WorldWideScience

Sample records for fission program summaries

  1. World Energy Data System (WENDS). Volume XI. Nuclear fission program summaries

    International Nuclear Information System (INIS)

    1979-06-01

    Brief management and technical summaries of nuclear fission power programs are presented for nineteen countries. The programs include the following: fuel supply, resource recovery, enrichment, fuel fabrication, light water reactors, heavy water reactors, gas cooled reactors, breeder reactors, research and test reactors, spent fuel processing, waste management, and safety and environment

  2. World Energy Data System (WENDS). Volume XI. Nuclear fission program summaries

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    Brief management and technical summaries of nuclear fission power programs are presented for nineteen countries. The programs include the following: fuel supply, resource recovery, enrichment, fuel fabrication, light water reactors, heavy water reactors, gas cooled reactors, breeder reactors, research and test reactors, spent fuel processing, waste management, and safety and environment. (JWR)

  3. Program summary

    International Nuclear Information System (INIS)

    1982-07-01

    The operating, construction, and development activities of the Department of Energy in the areas of uranium enrichment are described. The DOE supplies the enrichment service through toll enrichment contracts with foreign and domestic utilities by enriching uranium supplied by the utility to the desired U-235 level. This role will continue well into the next century. In addition it provides enriched uranium for US Government needs and for R and D purposes. At the present time, almost all the world's capacity to produce enriched uranium uses the gaseous diffusion process. The United States built the first gaseous diffusion plant during World War II. Later this plant was expanded and two additional plants were built. There is presently a $1.5 billion improvement and uprating program near completion which will improve the plant efficiency and increase the total capacity of the three plants by 60 percent to 27.3 million SWU per year. The Administration's energy message in 1977 provided for a further expansion of this capacity by using gas centrifuge technology. The new gas centrifuge plant is being built near the existing GDP near Portsmouth, Ohio. The normal capacity of an 8 building process plant will be 13.2 million SWU per year. The first 2.2 million SWU of capacity is scheduled to be available in 1989. The remaining capacity will be added as needed to meet demand and the overall goal of the program. The goal of the Uranium Enrichment Program is to meet domestic, foreign, and US Government requirements for uranium enrichment services in an economical, reliable, safe and environmentally acceptable manner. To ensure accomplishment of this goal, the overall program is broken down into three areas of implementation; Enrichment Operations; Capacity Upgrading Operations; and Business Operations

  4. Modification of the fission product inventory program FISPIN

    International Nuclear Information System (INIS)

    Thomas, R.B.

    1977-05-01

    The fission product inventory program FISPIN calculates inventories of fission products, actinides and activation products, during and after irradiation in a nuclear reactor, estimates also being given for heat output and radioactive activity of the isotopes. The program has been developed further by making provision for the simulation of fuel reprocessing and in providing subroutines to make the program compatible with nuclear data in a slightly modified ENDF/B4 format. Continuous development of FISPIN over the years has however involved many program alterations and additions, and this has resulted in a generally untidy and cumbersome program. An attempt has therefore been made to improve the basic structure of the program. The subject is dealt with under the following headings: modularisation, direct access data, override facility, selective output, flowcharts, summary. (U.K.)

  5. Computer program FPIP-REV calculates fission product inventory for U-235 fission

    Science.gov (United States)

    Brown, W. S.; Call, D. W.

    1967-01-01

    Computer program calculates fission product inventories and source strengths associated with the operation of U-235 fueled nuclear power reactor. It utilizes a fission-product nuclide library of 254 nuclides, and calculates the time dependent behavior of the fission product nuclides formed by fissioning of U-235.

  6. Summary Report of Second Research Coordination Meeting on Prompt Fission Neutron Spectra of Major Actinides

    International Nuclear Information System (INIS)

    Capote Noy, R.

    2013-09-01

    A summary is given of the Second Research Coordination Meeting on Prompt Fission Neutron Spectra of Actinides. Experimental data and modelling methods on prompt fission neutron spectra were reviewed. Extensive technical discussions held on theoretical methods to calculate prompt fission spectra. Detailed coordinated research proposals have been agreed. Summary reports of selected technical presentations at the meeting are given. The resulting work plan of the Coordinated Research Programme is summarized, along with actions and deadlines. (author)

  7. Workshop summaries for the third US/USSR symposium on fusion-fission reactors

    International Nuclear Information System (INIS)

    Jassby, D.L.

    1979-07-01

    Workshop summaries on topics related to the near-term development requirements for fusion-fission (hybrid) reactors are presented. The summary topics are as follows: (1) external factors, (2) plasma engineering, (3) ICF hybrid reactors, (4) blanket design, (5) materials and tritium, and (6) blanket engineering development requirements

  8. Geothermal energy. Program summary

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    Brief descriptions of geothermal projects funded through the Department of Energy during FY 1978 are presented. Each summary gives the project title, contractor name, contract number, funding level, dates, location, and name of the principal investigator, together with project highlights, which provide informaion such as objectives, strategies, and a brief project description. (MHR)

  9. Biomass energy systems program summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-07-01

    Research programs in biomass which were funded by the US DOE during fiscal year 1978 are listed in this program summary. The conversion technologies and their applications have been grouped into program elements according to the time frame in which they are expected to enter the commercial market. (DMC)

