental use. For more than 5000 hours the cavities have indicated no essential degradation of the cavity performance. The study of long-term performance should be continued in longer range of period. (N.K.)

Chronic radiation injury with mice and dogs exposed to external whole-body irradiation at the Argonne National Laboratory

International Nuclear Information System (INIS)

Grahn, D.; Fritz, T.E.

1986-01-01

This document describes studies on chronic radiation injury in experimental animals and the extrapolation of derived injury parameters to man. Most of the large studies have used mice given single, weekly, or continuous exposure to cobalt-60 gamma rays, or, more recently, single or weekly exposure to fission neutrons from the JANUS reactor. Primary measures of injury have been life shortening and the associated major pathological changes, particularly neoplastic diseases. Recent and ongoing studies compare the effects of extremely low neutron exposures with gamma irradiations delivered as a single dose or in 60 equal weekly increments. Total neutron doses range from 1 to 40 rads; gamma-ray doses range from 22.5 to 600 rads. Selected genetic studies are performed concurrently to provide a nearly complete matrix of somatic and genetic effects of these low exposures. Studies with the beagle have complemented those with mice and have shown a strong parallelism in the responses of the two species. Present exposures are at 0.3, 0.75, and 1.88 rads per day of continuous gamma irradiation to test a model for the prediction of life shortening in man which has evolved from Argonne's long-term studies. The dog offers the opportunity for longitudinal clinical evaluations that are not possible in the mouse, to develop a broader view of the neoplastic disease spectrum, and to study the mechanisms of radiation induction of leukemia. Diverse statistical approaches have been used to measure excess risk, dose-response functions, and rates of injury and repair. Actuarial statistical methods have been favored since they permit a more direct means of extrapolation to man. 50 refs., 4 figs

Computerization aspects of the Health Physics' Radiation Control Program at Argonne National Laboratory

International Nuclear Information System (INIS)

Dolecek, Elwyn H.

1978-01-01

Greater public awareness of the potential hazards of ionizing radiation and the more stringent governmental compliance programs have made accountability of radioactive materials an item of increasingly major concern for all radionuclide users. For low-volume (radioisotopically) organizations, manual record keeping techniques may suffice without requiring significant work-hour allocations. When considering high-volume users, the workload contingent with manual inventory is usually excessive from an employee time-allocation standpoint. Therefore, various automation systems are employed, usually with the aid of an in-house or time-purchase computer system. The computer programs developed for these systems often do not allow for future modification without major rewriting. Therefore, to facilitate in program concept, modification, and implementation the Health Physics Section at Argonne National Laboratory chose to design and code its computer program(s) and has instituted a Radiation Administrative Program (RAP) as a major component of the Section's laboratory-wide radiation control program. Coded in ANSI PL/I, RAP provides both flexibility in present concept and allowance for future growth. It requires less than 300K words of computer memory and can be easily incorporated at other organizations with minimal modifications. The modular design provides run cost benefits and versatility of report generation and modification. Through the use of this type of information processing and retrieval system, one can manipulate large amounts of radionuclide data, providing control and identification, while still maintaining commitment of computer costs and employee time at a reasonable level. (author)

K Basin Sludge Conditioning Testing. Nitric Acid Dissolution Testing of K East Area Sludge Composite, Small- and Large-Scale Testing

International Nuclear Information System (INIS)

Carlson, C.D.; Delegard, C.H.; Burgeson, I.E.; Schmidt, A.J.; Silvers, K.L.

1998-01-01

This report describes work performed by Pacific Northwest National Laboratory (PNNL) for Numatec Hanford Corporation (NHC) to support the development of the K Basin Sludge Treatment System. For this work, testing was performed to examine the dissolution behavior of a K East Basin floor and Weasel Pit sludge composite, referred to as K East area sludge composite, in nitric acid at the following concentrations: 2 M, 4 M, 6 M and 7.8 M. With the exception of one high solids loading test the nitric acid was added at 4X the stoichiometric requirement (assuming 100% of the sludge was uranium metal). The dissolution tests were conducted at boiling temperatures for 24 hours. Most of the tests were conducted with approximately2.5 g of sludge (dry basis). The high solids loading test was conducted with approximately7 g of sludge. A large-scale dissolution test was conducted with 26.5 g of sludge and 620 mL of 6 M nitric acid. The objectives of this test were to (1) generate a sufficient quantity of acid-insoluble residual solids for use in leaching studies, and (2) examine the dissolution behavior of the sludge composite at a larger scale

Radiation monitoring around United States nuclear test areas, calendar year 1989

International Nuclear Information System (INIS)

1990-05-01

This report describes the Offsite Radiation Safety Program conducted during 1989 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory-Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels, and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether the testing is in compliance with existing radiation protection standards, and to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of both animals and humans. To implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any release of radioactivity, personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each test. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to NTS activities. Trends were evaluated in the Noble Gas and Tritium, Milk Surveillance, TLD, and PIC networks, and the Long-Term Hydrological Monitoring Program. 35 refs., 68 figs., 32 tabs

Radiation monitoring around United States nuclear test areas, calendar year 1989

Energy Technology Data Exchange (ETDEWEB)

1990-05-01

This report describes the Offsite Radiation Safety Program conducted during 1989 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory-Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels, and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether the testing is in compliance with existing radiation protection standards, and to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of both animals and humans. To implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any release of radioactivity, personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each test. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to NTS activities. Trends were evaluated in the Noble Gas and Tritium, Milk Surveillance, TLD, and PIC networks, and the Long-Term Hydrological Monitoring Program. 35 refs., 68 figs., 32 tabs.

Experimental investigations of long-term interactions of molten UO2 with MgO and concrete at Argonne National Laboratory

International Nuclear Information System (INIS)

Stein, R.P.; Farhadieh, R.; Pedersen, D.R.; Gunther, W.H.; Purviance, R.T.

1982-01-01

Experimental work at Argonne is being performed to investigate the long-term molten-core-debris retention capability of the ex-vessel cavity following a postulated meltdown accident. The eventual objective of the work is to determine if normal structural material (concrete) or a specifically selected sacrificial material (MgO) located in the ex-vessel cavity region can effectively contain molten core debris. The materials under investigation at ANL are various types of concrete (limestone, basalt and magnetite) and commercially-available MgO brick. Results are presented of the status of real material experimental investigation at ANL into (1) molten UO 2 pool heat transfer, (2) long-term molten UO 2 penetration into concrete and (3) long-term molten UO 2 penetration into refractory substrates. The decay heating in the fuel has been simulated by direct electrical heating permitting the study of the long-term interaction

Experimental investigations of long-term interactions of molten UO2 with MgO and concrete at Argonne National Laboratory

International Nuclear Information System (INIS)

Stein, R.P.; Farhadieh, R.; Pedersen, D.R.; Gunther, W.H.; Purviance, R.T.

1982-01-01

Experimental work at Argonne is being performed to investigate the long-term molten core debris retention capability of the ex-vessel cavity following a postulated meltdown accident. The eventual objective of the work is to determine if normal structural material (concrete) or a specifically selected sacrificial material (MgO) located in the ex-vessel cavity region can effectively contain molten core debris. The materials under investigation at ANL are various types of concrete (limestone, basalt and magnetite) and commercially-available MgO brick. Results are presented of the status of real material experimental investigation at ANL into 1) molten UO 2 pool heat transfer, 2) long-term molten UO 2 penetration into concrete and 3) long-term molten UO 2 penetration into refractory substrates. The decay heating in the fuel has been simulated by direct electrical heating permitting the study of the long-term interaction

Weibull statistics effective area and volume in the ball-on-ring testing method

DEFF Research Database (Denmark)

Frandsen, Henrik Lund

2014-01-01

The ball-on-ring method is together with other biaxial bending methods often used for measuring the strength of plates of brittle materials, because machining defects are remote from the high stresses causing the failure of the specimens. In order to scale the measured Weibull strength...... to geometries relevant for the application of the material, the effective area or volume for the test specimen must be evaluated. In this work analytical expressions for the effective area and volume of the ball-on-ring test specimen is derived. In the derivation the multiaxial stress field has been accounted...

The Effect of Pile-Up and Contact Area on Hardness Test by Nanoindentation

Science.gov (United States)

Miyake, Koji; Fujisawa, Satoru; Korenaga, Atsushi; Ishida, Takao; Sasaki, Shinya

2004-07-01

We used atomic force microscopy (AFM) for the indentation test evaluating the indentation hardness of materials in the nanometer range. BK7, fused silica, and single-crystal silicon were used as test sample materials. The data analysis processes used to determine the contact area were important in evaluating the indentation hardness of the materials. The direct measurement of the size of the residual hardness impression was useful in evaluating the contact area even in the nanometer region. The results led us to conclude that AFM indentation using a sharp indenter is a powerful method for estimating the indentation hardness in the nanometer range.

The conversion of a room temperature NaK loop to a high temperature MHD facility for Li/V blanket testing

International Nuclear Information System (INIS)

Reed, C.B.; Haglund, R.C.; Miller, M.E.; Nasiatka, J.R.; Kirillov, I.R.; Ogorodnikov, A.P.; Preslitski, G.V.; Goloubovitch, G.P.; Xu, Zeng Yu

1996-01-01

The Vanadium/Lithium system has been the recent focus of ANL's Blanket Technology Pro-ram, and for the last several years, ANL's Liquid Metal Blanket activities have been carried out in direct support of the ITER (International Thermonuclear Experimental Reactor) breeding blanket task area. A key feasibility issue for the ITER Vanadium/Lithium breeding blanket is the Near the development of insulator coatings. Design calculations, Hua and Gohar, show that an electrically insulating layer is necessary to maintain an acceptably low magneto-hydrodynamic (MHD) pressure drop in the current ITER design. Consequently, the decision was made to convert Argonne's Liquid Metal EXperiment (ALEX) from a 200 degrees C NaK facility to a 350 degrees C lithium facility. The upgraded facility was designed to produce MHD pressure drop data, test section voltage distributions, and heat transfer data for mid-scale test sections and blanket mockups at Hartmann numbers (M) and interaction parameters (N) in the range of 10 3 to 10 5 in lithium at 350 degrees C. Following completion of the upgrade work, a short performance test was conducted, followed by two longer multiple-hour, MHD tests, all at 230 degrees C. The modified ALEX facility performed up to expectations in the testing. MHD pressure drop and test section voltage distributions were collected at Hartmann numbers of 1000

Studies of nuclei using radioactive beams

International Nuclear Information System (INIS)

Piercey, R.B.