  10. Photovoltaic systems. Program summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-12-01

    Each of the Department of Energy's Photovoltaic Systems Program projects funded and/or in existence during fiscal year 1978 (October 1, 1977 through September 30, 1978) are described. The project sheets list the contractor, principal investigator, and contract number and funding and summarize the programs and status. The program is divided into various elements: program assessment and integration, research and advanced development, technology development, system definition and development, system application experiments, and standards and performance criteria. (WHK)

  11. Program summary report

    International Nuclear Information System (INIS)

    1978-01-01

    The report provides summary information on all phases of nuclear regulation, and is intended as an information and decision-making tool for mid and upper level management of the Nuclear Regulatory Commission. The report is divided functionally into ten sections: (1) nuclear power plants in the United States; (2) operating nuclear power plants; (3) reactors under construction; (4) operating license applications under NRC review; (5) construction permit applications and special projects under NRC review; (6) ACRS and ASLBP; (7) nuclear materials; (8) standards and regulations; (9) research projects; and (10) foreign reactors

  12. Fission energy program of the US Department of Energy, FY 1981

    International Nuclear Information System (INIS)

    1980-03-01

    Information is presented concerning the National Energy Plan and fission energy policy; fission energy program management; converter reactor systems; breeder reactor systems; and special nuclear evaluations and systems

  13. Status of fission yield measurements

    International Nuclear Information System (INIS)

    Maeck, W.J.

    1979-01-01

    Fission yield measurement and yield compilation activities in the major laboratories of the world are reviewed. In addition to a general review of the effort of each laboratory, a brief summary of yield measurement activities by fissioning nuclide is presented. A new fast reactor fission yield measurement program being conducted in the US is described

  14. Federal Wind Energy Program. Program summary. [USA

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    The objective of the Federal Wind Energy Program is to accelerate the development of reliable and economically viable wind energy systems and enable the earliest possible commercialization of wind power. To achieve this objective for small and large wind systems requires advancing the technology, developing a sound industrial technology base, and addressing the non-technological issues which could deter the use of wind energy. This summary report outlines the projects being supported by the program through FY 1977 toward the achievement of these goals. It also outlines the program's general organization and specific program elements.

  15. 2011 Annual Criticality Safety Program Performance Summary

    Energy Technology Data Exchange (ETDEWEB)

    Andrea Hoffman

    2011-12-01

    The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection, an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The

  16. Mitochondrial fission proteins regulate programmed cell death in yeast.

    Science.gov (United States)

    Fannjiang, Yihru; Cheng, Wen-Chih; Lee, Sarah J; Qi, Bing; Pevsner, Jonathan; McCaffery, J Michael; Hill, R Blake; Basañez, Gorka; Hardwick, J Marie

    2004-11-15

    The possibility that single-cell organisms undergo programmed cell death has been questioned in part because they lack several key components of the mammalian cell death machinery. However, yeast encode a homolog of human Drp1, a mitochondrial fission protein that was shown previously to promote mammalian cell death and the excessive mitochondrial fragmentation characteristic of apoptotic mammalian cells. In support of a primordial origin of programmed cell death involving mitochondria, we found that the Saccharomyces cerevisiae homolog of human Drp1, Dnm1, promotes mitochondrial fragmentation/degradation and cell death following treatment with several death stimuli. Two Dnm1-interacting factors also regulate yeast cell death. The WD40 repeat protein Mdv1/Net2 promotes cell death, consistent with its role in mitochondrial fission. In contrast to its fission function in healthy cells, Fis1 unexpectedly inhibits Dnm1-mediated mitochondrial fission and cysteine protease-dependent cell death in yeast. Furthermore, the ability of yeast Fis1 to inhibit mitochondrial fission and cell death can be functionally replaced by human Bcl-2 and Bcl-xL. Together, these findings indicate that yeast and mammalian cells have a conserved programmed death pathway regulated by a common molecular component, Drp1/Dnm1, that is inhibited by a Bcl-2-like function.

  17. Fossil energy program. Summary document

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-05-01

    This program summary document presents a comprehensive overview of the research, development, and demonstration (RD and D) activities that will be performed in FY 1981 by the Assistant Secretary for Fossil Energy (ASFE), US Department of Energy (DOE). The ASFE technology programs for the fossil resources of coal, petroleum (including oil shale) and gas have been established with the goal of making substantive contributions to the nation's future supply and efficienty use of energy. On April 29, 1977, the Administration submitted to Congress the National Energy Plan (NEP) and accompanying legislative proposals designed to establish a coherent energy policy structure for the United States. Congress passed the National Energy Act (NEA) on October 15, 1978, which allows implementation of the vital parts of the NEP. The NEP was supplemented by additional energy policy statements culminating in the President's address on July 15, 1979, presenting a program to further reduce dependence on imported petroleum. The passage of the NEA-related energy programs represent specific steps by the Administration and Congress to reorganize, redirect, and clarify the role of the Federal Government in the formulation and execution of national energy policy and programs. The energy technology RD and D prog4rams carried out by ASFE are an important part of the Federal Government's effort to provide the combination and amounts of energy resources needed to ensure national security and continued economic growth.

  18. Mitochondrial fission proteins regulate programmed cell death in yeast

    OpenAIRE

    Fannjiang, Yihru; Cheng, Wen-Chih; Lee, Sarah J.; Qi, Bing; Pevsner, Jonathan; McCaffery, J. Michael; Hill, R. Blake; Basañez, Gorka; Hardwick, J. Marie

    2004-01-01

    The possibility that single-cell organisms undergo programmed cell death has been questioned in part because they lack several key components of the mammalian cell death machinery. However, yeast encode a homolog of human Drp1, a mitochondrial fission protein that was shown previously to promote mammalian cell death and the excessive mitochondrial fragmentation characteristic of apoptotic mammalian cells. In support of a primordial origin of programmed cell death involving mitochondria, we fo...

  19. 2011 statistical summaries : FTA grant assistance programs.

    Science.gov (United States)

    2013-05-01

    The 2011 Statistical Summaries provides information about the Federal Transit Administrations (FTA) major financial aid programs for Federal Fiscal Year (FY) 2011. The report covers the following programs: Urbanized Area Formula, Non-urbanized Are...

  20. 2010 statistical summaries : FTA grant assistance programs.

    Science.gov (United States)

    2013-07-01

    The 2010 Statistical Summaries provides information about the Federal Transit Administrations (FTA) major financial aid programs for Federal Fiscal Year (FY) 2010. The report covers the following programs: Urbanized Area Formula, Non-urbanized Are...

  1. 2012 statistical summaries : FTA grant assistance programs.

    Science.gov (United States)

    2013-12-01

    The 2012 Statistical Summaries provides information about the Federal Transit Administrations (FTA) major financial aid programs for : Federal Fiscal Year (FY) 2012. The report covers the following programs: Urbanized Area Formula, Non-urbanized A...

  2. Nuclear fission and neutron-induced fission cross-sections

    Energy Technology Data Exchange (ETDEWEB)

    James, G.D.; Lynn, J.E.; Michaudon, A.; Rowlands, J.; de Saussure, G.

    1981-01-01

    A general presentation of current knowledge of the fission process is given with emphasis on the low energy fission of actinide nuclei and neutron induced fission. The need for and the required accuracy of fission cross section data in nuclear energy programs are discussed. A summary is given of the steps involved in fission cross section measurement and the range of available techniques. Methods of fission detection are described with emphasis on energy dependent changed and detector efficiency. Examples of cross section measurements are given and data reduction is discussed. The calculation of fission cross sections is discussed and relevant nuclear theory including the formation and decay of compound nuclei and energy level density is introduced. A description of a practical computation of fission cross sections is given.

  3. An application program for fission product decay heat calculations

    International Nuclear Information System (INIS)

    Pham, Ngoc Son; Katakura, Jun-ichi

    2007-10-01

    The precise knowledge of decay heat is one of the most important factors in safety design and operation of nuclear power facilities. Furthermore, decay heat data also play an important role in design of fuel discharges, fuel storage and transport flasks, and in spent fuel management and processing. In this study, a new application program, called DHP (Decay Heat Power program), has been developed for exact decay heat summation calculations, uncertainty analysis, and for determination of the individual contribution of each fission product. The analytical methods were applied in the program without any simplification or approximation, in which all of linear and non-linear decay chains, and 12 decay modes, including ground state and meta-stable states, are automatically identified, and processed by using a decay data library and a fission yield data file, both in ENDF/B-VI format. The window interface of the program is designed with optional properties which is very easy for users to run the code. (author)

  4. Fission Product Experimental Program: Validation and Computational Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Leclaire, N.; Ivanova, T.; Letang, E. [Inst Radioprotect and Surete Nucl, F-92262 Fontenay Aux Roses (France); Girault, E. [CEA Valduc, Serv Rech Neutron and Critcite, 21 - Is-sur-Tille (France); Thro, J. F. [AREVA NC, F-78000 Versailles (France)

    2009-02-15

    From 1998 to 2004, a series of critical experiments referred to as the fission product (FP) experimental program was performed at the Commissariat a l'Energie Atomique Valduc research facility. The experiments were designed by Institut de Radioprotection et de Surete Nucleaire (IRSN) and funded by AREVA NC and IRSN within the French program supporting development of a technical basis for burnup credit validation. The experiments were performed with the following six key fission products encountered in solution either individually or as mixtures: {sup 103}Rh, {sup 133}Cs, {sup nat}Nd, {sup 149}Sm, {sup 152}Sm, and {sup 155}Gd. The program aimed at compensating for the lack of information on critical experiments involving FPs and at establishing a basis for FPs credit validation. One hundred forty-five critical experiments were performed, evaluated, and analyzed with the French CRISTAL criticality safety package and the American SCALE5. 1 code system employing different cross-section libraries. The aim of the paper is to show the experimental data potential to improve the ability to perform validation of full burnup credit calculation. The paper describes three Phases of the experimental program; the results of preliminary evaluation, the calculation, and the sensitivity/uncertainty study of the FP experiments used to validate the APOLLO2-MORET 4 route in the CRISTAL criticality package for burnup credit applications. (authors)

  5. Summary of Green Building Programs

    Energy Technology Data Exchange (ETDEWEB)

    2002-08-01

    In early 2002, the National Association of Home Builders completed a census of residential green building programs across the United States to assess differences and similarities among programs. This report catalogs different ways that builders participate in residential green building programs.

  6. FISPRO: a simplified computer program for general fission product formation and decay calculations

    International Nuclear Information System (INIS)

    Jiacoletti, R.J.; Bailey, P.G.