1989-07-01

The 12 month period from May 1988 to July 1989 represents the first full year of our 18 month pilot program in nuclear structure research. In this period, research was initiated to develop a capability for radioactive secondary beams at Argonne National Laboratory using the Atlas and the new Fragment Mass Analyzer (FMA), which is currently under construction. Two major new detector facilities are currently in the final stages of design and testing. The Large-Area, Scintillator Telescope (LAST) detector is fully operational and will be shipped to Argonne National Laboratory in August for fit-tests and in-beam calibrations. The first segments of a new sixteen-segment neutron multiplicity detector have been built and tested. The remaining segments are currently being constructed. Research was continued in the areas of (1) Coulomb excitation studies of rare earth and actinide nuclei; (2) In-beam, gamma-ray spectroscopy of nuclei in the mass 100 region, and (3) Advanced detector design. Several journal articles and abstracts were published or submitted for publication in the reporting period, and others are currently in preparation. Three graduate students participated in the program, one from the University of Florida and two from the Royal Institute of Technology, Stockholm, Sweden

Studies of nuclei using radioactive beams. [Space Astronomy Lab. , Univ. of Florida, Gainesville, Florida

Energy Technology Data Exchange (ETDEWEB)

Piercey, R.B.

1989-07-01

The 12 month period from May 1988 to July 1989 represents the first full year of our 18 month pilot program in nuclear structure research. In this period, research was initiated to develop a capability for radioactive secondary beams at Argonne National Laboratory using the Atlas and the new Fragment Mass Analyzer (FMA), which is currently under construction. Two major new detector facilities are currently in the final stages of design and testing. The Large-Area, Scintillator Telescope (LAST) detector is fully operational and will be shipped to Argonne National Laboratory in August for fit-tests and in-beam calibrations. The first segments of a new sixteen-segment neutron multiplicity detector have been built and tested. The remaining segments are currently being constructed. Research was continued in the areas of (1) Coulomb excitation studies of rare earth and actinide nuclei; (2) In-beam, gamma-ray spectroscopy of nuclei in the mass 100 region, and (3) Advanced detector design. Several journal articles and abstracts were published or submitted for publication in the reporting period, and others are currently in preparation. Three graduate students participated in the program, one from the University of Florida and two from the Royal Institute of Technology, Stockholm, Sweden.

Studies of nuclei using radioactive beams. Progress report, May 1988--July 1989

Energy Technology Data Exchange (ETDEWEB)

Piercey, R.B.

1989-07-01

The 12 month period from May 1988 to July 1989 represents the first full year of our 18 month pilot program in nuclear structure research. In this period, research was initiated to develop a capability for radioactive secondary beams at Argonne National Laboratory using the Atlas and the new Fragment Mass Analyzer (FMA), which is currently under construction. Two major new detector facilities are currently in the final stages of design and testing. The Large-Area, Scintillator Telescope (LAST) detector is fully operational and will be shipped to Argonne National Laboratory in August for fit-tests and in-beam calibrations. The first segments of a new sixteen-segment neutron multiplicity detector have been built and tested. The remaining segments are currently being constructed. Research was continued in the areas of (1) Coulomb excitation studies of rare earth and actinide nuclei; (2) In-beam, gamma-ray spectroscopy of nuclei in the mass 100 region, and (3) Advanced detector design. Several journal articles and abstracts were published or submitted for publication in the reporting period, and others are currently in preparation. Three graduate students participated in the program, one from the University of Florida and two from the Royal Institute of Technology, Stockholm, Sweden.

Preliminary Engineering Report contaminated groundwater seeps 317/319/ENE area

International Nuclear Information System (INIS)

1996-01-01

When the Resource Conservation and Recovery Act Facility Investigation (RFI) in the 317/319/ENE Area of Argonne National Laboratory-East (ANL-E) was being completed, groundwater was discovered moving to the surface through a series of seeps. The seeps are located approximately 600 ft south of the ANL fence line in Waterfall Glen Forest Preserve. Samples of this water were collected and analyzed for selected parameters. Two of five seeps sampled were found to contain detectable levels of organic contaminants. Three chemical species were identified: chloroform (14-25 μg/L), carbon tetrachloride (56-340 μg/L), and tetrachloroethylene (3-6 μg/L). The other seeps did not contain detectable levels of volatile organic compounds (VOCs). The water issuing from these two contaminated seeps flows into a narrow ravine, where it is visible as a trickle of water flowing through sand and gravel deposits on the floor of the ravine. Approximately 100-ft downstream of the seep area, the contaminated water is no longer visible, having drained back into the soil in the bed of the ravine. Figure 1 shows the location of the 317/319/ENE Area in relation to the ANL-E site and the Waterfall Glen Forest Preserve

The sodium process facility at Argonne National Laboratory - West

International Nuclear Information System (INIS)

Michelbacher, J.A.; Henslee, S.P.; McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

1997-01-01

Argonne National Laboratory - West (ANL-W) has approximately 680,000 liters (180,000 gallons) of raw sodium stored in facilities on site. As mandated by the State of Idaho and the United States Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The SPF was designed to react elemental sodium to sodium carbonate through two-stages involving caustic process and carbonate process steps. The sodium is first reacted to sodium hydroxide in the caustic process step. The caustic process step involves the injection of sodium into a nickel reaction vessel filled with a 50 wt% solution of sodium hydroxide. Water is also injected, controlling the boiling point of the solution. In the carbonate process, the sodium hydroxide is reacted with carbon dioxide to form sodium carbonate. This dry powder, similar in consistency to baking soda, is a waste form acceptable for burial in the State of Idaho as a non-hazardous, radioactive waste. The caustic process was originally designed and built in the 1980s for reacting the 290,000 liters (77,000 gallons) of primary sodium from the Fermi-1 Reactor to sodium hydroxide. The hydroxide was slated to be used to neutralize acid products from the PUREX process at the Hanford site. However, changes in the DOE mission precluded the need for hydroxide and the caustic process was never operated. With the shutdown of the Experimental Breeder Reactor-II (EBR-II), the necessity for a facility to react sodium was identified. In order to comply with Resource Conservation and Recovery Act (RCRA) requirements, the sodium had to be converted into a waste form acceptable for disposal in a Sub-Title D low-level radioactive waste disposal facility. Sodium hydroxide is a RCRA

Underground Test Area Quality Assurance Project Plan Nevada National Security Site, Nevada, Revision 0

Energy Technology Data Exchange (ETDEWEB)

Irene Farnham

2011-05-01

This Quality Assurance Project Plan (QAPP) provides the overall quality assurance (QA) program requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Underground Test Area (UGTA) Sub-Project (hereafter the Sub-Project) activities. The requirements in this QAPP are consistent with DOE Order 414.1C, Quality Assurance (DOE, 2005); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). The QAPP Revision 0 supersedes DOE--341, Underground Test Area Quality Assurance Project Plan, Nevada Test Site, Nevada, Revision 4.

PEROXIDE DESTRUCTION TESTING FOR THE 200 AREA EFFLUENT TREATMENT FACILITY

International Nuclear Information System (INIS)

Halgren, D.L.

2010-01-01

The hydrogen peroxide decomposer columns at the 200 Area Effluent Treatment Facility (ETF) have been taken out of service due to ongoing problems with particulate fines and poor destruction performance from the granular activated carbon (GAC) used in the columns. An alternative search was initiated and led to bench scale testing and then pilot scale testing. Based on the bench scale testing three manganese dioxide based catalysts were evaluated in the peroxide destruction pilot column installed at the 300 Area Treated Effluent Disposal Facility. The ten inch diameter, nine foot tall, clear polyvinyl chloride (PVC) column allowed for the same six foot catalyst bed depth as is in the existing ETF system. The flow rate to the column was controlled to evaluate the performance at the same superficial velocity (gpm/ft 2 ) as the full scale design flow and normal process flow. Each catalyst was evaluated on peroxide destruction performance and particulate fines capacity and carryover. Peroxide destruction was measured by hydrogen peroxide concentration analysis of samples taken before and after the column. The presence of fines in the column headspace and the discharge from carryover was generally assessed by visual observation. All three catalysts met the peroxide destruction criteria by achieving hydrogen peroxide discharge concentrations of less than 0.5 mg/L at the design flow with inlet peroxide concentrations greater than 100 mg/L. The Sud-Chemie T-2525 catalyst was markedly better in the minimization of fines and particle carryover. It is anticipated the T-2525 can be installed as a direct replacement for the GAC in the peroxide decomposer columns. Based on the results of the peroxide method development work the recommendation is to purchase the T-2525 catalyst and initially load one of the ETF decomposer columns for full scale testing.

Argonne Code Center: Benchmark problem book.

Energy Technology Data Exchange (ETDEWEB)

None, None

1977-06-01

This book is an outgrowth of activities of the Computational Benchmark Problems Committee of the Mathematics and Computation Division of the American Nuclear Society. This is the second supplement of the original benchmark book which was first published in February, 1968 and contained computational benchmark problems in four different areas. Supplement No. 1, which was published in December, 1972, contained corrections to the original benchmark book plus additional problems in three new areas. The current supplement. Supplement No. 2, contains problems in eight additional new areas. The objectives of computational benchmark work and the procedures used by the committee in pursuing the objectives are outlined in the original edition of the benchmark book (ANL-7416, February, 1968). The members of the committee who have made contributions to Supplement No. 2 are listed below followed by the contributors to the earlier editions of the benchmark book.

Environmental Assessment -- Test Area North pool stabilization project update

International Nuclear Information System (INIS)

1997-08-01

The purpose of this Environmental Assessment (EA) is to update the ''Test Area North Pool Stabilization Project'' EA (DOE/EA-1050) and finding of no significant impact (FONSI) issued May 6, 1996. This update analyzes the environmental and health impacts of a drying process for the Three Mile Island (TMI) nuclear reactor core debris canisters now stored underwater in a facility on the Idaho National Engineering and Environmental Laboratory (INEEL). A drying process was analyzed in the predecision versions of the EA released in 1995 but that particular process was determined to be ineffective and dropped from the EA/FONSI issued May 6, 1996. A new drying process was subsequently developed and is analyzed in Section 2.1.2 of this document. As did the 1996 EA, this update analyzes the environmental and health impacts of removing various radioactive materials from underwater storage, dewatering these materials, constructing a new interim dry storage facility, and transporting and placing the materials into the new facility. Also, as did the 1996 EA, this EA analyzes the removal, treatment and disposal of water from the pool, and placement of the facility into a safe, standby condition. The entire action would take place within the boundaries of the INEEL. The materials are currently stored underwater in the Test Area North (TAN) building 607 pool, the new interim dry storage facility would be constructed at the Idaho Chemical Processing Plant (ICPP) which is about 25 miles south of TAN

Material control system design: Test Bed Nitrate Storage Area (TBNSA)

International Nuclear Information System (INIS)

Clark, G.A.; Da Roza, R.A.; Dunn, D.R.; Sacks, I.J.; Harrison, W.; Huebel, J.G.; Ross, W.N.; Salisbury, J.D.; Sanborn, R.H.; Weissenberger, S.

1978-05-01

This report provides an example of a hypothetical Special Nuclear Material (SNM) Safeguard Material Control and Accounting (MC and A) System which will be used as a subject for the demonstration of the Lawrence Livermore Laboratory MC and A System Evaluation Methodology in January 1978. This methodology is to become a tool in the NRC evaluation of license applicant submittals for Nuclear Fuel Cycle facilities. The starting point for this test bed design was the Allied-General Nuclear Services--Barnwell Nuclear Fuel Plant Reprocessing plant as described in the Final Safety Analysis Report (FSAR), of August 1975. The test bed design effort was limited to providing an SNM safeguard system for the plutonium nitrate storage area of this facility

Test strip at the Musters lake area, Chubut province (Argentina)

International Nuclear Information System (INIS)

Lopez, Luis E.

1998-01-01

A local test strip to determine both the system sensitivities and height attenuation coefficients was defined at the Musters Lake area, for its use in airborne spectrometric surveys in the South Patagonia region. The selected calibration range presents both low and uniform radioelement concentration. The mean spectrometer values obtained at ground level were 1.8 % K, 1.6 ppm eU and 7.3 ppm eTh while the variation coefficients were 7.5 %, 27.0 %, and 10.2 %, respectively. These values as well as range dimensions, moisture condition, easy access, easy navigation for aircraft, proximity to a fresh water body and with no flight restrictions are consistent with the international recommendations for setting up a test range. (author)

Test strip at the Musters Lake area, Chubut province (Argentina)

International Nuclear Information System (INIS)

Lopez, Luis E.

1998-01-01

A local test strip to determine both the system sensitivities and height attenuation coefficients was defined at the Musters Lake area, for its use in airborne spectrometric surveys in the South Patagonia region. The selected calibration range presents both low and uniform radioelement concentrations. The mean spectrometer values obtained at ground level were 1.8 % K, 1.6 ppm eU and 7.3 ppm eTh while the variation coefficients were 7.5 %, 27.0 %, and 10.2 %, respectively. These values as well as range dimensions, moisture condition, easy access, easy navigation for aircraft, proximity to a fresh water body and with no flight restrictions are consistent with the international recommendations for setting up a test range. (author)

HISTORICAL AMERICAN ENGINEERING RECORD - IDAHO NATIONAL ENGINEERING AND ENVIRONMENTAL LABORATORY, TEST AREA NORTH, HAER NO. ID-33-E

Energy Technology Data Exchange (ETDEWEB)

Susan Stacy; Hollie K. Gilbert

2005-02-01

Test Area North (TAN) was a site of the Aircraft Nuclear Propulsion (ANP) Project of the U.S. Air Force and the Atomic Energy Commission. Its Cold War mission was to develop a turbojet bomber propelled by nuclear power. The project was part of an arms race. Test activities took place in five areas at TAN. The Assembly & Maintenance area was a shop and hot cell complex. Nuclear tests ran at the Initial Engine Test area. Low-power test reactors operated at a third cluster. The fourth area was for Administration. A Flight Engine Test facility (hangar) was built to house the anticipated nuclear-powered aircraft. Experiments between 1955-1961 proved that a nuclear reactor could power a jet engine, but President John F. Kennedy canceled the project in March 1961. ANP facilities were adapted for new reactor projects, the most important of which were Loss of Fluid Tests (LOFT), part of an international safety program for commercial power reactors. Other projects included NASA's Systems for Nuclear Auxiliary Power and storage of Three Mile Island meltdown debris. National missions for TAN in reactor research and safety research have expired; demolition of historic TAN buildings is underway.

HISTORICAL AMERICAN ENGINEERING RECORD - IDAHO NATIONAL ENGINEERING AND ENVIRONMENTAL LABORATORY, TEST AREA NORTH, HAER NO. ID-33-E

International Nuclear Information System (INIS)

Susan Stacy; Hollie K. Gilbert

2005-01-01

Test Area North (TAN) was a site of the Aircraft Nuclear Propulsion (ANP) Project of the U.S. Air Force and the Atomic Energy Commission. Its Cold War mission was to develop a turbojet bomber propelled by nuclear power. The project was part of an arms race. Test activities took place in five areas at TAN. The Assembly and Maintenance area was a shop and hot cell complex. Nuclear tests ran at the Initial Engine Test area. Low-power test reactors operated at a third cluster. The fourth area was for Administration. A Flight Engine Test facility (hangar) was built to house the anticipated nuclear-powered aircraft. Experiments between 1955-1961 proved that a nuclear reactor could power a jet engine, but President John F. Kennedy canceled the project in March 1961. ANP facilities were adapted for new reactor projects, the most important of which were Loss of Fluid Tests (LOFT), part of an international safety program for commercial power reactors. Other projects included NASA's Systems for Nuclear Auxiliary Power and storage of Three Mile Island meltdown debris. National missions for TAN in reactor research and safety research have expired; demolition of historic TAN buildings is underway

Mock Target Window OTR and IR Design and Testing

Energy Technology Data Exchange (ETDEWEB)

Wass, Alexander Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-09-19

In order to fully verify temperature measurements made on the target window using infrared (IR) optical non-contact methods, actual comparative measurements are made with a real beam distribution as the heat source using Argonne National Laboratory’s (ANL) 35 MeV electron accelerator. Using Monte Carlo N-Particle (MCNP) simulations and thermal Finite Element Analysis (FEA), a cooled mock target window with thermocouple implants is designed to be used in such a test to achieve window temperatures up to 700°C. An uncoated and blackcoated mock window is designed to enhance the IR temperature measurements and verify optical transmitted radiation (OTR) imagery. This allows us to fully verify and characterize our temperature accuracy with our current IR camera method and any future method we may wish to explore using actual production conditions. This test also provides us with valuable conclusions/concerns regarding the calibration method we developed using our IR test stand at TA-53 in MPF-14.

Closure Report for Corrective Action Unit 425: Area 9 Main Lake Construction Debris Disposal Area, Tonopah Test Range, Nevada

Energy Technology Data Exchange (ETDEWEB)

K. B. Campbell

2003-03-01

Corrective Action Unit (CAU) 425 is located on the Tonopah Test Range, approximately 386 kilometers (240 miles) northwest of Las Vegas, Nevada. CAU 425 is listed in the Federal Facility Agreement and Consent Order (FFACO, 1996) and is comprised of one Corrective Action Site (CAS). CAS 09-08-001-TA09 consisted of a large pile of concrete rubble from the original Hard Target and construction debris associated with the Tornado Rocket Sled Tests. CAU 425 was closed in accordance with the FFACO and the Nevada Division of Environmental Protection-approved Streamlined Approach for Environmental Restoration Plan for CAU 425: Area 9 Main Lake Construction Debris Disposal Area, Tonopah Test Range, Nevada (U.S. Department of Energy, Nevada Operations Office, 2002). CAU 425 was closed by implementing the following corrective actions: The approved corrective action for this unit was clean closure. Closure activities included: (1) Removal of all the debris from the site. (2) Weighing each load of debris leaving the job site. (3) Transporting the debris to the U.S. Air Force Construction Landfill for disposal. (4) Placing the radioactive material in a U.S. Department of Transportation approved container for proper transport and disposal. (5) Transporting the radioactive material to the Nevada Test Site for disposal. (6) Regrading the job site to its approximate original contours/elevation.

Simulating the effects of plasma disruption with a 1 MA current pulse in a coaxial test fixture

International Nuclear Information System (INIS)

Praeg, W.F.

1985-01-01

A test fixture for simulating plasma disruptions, comprising two coaxial cylinders, has been designed for use with Argonne's electromagnetic test facility FELIX. A pulsed power supply drives a half cycle sine wave current of 10 0 A through the test fixture generating fields of -1 . The coaxial structure is 140 cm long, has an outer cylinder with an OD of 78 cm and an inner cylinder with an OD of 8.3 cm. It is surrounded by the FELIX solenoid field of 1 T. This proposed upgrade of the FELIX facility should be useful for testing the effect of plasma disruption on First Wall-Blanket-Shield (FWBS) structures; a future upgrade of the solenoid field to 4 T will allow to simulate reactor conditions even better

Simulating the effects of plasma disruption with A 1 MA current pulse in a coaxial test fixture

International Nuclear Information System (INIS)

Praeg, W.F.