    1979-08-01

    This report describes a computer program that solves a general form of the fission product formation and decay equations over given time steps for arbitrary decay chains composed of up to three nuclides. All fission product data and operational history data are input through user-defined input files. The program is very useful in the calculation of fission product activities of specific nuclides for various reactor operational histories and accident consequence calculations

  7. Photovoltaic energy systems. Program summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-01-01

    The ongoing research, development, and demonstration efforts of the Photovoltaics Program are highlighted and each of the US Department of Energy's current photovoltaics projects initiated or renewed during fiscal year 1981 is described, including its title, directing organization, project engineer, contractor, principal investigator, contract period, funding, and objectives. The Photovoltaics Program is briefly summarized, including the history and organization and highlights of the research and development and of planning, assessment, and integration. Also summarized is the Federal Photovoltaic Utilization Program. An exhaustive bibliography is included. (LEW)

  8. Summary of foreign HTGR programs

    International Nuclear Information System (INIS)

    1980-06-01

    This report contains pertinent information on the status, objectives, budgets, major projects and facilities, as well as user, industrial and governmental organizations involved in major foreign gas-cooled thermal reactor programs. This is the second issue of this document (the first was issued in March 1979). The format has been revised to consolidate material according to country. These sections are followed by the foreign HTGR program index which serves as a quick reference to some of the many acronyms associated with the foreign HTGR programs

  9. LLL mirror fusion program: summary

    International Nuclear Information System (INIS)

    Fowler, T.K.

    1977-01-01

    During 1976, new Mirror Program plans have been laid out to take into account the significant advances during the last 18 months. The program is now focused on two new mirror concepts, field reversal and the tandem mirror, that can obtain high Q, defined as the ratio of fusion power output to the neutral-beam power injected to sustain the reaction. Theoretically, both concepts can attain Q = 5 or more, as compared to Q = 1 in previous mirror designs. Experimental planning for the next 5 years is complete in broad outline, and we are turning attention to what additional steps are necessary to reach our long-range goal of an experimental mirror reactor operating by 1990. Highlights of the events that have led to the above circumstance are listed, and experimental program plans are outlined

  10. Pollution Prevention Program: Technology summary

    International Nuclear Information System (INIS)

    1994-02-01

    The Department of Energy (DOE) has established a national Research, Development, Demonstration, Testing, and Evaluation (RDDT ampersand E) Program for pollution prevention and waste minimization at its production plants During FY89/90 the Office of Environmental Restoration and Waste Management (EM), through the Office of Technology Development (OTD), established comprehensive, pollution prevention technical support programs to demonstrate new, environmentally-conscious technology for production processes. The RDDT ampersand E program now entails collaborative efforts across DOE. The Pollution Prevention Program is currently supporting three major activities: The DOE/US Air Force Memorandum of Understanding Program is a collaborative effort to utilize the combined resources of DOE and the Department of Defense, eliminate duplication of effort in developing technologies, and to facilitate technology solutions aimed at reducing waste through process modification, material substitution or recycling. The Waste Component Recycle, Treatment and Disposal Integrated Demonstration (WeDID) will develop recycle, treatment, and disposal processes and associated technologies for use in the dismantlement of non-nuclear weapons components, to support US arms treaties and policies. This program will focus on meeting all security and regulatory requirements (with additional benefit to the commercial electronics industry). The Environmentally Conscious Manufacturing Integrated Demonstration (ECMID) will effectively implement ECM technologies that address both the needs of the DOE Complex and US electronics industry, and encourage strong interaction between DOE and US industry. The ECMID will also develop life cycle analysis tools that will aid decisionmakers in selecting the optimum process based on the tradeoffs between cost an environmental impact

  11. Robotics crosscutting program: Technology summary

    International Nuclear Information System (INIS)

    1996-08-01

    The Office of Environmental Management (EM) is responsible for cleaning up the legacy of radioactive and chemically hazardous waste at contaminated sites and facilities throughout the U.S. Department of Energy (DOE) nuclear weapons complex, preventing further environmental contamination, and instituting responsible environmental management. Initial efforts to achieve this mission resulted in the establishment of environmental restoration and waste management programs. However, as EM began to execute its responsibilities, decision makers became aware that the complexity and magnitude of this mission could not be achieved efficiently, affordably, safely, or reasonably with existing technology. Once the need for advanced cleanup technologies became evident, EM established an aggressive, innovative program of applied research and technology development. The Office of Technology Development (OTD) was established in November 1989 to advance new and improved environmental restoration and waste management technologies that would reduce risks to workers, the public, and the environment; reduce cleanup costs; and devise methods to correct cleanup problems that currently have no solutions. In 1996, OTD added two new responsibilities - management of a Congressionally mandated environmental science program and development of risk policy, requirements, and guidance. OTD was renamed the Office of Science and Technology (OST). This documents presents information concerning robotics tank waste retrieval overview, robotic chemical analysis automation, robotics decontamination and dismantlement, and robotics crosscutting and advanced technology

  12. Subsurface transport program: Research summary

    International Nuclear Information System (INIS)

    1987-01-01

    DOE's research program in subsurface transport is designed to provide a base of fundamental scientific information so that the geochemical, hydrological, and biological mechanisms that contribute to the transport and long term fate of energy related contaminants in subsurface ecosystems can be understood. Understanding the physical and chemical mechanisms that control the transport of single and co-contaminants is the underlying concern of the program. Particular attention is given to interdisciplinary research and to geosphere-biosphere interactions. The scientific results of the program will contribute to resolving Departmental questions related to the disposal of energy-producing and defense wastes. The background papers prepared in support of this document contain additional information on the relevance of the research in the long term to energy-producing technologies. Detailed scientific plans and other research documents are available for high priority research areas, for example, in subsurface transport of organic chemicals and mixtures and in the microbiology of deep aquifers. 5 figs., 1 tab

  13. Summary of JAPEIC age program

    International Nuclear Information System (INIS)

    Miyoshi, S.; Maeda, N.; Yamaguchi, A.