1985-01-01

A test fixture for simulating plasma disruptions, comprising two coaxial cylinders, has been designed for use with Argonne's electromagnetic test facility FELIX. A pulsed power supply drives a half cycle sine wave current of 10 0 A through the test fixture generating fields of -1 . The coaxial structure is 140 cm long, has an outer cylinder with an OD of 78 cm and an inner cylinder with an OD of 8.3 cm. It is surrounded by the FELIX solenoid field of 1 T. This proposed upgrade of the FELIX facility should be useful for testing the effect of plasma disruption on First Wall-Blanket-Shield (FWBS) structures; a future upgrade of the solenoid field to 4 T will allow to simulate reactor conditions even better

Nevada Test Site, 2006 Waste Management Monitoring Report, Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

David B. Hudson

2007-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2006 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports (U.S. Department of Energy, 2006; Warren and Grossman, 2007; National Security Technologies, LLC, 2007). Direct radiation monitoring data indicate that exposure levels around the RWMSs are at or below background levels. Air monitoring data at the Area 3 and Area 5 RWMSs indicate that tritium concentrations are slightly above background levels. There is no detectable man-made radioactivity by gamma spectroscopy, and concentrations of americium and plutonium are only slightly above detection limits at the Area 3 RWMS. Measurements at the Area 5 RWMS show that radon flux from waste covers is no higher than natural radon flux from undisturbed soil in Area 5. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by facility operations. Precipitation during 2006 totaled 98.6 millimeters (mm) (3.9 inches [in.]) at the Area 3 RWMS and 80.7 mm (3.2 in.) at the Area 5 RWMS. Soil-gas tritium monitoring continues to show slow subsurface migration consistent with previous results. Moisture from precipitation at Area 5 remains at the bottom of the bare-soil weighing lysimeter, but this same moisture has been removed from the vegetated weighing lysimeter by evapotranspiration. Vadose zone data from the operational waste pit covers show that evaporation continues to slowly remove soil moisture that came from the heavy precipitation in the fall of 2004 and the spring of

A facility for the test of large area muon chambers at high rates

CERN Document Server

Agosteo, S; Belli, G; Bonifas, A; Carabelli, V; Gatignon, L; Hessey, N P; Maggi, M; Peigneux, J P; Reithler, H; Silari, Marco; Vitulo, P; Wegner, M

2000-01-01

Operation of large area muon detectors at the future Large Hadron Collider (LHC) will be characterized by large sustained hit rates over the whole area, reaching the range of kHz/\\scm. We describe a dedicated test zone built at CERN to test the performance and the aging of the muon chambers currently under development. A radioactive source delivers photons causing the sustained rate of random hits, while a narrow beam of high energy muons is used to directly calibrate the detector performance. A system of remotely controlled lead filters serves to vary the rate of photons over four orders of magnitude, to allow the study of performance as a function of rate.

A facility for the test of large-area muon chambers at high rates

Energy Technology Data Exchange (ETDEWEB)

Agosteo, S.; Altieri, S.; Belli, G.; Bonifas, A.; Carabelli, V.; Gatignon, L.; Hessey, N.; Maggi, M.; Peigneux, J.-P.; Reithler, H. E-mail: hans.reithler@cern.ch; Silari, M.; Vitulo, P.; Wegner, M

2000-09-21

Operation of large-area muon detectors at the future Large Hadron Collider (LHC) will be characterized by large sustained hit rates over the whole area, reaching the range of kHz cm{sup -2}. We describe a dedicated test zone built at CERN to test the performance and the aging of the muon chambers currently under development. A radioactive source delivers photons causing the sustained rate of random hits, while a narrow beam of high-energy muons is used to directly calibrate the detector performance. A system of remotely controlled lead filters serves to vary the rate of photons over four orders of magnitude, to allow the study of performance as a function of rate. (authors)

Nevada Test Site 2001 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

Y. E. Townsend

2002-06-01

Environmental monitoring data, subsidence monitoring data, and meteorology monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS) (refer to Figure 1). These monitoring data include radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota data. Although some of these media (radiation exposure, air, and groundwater) are reported in detail in other Bechtel Nevada (BN) reports (Annual Site Environmental Report [ASER], the National Emissions Standard for Hazardous Air Pollutants [NESHAP] report, and the Annual Groundwater Monitoring Report), they are also summarized in this report to provide an overall evaluation of RWMS performance and environmental compliance. Direct radiation monitoring data indicate that exposure at and around the RWMSs is not above background levels. Air monitoring data indicate that tritium concentrations are slightly above background levels. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS has not been affected by the facility. Meteorology data indicate that 2001 was an average rainfall year: rainfall totaled 150 mm (5.9 in) at the Area 3 RWMS and 120 mm (4.7 in) at the Area 5 RWMS. Vadose zone monitoring data indicate that 2001 rainfall infiltrated less than one meter (3 ft) before being returned to the atmosphere by evaporation. Soil-gas tritium monitoring data indicate slow subsurface migration, and tritium concentrations in biota were lower than in previous years. All 2001 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing within expectations of the model and parameter assumptions for the facility performance assessments

Characterization Report for the 92-Acre Area of the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Bechtel Nevada; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2006-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office manages two low-level Radioactive Waste Management Sites at the Nevada Test Site. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. This report summarizes characterization and monitoring work pertinent to the 92-Acre Area in the southeast part of the Area 5 Radioactive Waste Management Sites. The decades of characterization and assessment work at the Area 5 RWMS indicate that the access controls, waste operation practices, site design, final cover design, site setting, and arid natural environment contribute to a containment system that meets regulatory requirements and performance objectives for the short- and long-term protection of the environment and public. The available characterization and Performance Assessment information is adequate to support design of the final cover and development of closure plans. No further characterization is warranted to demonstrate regulatory compliance. U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is proceeding with the development of closure plans for the six closure units of the 92-Acre Area

Characterization Report for the 92-Acre Area of the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

Bechtel Nevada; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2006-06-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office manages two low-level Radioactive Waste Management Sites at the Nevada Test Site. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. This report summarizes characterization and monitoring work pertinent to the 92-Acre Area in the southeast part of the Area 5 Radioactive Waste Management Sites. The decades of characterization and assessment work at the Area 5 RWMS indicate that the access controls, waste operation practices, site design, final cover design, site setting, and arid natural environment contribute to a containment system that meets regulatory requirements and performance objectives for the short- and long-term protection of the environment and public. The available characterization and Performance Assessment information is adequate to support design of the final cover and development of closure plans. No further characterization is warranted to demonstrate regulatory compliance. U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is proceeding with the development of closure plans for the six closure units of the 92-Acre Area.

Corrective action investigation plan for Central Nevada Test Area CAU No. 417

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-01-01

This Corrective Action Investigation Plan (CAIP) is part of a US Department of Energy (DOE)-funded environmental investigation of the Central Nevada Test Area (CNTA). The CNTA is located in Hot Creek Valley in Nye County, Nevada, adjacent to US Highway 6, about 15 kilometers (10 miles) northeast of Warm Springs. The CNTA was the site of Project Faultless, a nuclear device detonated in the subsurface by the US Atomic Energy Commission (AEC) in January 1968. The purpose of this test was to gauge the seismic effects of relatively large, high-yield detonations completed outside of the Nevada Test Site (NTS). The test was also used to determine the suitability of the site for future large detonations. The yield of the Faultless test was between 200 kilotons and 1 megaton (DOE, 1994c).

DOE technology information management system database study report

Energy Technology Data Exchange (ETDEWEB)

Widing, M.A.; Blodgett, D.W.; Braun, M.D.; Jusko, M.J.; Keisler, J.M.; Love, R.J.; Robinson, G.L. [Argonne National Lab., IL (United States). Decision and Information Sciences Div.

1994-11-01

To support the missions of the US Department of Energy (DOE) Special Technologies Program, Argonne National Laboratory is defining the requirements for an automated software system that will search electronic databases on technology. This report examines the work done and results to date. Argonne studied existing commercial and government sources of technology databases in five general areas: on-line services, patent database sources, government sources, aerospace technology sources, and general technology sources. First, it conducted a preliminary investigation of these sources to obtain information on the content, cost, frequency of updates, and other aspects of their databases. The Laboratory then performed detailed examinations of at least one source in each area. On this basis, Argonne recommended which databases should be incorporated in DOE`s Technology Information Management System.

Nevada Test Site fallout in the area of Enterprise, Utah

International Nuclear Information System (INIS)

Krey, P.W.; Hardy, E.P.; Heit, M.

1980-04-01

The analysis of a sediment core from the Enterprise reservoir in southwestern Utah has provided a record of fallout in the area dating to 1945. Assming that all the 137 Cs fallout that occurred at Enterprise reservoir between 1951 and 1957 came exclusively from the Nevada tests, an upper limit of the integrated deposit from this source is 18 mCi/km 2 of 137 Cs decay corrected to 1979 out of a total of 101 measured in 1979. The maximum infinity dose from the external radiation caused by this Nevada Test Site fallout is estimated to be 1700 mrad. This maximum dose is only a factor of two higher than the cumulative estimated dose in Enterprise derived from the radiological surveys conducted after each test. This indicates that the region around Enterprise reservoir did not experience an intrusion of fallout from NTS greatly in excess of what had been deduced from the post-shot external radiation surveys

Cryogenics for the MuCool Test Area (MTA)

International Nuclear Information System (INIS)

Darve, Christine; Norris, Barry; Pei, Liujin

2006-01-01

MuCool Test Area (MTA) is a complex of buildings at Fermi National Accelerator Laboratory, which are dedicated to operate components of a cooling cell to be used for Muon Collider and Neutrino Factory R and D. The long-term goal of this facility is to test ionization cooling principles by operating a 25-liter liquid hydrogen (LH2) absorber embedded in a 5 Tesla superconducting solenoid magnet. The MTA solenoid magnet will be used with RF cavities exposed to a high intensity beam. Cryogens used at the MTA include LHe, LN2 and LH2. The latter dictates stringent system design for hazardous locations. The cryogenic plant is a modified Tevatron refrigerator based on the Claude cycle. The implementation of an in-house refrigerator system and two 300 kilowatt screw compressors is under development. The helium refrigeration capacity is 500 W at 14 K. In addition the MTA solenoid magnet will be batch-filled with LHe every 2 days using the same cryo-plant. This paper reviews cryogenic systems used to support the Muon Collider and Neutrino Factory R and D programs and emphasizes the feasibility of handling cryogenic equipment at MTA in a safe manner

An investigation into the knowledge and attitudes towards radon testing among residents in a high radon area

International Nuclear Information System (INIS)

Clifford, Susan; Menezes, Gerard; Hevey, David

2012-01-01

The aim of this study was to investigate the knowledge and attitudes of residents in the Castleisland area to radon. Castleisland in Co. Kerry was described as a high radon area following the discovery of a house in the area with radon levels 245 times that of the national reference level. Residents in this area were then asked to measure their homes for radon in the Castleisland radon survey. The uptake of this measurement was 17%. In order to investigate this response rate further, a questionnaire was designed and distributed to residents in the Castleisland area. This questionnaire measured the testing history of the participants, the reasons for testing/not testing, the factors important to them when considering having their home tested, radon knowledge and finally intentions to measure their home for radon. It was found that the main reason people do not test their home for radon is that they believe their home does not have a problem. Optimistic bias was thought to play a role here. The subjective norm component of the theory of planned behaviour was found to have a significant independent contribution in the variation in intentions to measure one’s home for radon and this in turn could be targeted to increase uptake of radon measurement in the future. (note)

Yucca Mountain project canister material corrosion studies as applied to the electrometallurgical treatment metallic waste form

International Nuclear Information System (INIS)

Keiser, D.D.

1996-11-01

Yucca Mountain, Nevada is currently being evaluated as a potential site for a geologic repository. As part of the repository assessment activities, candidate materials are being tested for possible use as construction materials for waste package containers. A large portion of this testing effort is focused on determining the long range corrosion properties, in a Yucca Mountain environment, for those materials being considered. Along similar lines, Argonne National Laboratory is testing a metallic alloy waste form that also is scheduled for disposal in a geologic repository, like Yucca Mountain. Due to the fact that Argonne's waste form will require performance testing for an environment similar to what Yucca Mountain canister materials will require, this report was constructed to focus on the types of tests that have been conducted on candidate Yucca Mountain canister materials along with some of the results from these tests. Additionally, this report will discuss testing of Argonne's metal waste form in light of the Yucca Mountain activities

Microbiological analyses of samples from the H-Area injection well test site

International Nuclear Information System (INIS)

Wilde, E.W.; Franck, M.M.

1997-01-01

Microbial populations in well water from monitoring wells at the test site were one to three orders of magnitude higher than well water from the Cretaceous aquifer (used as dilution water for the tests) or from a control well adjacent to the test site facility. Coupons samples placed in monitoring and control wells demonstrated progressive adhesion by microbes to materials used in well construction. Samples of material scraped from test well components during abandonment of the test site project revealed the presence of a variety of attached microbes including iron bacteria. Although the injection wells at the actual remediation facility for the F- and H-Area seepage basins remediation project are expected to be subjected to somewhat different conditions (e.g. considerably lower iron concentrations) than was the case at the test site, the potential for microbiologically mediated clogging and fouling within the process should be considered. A sampling program that includes microbiological testing is highly recommended

Leaching characteristics of the metal waste form from the electrometallurgical treatment process: Product consistency testing

International Nuclear Information System (INIS)

Johnson, S. G.; Keiser, D. D.; Frank, S. M.; DiSanto, T.; Noy, M.

1999-01-01

Argonne National Laboratory is developing an electrometallurgical treatment for spent fuel from the experimental breeder reactor II. A product of this treatment process is a metal waste form that incorporates the stainless steel cladding hulls, zirconium from the fuel and the fission products that are noble to the process, i.e., Tc, Ru, Nb, Pd, Rh, Ag. The nominal composition of this waste form is stainless steel/15 wt% zirconium/1--4 wt% noble metal fission products/1--2 wt % U. Leaching results are presented from several tests and sample types: (1) 2 week monolithic immersion tests on actual metal waste forms produced from irradiated cladding hulls, (2) long term (>2 years) pulsed flow tests on samples containing technetium and uranium and (3) crushed sample immersion tests on cold simulated metal waste form samples. The test results will be compared and their relevance for waste form product consistency testing discussed

Initial tests of the dual-sweep streak camera system planned for APS particle-beam diagnostics

International Nuclear Information System (INIS)

Lumpkin, A.; Yang, B.; Gai, W.; Cieslik, W.

1995-01-01

Initial tests of a dual-sweep streak system planned for use on the Advanced Photon Source (APS) have been performed using assets of the Argonne Wakefield Accelerator (AWA) facility. The short light pulses from the photoelectric injector drive laser in both the visible (λ=496 nm, Δt∼1.5 ps (FWHM)), and the ultraviolet (λ=248 nm, Δt∼5 ps (FWHM)) were used. Both a UV-visible S20 photocathode streak tube and a UV-to-x-ray Au photocathode streak tube were tested. Calibration data with an etalon were also obtained. A sample of dual-sweep streak data using optical synchrotron radiation on the APS injector synchrotron is also presented

Nevada Test Site 2000 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

Yvonne Townsend

2001-01-01

Environmental monitoring data, subsidence monitoring data, and meteorology monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS) (refer to Figure 1). These monitoring data include radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota data. Although some of these media (radiation exposure, air, and groundwater) are reported in detail in other Bechtel Nevada reports (Annual Site Environmental Report [ASER], the National Emissions Standard for Hazardous Air Pollutants [NESHAP] report, and the Annual Groundwater Monitoring Report), they are also summarized in this report to provide an overall evaluation of RWMS performance and environmental compliance. Direct radiation monitoring data indicate that exposure at and around the RWMSs is not above background levels. Air monitoring data indicate that tritium concentrations are slightly above background levels, whereas radon concentrations are not above background levels. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS has not been affected by the facility. Meteorology data indicate that 2000 was an average rainfall year: rainfall totaled 167 mm (6.6 in) at the Area 3 RWMS (annual average is 156 mm [6.5 in]) and 123 mm (4.8 in) at the Area 5 RWMS (annual average is 127 mm [5.0 in]). Vadose zone monitoring data indicate that 2000 rainfall infiltrated less than one meter (3 ft) before being returned to the atmosphere by evaporation. Soil-gas tritium monitoring data indicate slow subsurface migration, and tritium concentrations in biota were lower than in previous years. All 2000 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing well at isolating buried waste

Product consistency leach tests of Savannah River Site radioactive waste glasses

International Nuclear Information System (INIS)

Bibler, N.E.; Bates, J.K.

1989-01-01

The Product Consistency Test (PCT) is a glass leach test that was developed at the Savannah River Site (SRS) to routinely confirm the durability of nuclear waste glasses that will be produced in the Defense Waste Processing Facility. The PCT is a 7 day, crushed glass leach test in deionized water at 90 degree C. Final leachates are filtered and acidified prior to analysis. To demonstrate the reproducibility of the PCT when performed remotely, SRS and Argonne National Laboratory have performed the PCT on samples of two radioactive glasses. The tests were also performed to compare the releases of the radionuclides with the major nonradioactive glass components and to determine if radiation from the glass was affecting the results of the PCT. The test was performed in triplicate at each laboratory. For the major soluble elements, B, Li, Na, and Si, in the glass, each investigator obtained relative precisions in the range 2--5% in the triplicate tests. This range indicates good precision for the PCT when performed remotely with master slave manipulators in a shielded cell environment

33 CFR 334.1440 - Pacific Ocean at Kwajalein Atoll, Marshall Islands; missile testing area.

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 3 2010-07-01 2010-07-01 false Pacific Ocean at Kwajalein Atoll, Marshall Islands; missile testing area. 334.1440 Section 334.1440 Navigation and Navigable Waters CORPS OF ENGINEERS, DEPARTMENT OF THE ARMY, DEPARTMENT OF DEFENSE DANGER ZONE AND RESTRICTED AREA REGULATIONS § 334.1440 Pacific Ocean at Kwajalein...

A Small Area In-Situ MEMS Test Structure to Accurately Measure Fracture Strength by Electrostatic Probing

Energy Technology Data Exchange (ETDEWEB)

Bitsie, Fernando; Jensen, Brian D.; de Boer, Maarten

1999-07-15

We have designed, fabricated, tested and modeled a first generation small area test structure for MEMS fracture studies by electrostatic rather than mechanical probing. Because of its small area, this device has potential applications as a lot monitor of strength or fatigue of the MEMS structural material. By matching deflection versus applied voltage data to a 3-D model of the test structure, we develop high confidence that the local stresses achieved in the gage section are greater than 1 GPa. Brittle failure of the polycrystalline silicon was observed.