    1992-01-01

    Japan Power Engineering and Inspection Corporation (JAPEIC) is a statutory foundation charged with responsibility of enhancing thermal and nuclear power plant quality. JAPEIC performs construction and pre-service inspections as well as periodic inspections of many types of power plants including nuclear, gas turbine and internal combustion systems. In 1987 a research center was established to permit the systematic examination of advanced inspection technologies. One of the Structural Materials in Use for commercial Nuclear Power Plants provides the link to this workshop. The project is also referred to as the Aging General Evaluation (AGE) project. The AGE project is a six year, multi-task effort addressing material condition monitoring. One set of tasks emphasizes instrumentation simulation tasks to aid in application and utilization. All tasks are in their initial phases. The program is described in this paper

  14. 41 CFR 60-2.31 - Program summary.

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 1 2010-07-01 2010-07-01 true Program summary. 60-2.31...-AFFIRMATIVE ACTION PROGRAMS Miscellaneous § 60-2.31 Program summary. The affirmative action program must be summarized and updated annually. The program summary must be prepared in a format which will be prescribed by...

  15. Program summaries for 1979: energy sciences programs

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    This report describes the objectives of the various research programs being conducted by the Chemical Sciences, Metallurgy and Materials Science, and Process Science divisions of the BNL Dept. of Energy and Environment. Some of the more significant accomplishments during 1979 are also reported along with plans for 1980. Some of the topics under study include porphyrins, combustion, coal utilization, superconductors, semiconductors, coal, conversion, fluidized-bed combustion, polymers, etc. (DLC)

  16. Program summaries for 1979: environmental programs

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    Progress in research is reported for the three Divisions and one Group. Current programs in the Atmospheric Sciences Division include major participation in the multilaboratory cooperative Multistate Power Production Pollution Study - Regional Acidity of Industrial Emissions (MAP3S-RAINE), involving both field and modeling studies related to power-plant produced atmospheric pollutants on a regional scale, the study of the meteorology of the coastal land-sea interface, including both field and analytical activities, and field and modeling studies of the exchange of momentum, heat, and water vapor between the atmosphere and the ocean. The Environmental Chemistry Division is engaged in a wide range of programs including the development of methodologies and practical instrumentation for the detection and measurement of a variety of atmospheric constituents at ambient levels in real time in the field and in the laboratory, development and measurement of atmospheric tracers at extremely low levels, theoretical, laboratory, and field studies of the formation and behavior of aerosol particulates, and studies of gaseous and particulate emissions at power plants and in stack plumes in the atmosphere. The programs in Oceanographic Sciences include studies on coastal transport and diffusion, primary production and utilization, food chain dynamics, and ecosystems analysis. Emphasis in the Land and Freshwater Environmental Sciences Group has been on the effects of acid rain caused by energy-related pollutants on field crops, microbiota, and forest and freshwater ecosystems. Studies of the effects of acidification on the biota and biological processes of freshwater lakes are reported. Areas in the eastern United States sensitive to acidification were evaluated and mapped in a field and library study. (JGB)

  17. Summary reports of activities under visiting research program, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This report contains summary reports of activities under visiting research program, 1995 carried out in the Research Reactor Institute, Kyoto University in 1995. As cooperative activities of KUR, 9 projects and 91 ordinary researches are described in their summaries, with 10 ordinary researches in KUCA cooperative activities. Titles of the 9 projects are development of biological effect analysis of monochromatic neutron spectrum field, study on optimization of bottle condition in ultra cold neutron fission experiment, feature improvement of KUR-ISOL and nuclear spectroscopy and nuclear physics using it, fundamental study on development of new compound for thermal neutron trapping therapy and expansion of its adopting illness, study on properties of synthetic metal using nuclear procedure, neutron diffraction of magnetic substances under the extreme conditions (high pressure, high magnetic field), study on movement in environment of harmful substances, fundamental study on radiation protection against controllable radiation in KUR, and dynamic property study of metal materials using low speed neutron scattering method. (G.K.)

  18. Short rotation woody crops program: 1982 program summary

    Energy Technology Data Exchange (ETDEWEB)

    Ranney, J.W.; Cushman, J.H.; Trimble, J.L.

    1982-09-01

    The general objective and overall approach of the program are discussed, and the status, specific goals, and recent results of the three major research areas are presented. The report concludes with brief summaries of the individual research projects in the program.

  19. Innovative Technology Development Program. Final summary report

    International Nuclear Information System (INIS)

    Beller, J.