Flood Assessment Area 3 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

NSTec Environmental Management

2007-01-01

A flood assessment was conducted at the Area 3 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) in Nye County, Nevada (Figure 1-1). The study area encompasses the watershed of Yucca Flat, a closed basin approximately 780 square kilometers (km2) (300 square miles) in size. The focus of this effort was on a drainage area of approximately 94 km2 (36 mi2), determined from review of topographic maps and aerial photographs to be the only part of the Yucca Flat watershed that could directly impact the Area 3 RWMS. This smaller area encompasses portions of the Halfpint Range, including Paiute Ridge, Jangle Ridge, Carbonate Ridge, Slanted Buttes, Cockeyed Ridge, and Banded Mountain. The Area 3 RWMS is located on coalescing alluvial fans emanating from this drainage area

Hydrologic Resources Management Program and Underground Test Area Project FY2005 Progress Report

International Nuclear Information System (INIS)

Eaton, G F; Genetti, V; Hu, Q; Hudson, G B; Kersting, A B; Lindvall, R E; Moran, J E; Nimz, G J; Ramon, E C; Rose, T P; Shuller, L; Williams, R W; Zavarin, M; Zhao, P

2007-01-01

This report describes FY 2005 technical studies conducted by the Chemical Biology and Nuclear Science Division (CBND) at Lawrence Livermore National Laboratory (LLNL) in support of the Hydrologic Resources Management Program (HRMP) and the Underground Test Area Project (UGTA). These programs are administered by the U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office (NNSA/NSO) through the Defense Programs and Environmental Restoration Divisions, respectively. HRMP-sponsored work is directed toward the responsible management of the natural resources at the Nevada Test Site (NTS), enabling its continued use as a staging area for strategic operations in support of national security. UGTA-funded work emphasizes the development of an integrated set of groundwater flow and contaminant transport models to predict the extent of radionuclide migration from underground nuclear testing areas at the NTS. The report is organized on a topical basis and contains five chapters that highlight technical work products produced by CBND. However, it is important to recognize that most of this work involves collaborative partnerships with the other HRMP and UGTA contract organizations. These groups include the Energy and Environment Directorate at LLNL (LLNL-E and E), Los Alamos National Laboratory (LANL), the Desert Research Institute (DRI), the U.S. Geological Survey (USGS), Stoller-Navarro Joint Venture (SNJV), and Bechtel Nevada (BN)

Closure Strategy Nevada Test Site Area 5 Radioactive Waste Management Site

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2007-03-01

This paper presents an overview of the strategy for closure of part of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada (Figure 1). The Area 5 RWMS is in the northern part of Frenchman Flat, approximately 14 miles north of Mercury. The Area 5 RWMS encompasses 732 acres subdivided into quadrants, and is bounded by a 1,000-foot (ft)-wide buffer zone. The northwest and southwest quadrants have not been developed. The northeast and southeast quadrants have been used for disposal of unclassified low-level radioactive waste (LLW) and indefinite storage of classified materials. This paper focuses on closure of the 38 waste disposal and classified material storage units within the southeast quadrant of the Area 5 RWMS, called the ''92-Acre Area''. The U.S Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is currently planning to close the 92-Acre Area by 2011. Closure planning for this site must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. For ease of discussion, the 92-Acre Area has been subdivided into six closure units defined by waste type, location, and similarity in regulatory requirements. Each of the closure units contains one or more waste disposal units; waste disposal units are also called waste disposal cells. The paper provides a brief background of the Area 5 RWMS, identifies key closure issues for the 92-Acre Area, recommends actions to address the issues, and provides the National Security Technologies, LLC (NSTec), schedule for closure.

The investigation on hereditary disease and congenital malformation in the surrounding area of the nuclear test site in Xinjiang

International Nuclear Information System (INIS)

Zou Wenliang; Zhang Jujing

1989-01-01

The investigation on hereditary disease and congenital malformation, on the children below eleven years old and living in the surrounding area of the nuclear test site and control area is reported. The total prevalence rate of the ninteen kinds of hereditary disease and congenital malformation in both areas are 7.12%0 and 7.28%0, respectively. The prevalence rate of congenital foolishness in investigation area is 0.64%0; while in control area, it is 0.54%0. There is no significant difference between the two areas. However, it is found that the prevalence rate of harelip in investigation area is higher than in control area, whereas the prevalence rate of congenital heart disease in control area is higher than in investigation area. As for the rests there is no significant difference. There is no significant difference between the two areas. It is concluded that nuclear tests in China did not cause hereditary disease and congenital malformation for the children who live in surrounding area, of the nuclear test site

Accelerated Leach Testing of GLASS: ALTGLASS Version 3.0

Energy Technology Data Exchange (ETDEWEB)

Trivelpiece, Cory L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jantzen, Carol M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Crawford, Charles L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-12-31

The Accelerated Leach Testing of GLASS (ALTGLASS) database is a collection of data from short- and long-term product consistency tests (PCT, ASTM C1285 A and B) on high level waste (HLW) as well as low activity waste (LAW) glasses. The database provides both U.S. and international researchers with an archive of experimental data for the purpose of studying, modeling, or validating existing models of nuclear waste glass corrosion. The ALTGLASS database is maintained and updated by researchers at the Savannah River National Laboratory (SRNL). This newest version, ALTGLASS Version 3.0, has been updated with an additional 503 rows of data representing PCT results from corrosion experiments conducted in the United States by the Savannah River National Laboratory, Pacific Northwest National Laboratory, Argonne National Laboratory, and the Vitreous State Laboratory (SRNL, PNNL, ANL, VSL, respectively) as well as the National Nuclear Laboratory (NNL) in the United Kingdom.

Accelerated Leach Testing of GLASS: ALTGLASS Version 3.0

International Nuclear Information System (INIS)

Trivelpiece, Cory L.; Jantzen, Carol M.; Crawford, Charles L.

2016-01-01

The Accelerated Leach Testing of GLASS (ALTGLASS) database is a collection of data from short- and long-term product consistency tests (PCT, ASTM C1285 A and B) on high level waste (HLW) as well as low activity waste (LAW) glasses. The database provides both U.S. and international researchers with an archive of experimental data for the purpose of studying, modeling, or validating existing models of nuclear waste glass corrosion. The ALTGLASS database is maintained and updated by researchers at the Savannah River National Laboratory (SRNL). This newest version, ALTGLASS Version 3.0, has been updated with an additional 503 rows of data representing PCT results from corrosion experiments conducted in the United States by the Savannah River National Laboratory, Pacific Northwest National Laboratory, Argonne National Laboratory, and the Vitreous State Laboratory (SRNL, PNNL, ANL, VSL, respectively) as well as the National Nuclear Laboratory (NNL) in the United Kingdom.

Energy Systems Test Area (ESTA) Battery Test Operations User Test Planning Guide

Science.gov (United States)

Salinas, Michael

2012-01-01

Test process, milestones and inputs are unknowns to first-time users of the ESTA Battery Test Operations. The User Test Planning Guide aids in establishing expectations for both NASA and non-NASA facility customers. The potential audience for this guide includes both internal and commercial spaceflight hardware/software developers. It is intended to assist their test engineering personnel in test planning and execution. Material covered includes a roadmap of the test process, roles and responsibilities of facility and user, major milestones, facility capabilities, and inputs required by the facility. Samples of deliverables, test article interfaces, and inputs necessary to define test scope, cost, and schedule are included as an appendix to the guide.

Testing and evaluation of large-area heliostats for solar thermal applications

Energy Technology Data Exchange (ETDEWEB)

Strachan, J.W.; Houser, R.M.

1993-02-01

Two heliostats representing the state-of-the-art in glass-metal designs for central receiver (and photovoltaic tracking) applications were tested and evaluated at the National Solar Thermal Test Facility in Albuquerque, New Mexico from 1986 to 1992. These heliostats have collection areas of 148 and 200 m{sup 2} and represent low-cost designs for heliostats that employ glass-metal mirrors. The evaluation encompassed the performance and operational characteristics of the heliostats, and examined heliostat beam quality, the effect of elevated winds on beam quality, heliostat drives and controls, mirror module reflectance and durability, and the overall operational and maintenance characteristics of the two heliostats. A comprehensive presentation of the results of these and other tests is presented. The results are prefaced by a review of the development (in the United States) of heliostat technology.

Particulate Emissions Control using Advanced Filter Systems: Final Report for Argonne National Laboratory, Corning Inc. and Hyundai Motor Company CRADA Project

Energy Technology Data Exchange (ETDEWEB)

Seong, Hee Je [Argonne National Lab. (ANL), Argonne, IL (United States); Choi, Seungmok [Argonne National Lab. (ANL), Argonne, IL (United States)

2015-10-09

This is a 3-way CRADA project working together with Corning, Inc. and Hyundai Motor Co. (HMC). The project is to understand particulate emissions from gasoline direct-injection engines (GDI) and their physico-chemical properties. In addition, this project focuses on providing fundamental information about filtration and regeneration mechanisms occurring in gasoline particulate filter (GPF) systems. For the work, Corning provides most advanced filter substrates for GPF applications and HMC provides three-way catalyst (TWC) coating services of these filter by way of a catalyst coating company. Then, Argonne National Laboratory characterizes fundamental behaviors of filtration and regeneration processes as well as evaluated TWC functionality for the coated filters. To examine aging impacts on TWC and GPF performance, the research team evaluates gaseous and particulate emissions as well as back-pressure increase with ash loading by using an engine-oil injection system to accelerate ash loading in TWC-coated GPFs.

Lithology and Stratigraphy of Holes Drilled in LANL-Use Areas of the Nevada Test Site

Energy Technology Data Exchange (ETDEWEB)

Lance B. Prothro; Sigmund L. Drellack, Jr.; Brian M. Allen

1999-07-01

Geologic data for ten holes drilled in areas used by Los Alamos National Laboratory at the Nevada Test Site are presented in this report. The holes include emplacement holes, instrumentation holes, and Underground Test Area wells drilled during calendar years 1991 through 1995. For each hole a stratigraphic log, a detailed lithologic log, and one or two geologic cross sections are presented, along with a supplemental data sheet containing information about the drilling operations, geology, or references. For three of the holes, graphic data summary sheets with geologic and geophysical data are provided as plates.