    1995-08-01

    Through the Office of Technology Development (OTD), the U.S. Department of Energy (DOE) has initiated a national applied research, development, demonstration, testing, and evaluation program, whose goal has been to resolve the major technical issues and rapidly advance technologies for environmental restoration and waste management. The Innovative Technology Development (ITD) Program was established as a part of the DOE, Research, Development, Demonstration, Testing, and Evaluation (RDDT ampersand E) Program. The plan is part of the DOE's program to restore sites impacted by weapons production and to upgrade future waste management operations. On July 10, 1990, DOE issued a Program Research and Development Announcement (PRDA) through the Idaho Operations Office to solicit private sector help in developing innovative technologies to support DOE's clean-up goals. This report presents summaries of each of the seven projects, which developed and tested the technologies proposed by the seven private contractors selected through the PRDA process

  20. 1978 source book for fusion--fission hybrid systems. Executive summary

    International Nuclear Information System (INIS)

    Crowley, J.H.; Pavlenco, G.F.; Kaminski, R.S.

    1978-12-01

    The 1978 Source Book for Fusion--Fission Hybrid Systems was prepared by United Engineers and Constructors Inc. for the U.S. Department of Energy and the Electric Power Research Institute. It reviews the current status of fusion--fission hybrid reactors, and presents the prevailing views of members of the fusion community on the RD and D timetable required for the development and commercialization of fusion--fission hybrids. The results presented are based on a review of related references as well as interviews with recognized experts in the field. Contributors from the academic and industrial communities are listed

  1. Consultants’ Meeting on Recommended Input Parameters for Fission Cross-Section Calculations. Summary Report

    International Nuclear Information System (INIS)

    Capote Noy, Roberto; Simakov, Stanislav; Goriely, Stephane; Hilaire, Stephane; Iwamoto, Osamu; Kawano, Toshihiko; Koning, Arjan

    2014-12-01

    A Consultants’ Meeting on “Recommended Input Parameters for Fission Cross-Section Calculations” was held at IAEA Headquarters, Vienna, Austria to define the scope, deliverables and appropriate work programme of a possible Coordinated Research Project (CRP) on the subject. Presentations are available online at https://www-nds.iaea.org/indexmeeting-crp/CM-RIPL-fission/. A new CRP was endorsed to recommend a comprehensive set of fission input parameters needed for the modelling of fission cross sections. Special attention will be given to the modelling of photon and nucleon induced reactions on actinides with emphasis on incident energies below 30 MeV. The goals and detailed deliverables of the planned CRP were proposed. A Hauser-Feshbach code intercomparison was recommended. (author)

  2. Consultants' meeting on prompt fission neutron spectra of major actinides. Summary report

    International Nuclear Information System (INIS)

    Capote Noy, R.; Maslov, V.; Bauge, E.; Ohsawa, T.; Vorobyev, A.; Chadwick, M.B.; Oberstedt, S.

    2009-01-01

    A Consultants' Meeting on 'Prompt Fission Neutron Spectra of Major Actinides' was held at IAEA Headquarters, Vienna, Austria, to discuss the adequacy and quality of the recommended prompt fission neutron spectra to be found in existing nuclear data applications libraries. These prompt fission neutron spectra were judged to be inadequate, and this problem has proved difficult to resolve by means of theoretical modelling. Major adjustments may be required to ensure the validity of such important data. There is a strong requirement for an international effort to explore and resolve these difficulties and recommend prompt fission neutron spectra and uncertainty covariance matrices for the actinides over the neutron energy range from thermal to 20 MeV. Participants also stressed that there would be a strong need for validation of the resulting data against integral critical assembly and dosimetry data. (author)

  3. Fission product inventory calculation by a CASMO/ORIGEN coupling program

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Do Heon; Kim, Jong Kyung [Hanyang University, Seoul (Korea, Republic of); Choi, Hang Bok; Roh, Gyu Hong; Jung, In Ha [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    A CASMO/ORIGEN coupling utility program was developed to predict the composition of all the fission products in spent PWR fuels. The coupling program reads the CASMO output file, modifies the ORIGEN cross section library and reconstructs the ORIGEN input file at each depletion step. In ORIGEN, the burnup equation is solved for actinides and fission products based on the fission reaction rates and depletion flux of CASMO. A sample calculation has been performed using a 14 x 14 PWR fuel assembly and the results are given in this paper. 3 refs., 1 fig., 1 tab. (Author)

  4. Fission product inventory calculation by a CASMO/ORIGEN coupling program

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Do Heon; Kim, Jong Kyung [Hanyang University, Seoul (Korea, Republic of); Choi, Hang Bok; Roh, Gyu Hong; Jung, In Ha [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    A CASMO/ORIGEN coupling utility program was developed to predict the composition of all the fission products in spent PWR fuels. The coupling program reads the CASMO output file, modifies the ORIGEN cross section library and reconstructs the ORIGEN input file at each depletion step. In ORIGEN, the burnup equation is solved for actinides and fission products based on the fission reaction rates and depletion flux of CASMO. A sample calculation has been performed using a 14 x 14 PWR fuel assembly and the results are given in this paper. 3 refs., 1 fig., 1 tab. (Author)

  5. Specialists' meeting on fission product release and transport in gas-cooled reactors. Summary report

    International Nuclear Information System (INIS)

    1985-01-01

    The purpose of the Meeting on Fission Product Release and Transport in Gas-Cooled Reactors was to compare and discuss experimental and theoretical results of fission product behaviour in gas-cooled reactors under normal and accidental conditions and to give direction for future development. The technical part of the meeting covered operational experience and laboratory research, activity release, and behaviour of released activity

  6. Specialists' meeting on fission product release and transport in gas-cooled reactors. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-07-01

    The purpose of the Meeting on Fission Product Release and Transport in Gas-Cooled Reactors was to compare and discuss experimental and theoretical results of fission product behaviour in gas-cooled reactors under normal and accidental conditions and to give direction for future development. The technical part of the meeting covered operational experience and laboratory research, activity release, and behaviour of released activity.