Split ring resonator for the Argonne superconducting heavy ion booster

International Nuclear Information System (INIS)

Shepard, K.W.; Scheibelhut, C.H.; Benaroya, R.; Bollinger, L.M.

1977-01-01

A split-ring resonator for use in the ANL superconducting heavy-ion linac was constructed and is being tested. The electromagnetic characteristics of the 98-MHz device are the same as the unit described earlier, but the housing is formed of a new material consisting of niobium sheet explosively bonded to copper. The niobium provides the superconducting path and the copper conducts heat to a small area cooled by liquid helium. This arrangement greatly simplified the cryogenic system. Fabrication of the housing was relatively simple, with the result that costs have been reduced substantially. The mechanical stability of the resonator and the performance of the demountable superconducting joints are significantly better than for the earlier unit

Split ring resonator for the Argonne superconducting heavy ion booster

Energy Technology Data Exchange (ETDEWEB)

Shepard, K.W.; Scheibelhut, C.H.; Benaroya, R.; Bollinger, L.M.

1977-01-01

A split-ring resonator for use in the ANL superconducting heavy-ion linac was constructed and is being tested. The electromagnetic characteristics of the 98-MHz device are the same as the unit described earlier, but the housing is formed of a new material consisting of niobium sheet explosively bonded to copper. The niobium provides the superconducting path and the copper conducts heat to a small area cooled by liquid helium. This arrangement greatly simplified the cryogenic system. Fabrication of the housing was relatively simple, with the result that costs have been reduced substantially. The mechanical stability of the resonator and the performance of the demountable superconducting joints are significantly better than for the earlier unit.

Testing and development of electric vehicle batteries for EPRI Electric Transportation Program

Science.gov (United States)

1985-11-01

Argonne National Laboratory conducted an electric-vehicle battery testing and development program for the Electric Power Research Institute. As part of this program, eighteen battery modules previously developed by Johnson Controls, Inc. were tested. This type of battery (EV-2300 - an improved state-of-the-art lead-acid battery) was designed specifically for improved performance, range, and life in electric vehicles. In order to obtain necessary performance data, the batteries were tested under various duty cycles typical of normal service. This program, supported by the Electric Power Research Institute, consisted of three tasks: determination of the effect of cycle life vs peak power and rest period, determination of the impact of charge method on cycle life, and evaluation of the EV-2300 battery system. Two supporting studies were also carried out: one on thermal management of electric-vehicle batteries and one on enhanced utilization of active material in lead-acid batteries.

Irreversible Wash Aid Additive for Cesium Mitigation. Small-Scale Demonstration and Lessons Learned

Energy Technology Data Exchange (ETDEWEB)

Kaminski, Michael [Argonne National Lab. (ANL), Argonne, IL (United States)

2015-01-01

The Irreversible Wash Aid Additive process has been under development by the U.S. Environmental Protection Agency (EPA) and Argonne National Laboratory (Argonne). This process for radioactive cesium mitigation consists of a solution to wash down contaminated structures, roadways, and vehicles and a sequestering agent to bind the radionuclides from the wash water and render them environmentally immobile. The purpose of this process is to restore functionality to basic services and immediately reduce the consequences of a radiologically-contaminated urban environment. Research and development have resulted in a down-selection of technologies for integration and demonstration at the pilot-scale level as part of the Wide Area Recovery and Resiliency Program (WARRP) under the Department of Homeland Security and the Denver Urban Area Security Initiative. As part of developing the methods for performing a pilot-scale demonstration at the WARRP conference in Denver in 2012, Argonne conducted small-scale field experiments at Separmatic Systems. The main purpose of these experiments was to refine the wash water collection and separations systems and demonstrate key unit operations to help in planning for the large scale demonstration in Denver. Since the purpose of these tests was to demonstrate the operations of the system, we used no radioactive materials. After a brief set of experiments with the LAKOS unit to familiarize ourselves with its operation, two experiments were completed on two separate dates with the Separmatic systems.

Site characterization and monitoring data from Area 5 Pilot Wells, Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

1994-02-01

The Special Projects Section (SPS) of Reynolds Electrical ampersand Engineering Co., Inc. (REECO) is responsible for characterizing the subsurface geology and hydrology of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) for the US Department of Energy, Nevada Operations Office (DOE/NV), Environmental Restoration and Waste Management Division, Waste Operations Branch. The three Pilot Wells that comprise the Pilot Well Project are an important part of the Area 5 Site Characterization Program designed to determine the suitability of the Area 5 RWMS for disposal of low-level waste (LLW), mixed waste (MW), and transuranic waste (TRU). The primary purpose of the Pilot Well Project is two-fold: first, to characterize important water quality and hydrologic properties of the uppermost aquifer; and second, to characterize the lithologic, stratigraphic, and hydrologic conditions which influence infiltration, redistribution, and percolation, and chemical transport through the thick vadose zone in the vicinity of the Area 5 RWMS. This report describes Pilot Well drilling and coring, geophysical logging, instrumentation and stemming, laboratory testing, and in situ testing and monitoring activities

Nevada Test Site 2001 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites; TOPICAL

International Nuclear Information System (INIS)

Y. E. Townsend

2002-01-01

Environmental monitoring data, subsidence monitoring data, and meteorology monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS) (refer to Figure 1). These monitoring data include radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota data. Although some of these media (radiation exposure, air, and groundwater) are reported in detail in other Bechtel Nevada (BN) reports (Annual Site Environmental Report[ASER], the National Emissions Standard for Hazardous Air Pollutants[NESHAP] report, and the Annual Groundwater Monitoring Report), they are also summarized in this report to provide an overall evaluation of RWMS performance and environmental compliance. Direct radiation monitoring data indicate that exposure at and around the RWMSs is not above background levels. Air monitoring data indicate that tritium concentrations are slightly above background levels. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS has not been affected by the facility. Meteorology data indicate that 2001 was an average rainfall year: rainfall totaled 150 mm (5.9 in) at the Area 3 RWMS and 120 mm (4.7 in) at the Area 5 RWMS. Vadose zone monitoring data indicate that 2001 rainfall infiltrated less than one meter (3 ft) before being returned to the atmosphere by evaporation. Soil-gas tritium monitoring data indicate slow subsurface migration, and tritium concentrations in biota were lower than in previous years. All 2001 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing within expectations of the model and parameter assumptions for the facility performance assessments

Closure Report for Corrective Action Unit 407: Roller Coaster RADSAFE Area, Tonopah Test Range, Nevada

International Nuclear Information System (INIS)

Fitzmaurice, T. M.

2001-01-01

This closure report (CR) provides documentation for the closure of the Roller Coaster RADSAFE Area (RCRSA) Corrective Action Unit (CAU) 407 identified in the Federal Facility Agreement and Consent Order (FFACO) (Nevada Division of Environmental Protection [NDEP] et al., 1996). CAU 407 is located at the Tonopah Test Range (TTR), Nevada. The TTR is approximately 225 kilometers (km) (140 miles [mi]) northwest of Las Vegas, Nevada (Figure 1). The RCRSA is located on the northeast comer of the intersection of Main Road and Browne's Lake Road, which is approximately 8 km (5 mi) south of Area 3 (Figure 1). The RCRSA was used during May and June of 1963 to decontaminate vehicles, equipment, and personnel from the Double Tracks and Clean Slate tests. Investigation of the RCRSA was conducted from June through November of 1998. A Corrective Action Decision Document (CADD) (U.S. Department of Energy, Nevada Operations Office [DOEN], 1999) was approved in October of 1999. The purpose of this CR is to: Document the closure activities as proposed in the Corrective Action Plan (CAP) (DOEM, 2000). Obtain a Notice of Completion from the NDEP. Recommend the movement of CAU 407 from Appendix III to Appendix IV of the FFACO. The following is the scope of the closure actions implemented for CAU 407: Removal and disposal of surface soils which were over three times background for the area. Soils identified for removal were disposed of at the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS). Excavated areas were backfilled with clean borrow soil located near the site. A soil cover was constructed over the waste disposal pit area, where subsurface constituents of concern remain. The site was fenced and posted as an ''Underground Radioactive Material'' area

Compilation of modal analyses of volcanic rocks from the Nevada Test Site area, Nye County, Nevada

International Nuclear Information System (INIS)

Page, W.R.

1990-01-01

Volcanic rock samples collected from the Nevada Test Site, Nye County, Nevada, between 1960 and 1985 were analyzed by thin section to obtain petrographic mode data. In order to provide rapid accessibility to the entire database, all data from the cards were entered into a computerized database. This computer format will enable workers involved in stratigraphic studies in the Nevada Test Site area and other locations in southern Nevada to perform independent analyses of the data. The data were compiled from the mode cards into two separate computer files. The first file consists of data collected from core samples taken from drill holes in the Yucca Mountain area. The second group of samples were collected from measured sections and surface mapping traverses in the Nevada Test Site area. Each data file is composed of computer printouts of tables with mode data from thin section point counts, comments on additional data, and location data. Tremendous care was taken in transferring the data from the cards to computer, in order to preserve the original information and interpretations provided by the analyzer. In addition to the data files above, a file is included that consists of Nevada Test Site petrographic data published in other US Geological Survey and Los Alamos National Laboratory reports. These data are presented to supply the user with an essentially complete modal database of samples from the volcanic stratigraphic section in the Nevada Test Site area. 18 refs., 4 figs

Airborne gravity tests in the Italian area to improve the geoid model of Italy

DEFF Research Database (Denmark)

Barzaghi, R; Borghi, A; Keller, K

2009-01-01

Airborne gravimetry is an important method for measuring gravity over large unsurveyed areas. This technology has been widely applied in Canada, Antarctica and Greenland to map the gravity fields of these regions and in recent years, in the oil industry. In 2005, two tests in the Italian area were...... performed by ENI in cooperation with the Politecnico di Milano and the Danish National Space Center. To the knowledge of the authors, these were the first experiments of this kind in Italy and were performed over the Ionian coasts of Calabria and the Maiella Mountains. The Calabria test field......, the collocation method applied to compare and merge ground-based and airborne data proved to be efficient and reliable. The standard deviation of the discrepancies between airborne data and collocation upward continued gravity is, in both cases, less than 8 mgal. In the Maiella test, the gravity field obtained...