  7. Balanced program plan. Volume XI. Fission analysis for biomedical and environmental research

    International Nuclear Information System (INIS)

    Foster, R.F.

    1976-06-01

    Factors involved in the formulation of an ERDA-sponsored program for health and environmental research in connection with the fission fuel cycle are discussed under the following section headings: major issues associated with the use of nuclear power; fission fuel cycle technology: milling, UF 6 production, uranium enrichment, plutonium fuel fabrication, power production (reactors), fuel reprocessing, waste management, fuel and waste transportation; problem definition: characterization, measurement and monitoring, transport processes, health effects, ecological processes and effects, and integrated assessment; budget; characterization, measuring and monitoring program units; transport processes program units; health effects program units; ecological processes and effects program units; and integrated assessment program units

  8. TMI-2 [Three Mile Island] fission product inventory program: FY-85 status report

    International Nuclear Information System (INIS)

    Langer, S.; Croney, S.T.; Akers, D.W.; Russell, M.L.

    1986-11-01

    This report presents the status of the TMI-2 fission product inventory program through May 1985. The fission product inventory program is an assessment of the location of fission products distributed in the plant as a result of the TMI-2 accident. Included in this report are principal results of samples from the reactor building where most of the mobile fission products (i.e., radiocesium and iodine) are expected to be found. The data are now complete enough for most reactor components; therefore, it is possible to direct the balance of the examination and sampling program to areas and components where it is likely to be most productive. Those areas are the reactor core and the reactor building basement, with emphasis on the currently unsampled portions of the core

  9. Reference and standard benchmark field consensus fission yields for U.S. reactor dosimetry programs

    International Nuclear Information System (INIS)

    Gilliam, D.M.; Helmer, R.G.; Greenwood, R.C.; Rogers, J.W.; Heinrich, R.R.; Popek, R.J.; Kellogg, L.S.; Lippincott, E.P.; Hansen, G.E.; Zimmer, W.H.

    1977-01-01

    Measured fission product yields are reported for three benchmark neutron fields--the BIG-10 fast critical assembly at Los Alamos, the CFRMF fast neutron cavity at INEL, and the thermal column of the NBS Research Reactor. These measurements were carried out by participants in the Interlaboratory LMFBR Reaction Rates (ILRR) program. Fission product generation rates were determined by post-irradiation analysis of gamma-ray emission from fission activation foils. The gamma counting was performed by Ge(Li) spectrometry at INEL, ANL, and HEDL; the sample sent to INEL was also analyzed by NaI(Tl) spectrometry for Ba-140 content. The fission rates were determined by means of the NBS Double Fission Ionization Chamber using thin deposits of each of the fissionable isotopes. Four fissionable isotopes were included in the fast neutron field measurements; these were U-235, U-238, Pu-239, and Np-237. Only U-235 was included in the thermal neutron yield measurements. For the fast neutron fields, consensus yields were determined for three fission product isotopes--Zr-95, Ru-103, and Ba-140. For these fission product isotopes, a separately activated foil was analyzed by each of the three gamma counting laboratories. The experimental standard deviation of the three independent results was typically +- 1.5%. For the thermal neutron field, a consensus value for the Cs-137 yield was also obtained. Subsidiary fission yields are also reported for other isotopes which were studied less intensively (usually by only one of the participating laboratories). Comparisons with EBR-II fast reactor yields from destructive analysis and with ENDF/B recommended values are given

  10. Fission yeast mating-type switching: programmed damage and repair

    DEFF Research Database (Denmark)

    Egel, Richard

    2005-01-01

    Mating-type switching in fission yeast follows similar rules as in budding yeast, but the underlying mechanisms are entirely different. Whilst the initiating double-strand cut in Saccharomyces cerevisiae requires recombinational repair for survival, the initial damage in Schizosaccharomyces pombe...

  11. SIMS analysis: Development and evaluation program summary

    International Nuclear Information System (INIS)

    Groenewold, G.S.; Appelhans, A.D.; Ingram, J.C.; Delmore, J.E.; Dahl, D.A.

    1996-11-01

    This report provides an overview of the ''SIMS Analysis: Development and Evaluation Program'', which was executed at the Idaho National Engineering Laboratory from mid-FY-92 to the end of FY-96. It should be noted that prior to FY-1994 the name of the program was ''In-Situ SIMS Analysis''. This report will not go into exhaustive detail regarding program accomplishments, because this information is contained in annual reports which are referenced herein. In summary, the program resulted in the design and construction of an ion trap secondary ion mass spectrometer (IT-SIMS), which is capable of the rapid analysis of environmental samples for adsorbed surface contaminants. This instrument achieves efficient secondary ion desorption by use of a molecular, massive ReO 4 - primary ion particle. The instrument manages surface charge buildup using a self-discharging principle, which is compatible with the pulsed nature of the ion trap. The instrument can achieve high selectivity and sensitivity using its selective ion storage and MS/MS capability. The instrument was used for detection of tri-n-butyl phosphate, salt cake (tank cake) characterization, and toxic metal speciation studies (specifically mercury). Technology transfer was also an important component of this program. The approach that was taken toward technology transfer was that of component transfer. This resulted in transfer of data acquisition and instrument control software in FY-94, and ongoing efforts to transfer primary ion gun and detector technology to other manufacturers