Nevada Test Site 2005 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

David B. Hudson, Cathy A. Wills

2006-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2005 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports (U.S. Department of Energy, 2005; Grossman, 2005; Bechtel Nevada, 2006). Direct radiation monitoring data indicate that exposure levels around the RWMSs are at or below background levels. Air monitoring data at the Area 3 and Area 5 RWMSs indicate that tritium concentrations are slightly above background levels. There is no detectable man-made radioactivity by gamma spectroscopy, and concentrations of americium and plutonium are only slightly above detection limits at the Area 3 RWMS. Measurements at the Area 5 RWMS show that radon flux from waste covers is no higher than natural radon flux from undisturbed soil in Area 5. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by facility operations. Precipitation during 2005 totaled 219.1 millimeters (mm) (8.63 inches [in.]) at the Area 3 RWMS and 201.4 mm (7.93 in.) at the Area 5 RWMS. Soil-gas tritium monitoring continues to show slow subsurface migration consistent with previous results. Moisture from precipitation at Area 5 has percolated to the bottom of the bare-soil weighing lysimeter, but this same moisture has been removed from the vegetated weighing lysimeter by evapotranspiration. Vadose zone data from the operational waste pit covers show that precipitation from the fall of 2004 and the spring of 2005 infiltrated past the deepest sensors at 188 centimeters (6.2 feet) and remains in the pit cover

Nevada Test Site 2009 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

2010-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS). These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2009 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports. Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NTS. Air monitoring data at the Area 3 and Area 5 RWMSs indicate that tritium concentrations are slightly above background levels. All gamma spectroscopy results for air particulates collected at the Area 3 and Area 5 RWMS were below the minimum detectable concentrations, and concentrations of americium and plutonium are only slightly above detection limits. The measured levels of radionuclides in air particulates and moisture are below derived concentration guides for these radionuclides. Radon flux from waste covers is well below regulatory limits. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by facility operations. The 87.6 millimeters (mm) (3.45 inches (in.)) of precipitation at the Area 3 RWMS during 2009 is 43 percent below the average of 152.4 mm (6.00 in.), and the 62.7 mm (2.47 in.) of precipitation at the Area 5 RWMS during 2009 is 49 percent below the average of 122.5 mm (4.82 in.). Soil-gas tritium monitoring at borehole GCD-05 continues to show slow subsurface migration consistent with previous results. Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward percolation of precipitation more effectively than evaporation

Nevada Test Site Area 25, Radiological Survey and Cleanup Project, 1974-1983 (a revised final report). Revision 1

International Nuclear Information System (INIS)

Miller, M.G.

1984-12-01

This report describes the radiological survey, decontamination and decommissioning (D and D) of the Nevada Test Site (NTS) Area 25 facilities and land areas incorporated in the Nuclear Rocket Development Station (NRDS). Buildings, facilities and support systems used after 1959 for nuclear reactor and engine testing were surveyed for the presence of radioactive contamination. The radiological survey portion of the project encompassed portable instrument surveys and removable contamination surveys (swipe) for beta plus gamma and alpha radioactive contamination of facilities, equipment and land areas. Soil sampling was also accomplished. The majority of Area 25 facilities and land areas have been returned to unrestricted use. Remaining radiologically contaminated areas are posted with warning signs and barricades. 9 references, 23 figures

The indication area of a diagnostic test. Part I--discounting gain and loss in diagnostic certainty

NARCIS (Netherlands)

Stalpers, Lukas J. A.; Nelemans, Patty J.; Geurts, Sandra M. E.; Jansen, Erik; de Boer, Peter; Verbeek, André L. M.

2015-01-01

Test performance is conventionally expressed by gain in diagnostic certainty. We propose net diagnostic gain and indication area as more appropriate measures of test performance; then, the loss in certainty due to misclassification and the information of "no test" would be performed are taken into

Abbreviated sampling and analysis plan for planning decontamination and decommissioning at Test Reactor Area (TRA) facilities

International Nuclear Information System (INIS)

1994-10-01

The objective is to sample and analyze for the presence of gamma emitting isotopes and hazardous constituents within certain areas of the Test Reactor Area (TRA), prior to D and D activities. The TRA is composed of three major reactor facilities and three smaller reactors built in support of programs studying the performance of reactor materials and components under high neutron flux conditions. The Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) facilities are currently pending D/D. Work consists of pre-D and D sampling of designated TRA (primarily ETR) process areas. This report addresses only a limited subset of the samples which will eventually be required to characterize MTR and ETR and plan their D and D. Sampling which is addressed in this document is intended to support planned D and D work which is funded at the present time. Biased samples, based on process knowledge and plant configuration, are to be performed. The multiple process areas which may be potentially sampled will be initially characterized by obtaining data for upstream source areas which, based on facility configuration, would affect downstream and as yet unsampled, process areas. Sampling and analysis will be conducted to determine the level of gamma emitting isotopes and hazardous constituents present in designated areas within buildings TRA-612, 642, 643, 644, 645, 647, 648, 663; and in the soils surrounding Facility TRA-611. These data will be used to plan the D and D and help determine disposition of material by D and D personnel. Both MTR and ETR facilities will eventually be decommissioned by total dismantlement so that the area can be restored to its original condition

F and H Area Effluent Treatment Facility (F/H ETF): ultrafiltration and hyperfiltration systems testing at Carre, Inc. with simulated F and H area effluents

International Nuclear Information System (INIS)

Ryan, J.P.

1984-01-01

The F and H Area Effluent Treatment Facility is essentially a four-stage process that will decontaminate the waste water that is currently being discharged to seepage basins in the Separations Areas. The stages include pretreatment, reverse osmosis, ion exchange, and evaporation. A series of tests were performed at Carre, Inc. (Seneca, SC) from March 5 through March 13, to determine the usefulness of ultrafiltration (UF) in the pretreatment stage of the ETF. The results of that testing program indicate that UF would be an excellent means of removing entrained activity from the 200 Area process effluents. Hyperfiltration (HF) was also tested as a means of providing an improved concentration factor from the reverse osmosis stage. The results show that the membranes that were tested would not reject salt well enough at high salt concentrations to be useful in the final reverse osmosis stage. However, there are several membranes which are commercially available that would provide the needed rejection if they could be applied (dynamically) on the Carre support structure. This avenue is still being explored, as theoretically, it could eliminate the need for the F/H ETF evaporator

Nevada Test Site 2007 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

NSTec Environmental Management

2008-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2007 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports (National Security Technologies, LLC, 2007a; 2008; Warren and Grossman, 2008). Direct radiation monitoring data indicate exposure levels at the RWMSs are at background levels. Air monitoring data at the Area 3 and Area 5 RWMSs indicate that tritium concentrations are slightly above background levels. A single gamma spectroscopy measurement for cesium was slightly above the minimum detectable concentration, and concentrations of americium and plutonium are only slightly above detection limits at the Area 3 RWMS. The measured levels of radionuclides in air particulates are below derived concentration guides for these radionuclides. Radon flux from waste covers is well below regulatory limits. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by facility operations. The 136.8 millimeters (mm) (5.39 inches [in.]) of precipitation at the Area 3 RWMS during 2007 is 13 percent below the average of 158.1 mm (6.22 in.), and the 123.8 mm (4.87 in.) of precipitation at the Area 5 RWMS during 2007 is 6 percent below the average of 130.7 mm (5.15 in.). Soil-gas tritium monitoring at borehole GCD-05U continues to show slow subsurface migration consistent with previous results. Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward movement percolation of precipitation more effectively

Vibratory response of a mirror support/positioning system for the Advanced Photon Source project at Argonne National Laboratory

International Nuclear Information System (INIS)

Basdogan, I.; Shu, Deming; Kuzay, T.M.; Royston, T.J.; Shabana, A.A.

1996-01-01

The vibratory response of a typical mirror support/positioning system used at the experimental station of the Advanced Photon Source (APS) project at Argonne National Laboratory is investigated. Positioning precision and stability are especially critical when the supported mirror directs a high-intensity beam aimed at a distant target. Stability may be compromised by low level, low frequency seismic and facility-originated vibrations traveling through the ground and/or vibrations caused by flow-structure interactions in the mirror cooling system. The example case system has five positioning degrees of freedom through the use of precision actuators and rotary and linear bearings. These linkage devices result in complex, multi-dimensional vibratory behavior that is a function of the range of positioning configurations. A rigorous multibody dynamical approach is used for the development of the system equations. Initial results of the study, including estimates of natural frequencies and mode shapes, as well as limited parametric design studies, are presented. While the results reported here are for a particular system, the developed vibratory analysis approach is applicable to the wide range of high-precision optical positioning systems encountered at the APS and at other comparable facilities

Underground Test Area Subproject Phase I Data Analysis Task. Volume VIII - Risk Assessment Documentation Package

Energy Technology Data Exchange (ETDEWEB)

None

1996-12-01

Volume VIII of the documentation for the Phase I Data Analysis Task performed in support of the current Regional Flow Model, Transport Model, and Risk Assessment for the Nevada Test Site Underground Test Area Subproject contains the risk assessment documentation. Because of the size and complexity of the model area, a considerable quantity of data was collected and analyzed in support of the modeling efforts. The data analysis task was consequently broken into eight subtasks, and descriptions of each subtask's activities are contained in one of the eight volumes that comprise the Phase I Data Analysis Documentation.

Fabrication and radio frequency test of large-area MgB2 films on niobium substrates