  12. Status update on the NIFFTE high precision fission cross section measurement program

    International Nuclear Information System (INIS)

    Laptev, Alexander B.; Tovesson, Fredrik; Burgett, Eric; Greife, Uwe; Grimes, Steven; Heffner, Michael D.; Hertel, Nolan E.; Hill, Tony; Isenhower, Donald; Klay, Jennifer L.; Kornilov, Nickolay; Kudo, Ryuho; Loveland, Walter; Massey, Thomas; McGrath, Chris; Pickle, Nathan; Qu, Hai; Sharma, Sarvagya; Snyder, Lucas; Thornton, Tyler; Towell, Rusty S.; Watson, Shon

    2010-01-01

    The Neutron Induced Fission Fragment Tracking Experiment (NIFFTE) program has been underway for nearly two years. The program's mission is to measure fission cross sections of the primary fissionable and fissile materials ( 235 U, 239 Pu, 238 U) as well as the minor actinides across energies from approximately 50 keV up to 20 MeV with an absolute uncertainty of less than one percent while investigating energy ranges from below an eV to 600 MeV. This basic nuclear physics data is being reinvestigated to support the next generation power plants and a fast burner reactor program. Uncertainties in the fast, resolved and unresolved resonance regions in plutonium and other transuranics are extremely large, dominating safety margins in the next generation nuclear power plants and power plants of today. This basic nuclear data can be used to support all aspects of the nuciear renaissance. The measurement campaign is utilizing a Time Projection Chamber or TPC as the tool to measure these cross sections to these unprecedented levels. Unlike traditional fission cross section measurements using time-of-flight and a multiple fission foil configurations in which fission cross sections in relation to that of 235 U are performed, the TPC project uses time-of-flight and hydrogen as the benchmark cross section. Using the switch to hydrogen, a simple, smooth cross section that can be used which removes the uncertainties associated with the resolved and unresolved resonances in 235 U.

  13. Program summary. Nuclear waste management and fuel cycle programs

    International Nuclear Information System (INIS)

    1982-07-01

    This Program Summary Document describes the US Department of Energy (DOE) Nuclear Waste Management and Fuel Cycle Programs. Particular emphasis is given to near-term, specifically Fiscal Year (FY) 1982, activities. The overall objective of these programs will be achieved by the demonstration of: (1) safe radioactive waste management practices for storage and disposal of high-level waste and (2) advanced technologies necessary to close the nuclear fuel cycle on a schedule which would assure a healthy future for the development of nuclear power in this country

  14. Summary reports of activities under visiting research program (1993)

    International Nuclear Information System (INIS)

    1993-10-01

    The summary reports of activities under visiting research program in the Research Reactor Institute, Kyoto University, in fiscal year 1992 are included. In this report, 104 summaries of researches using the Kyoto University Reactor (KUR) and 9 summaries of the researches using the Kyoto University Critical Assembly (KUCA) are collected. (J.P.N.)

  15. Fission energy program of the U.S. Department of Energy. FY 1980

    International Nuclear Information System (INIS)

    1979-04-01

    This document presents the baseline implementation program plan as of January 1979 and is derived from the National Energy Plan and other major policy documents. The document discusses civilian nuclear power development, the policy for which has been established by the National Energy Plan of April 1977 and the National Energy Act of 1978. It derives the fission energy policy and program objectives from the National Energy Plan and Act, describes the overall program strategy, and presents the overall budget. The approach used in managing the program, including the program structure and methods used for program control, is explained. The civilian fission power development implementation programs are described in detail. Other considerations affecting civilian nuclear power development are also discussed

  16. ENDF/B-IV fission-product files: summary of major nuclide data

    International Nuclear Information System (INIS)

    England, T.R.; Schenter, R.E.

    1975-09-01

    The major fission-product parameters [sigma/sub th/, RI, tau/sub 1/2/, E-bar/sub β/, E-bar/sub γ/, E-bar/sub α/, decay and (n,γ) branching, Q, and AWR] abstracted from ENDF/B-IV files for 824 nuclides are summarized. These data are most often requested by users concerned with reactor design, reactor safety, dose, and other sundry studies. The few known file errors are corrected to date. Tabular data are listed by increasing mass number

  17. Executive summary of the Cryofracture demonstration program

    International Nuclear Information System (INIS)

    Loomis, G.; Osborne, D.; Ancho, M.

    1991-09-01

    This report provides an executive summary of the Cryofracture demonstration program performed at Nuclear Remedial Technologies Corporation under contract to EG ampersand G Idaho, Inc., for the Department of Energy (DOE). Cryofracture is a size-reducing process whereby objects are frozen whereby objects are frozen to liquid nitrogen temperatures and crushed in a large hydraulic press. Material at the cryogenic temperatures have low ductility and are easily size reduced by fracturing. The main application being investigated for the DOE is for retrieved buried and stored transuranic (TRU) waste. Six 55-gallon drums and six 2 ft x 2 ft x 8 ft boxes containing simulated waste with tracers were subjected to the Cryofracture process. Data was obtained on (a) cool-down time, (b) yield strength of the containers, (c) size distribution of the waste before and after the Cryofracture process, (d) volume reduction of the waste, and (e) sampling of air and surface dusts for spread of tracers to evaluate potential contamination spread. The Cryofracture process was compared to conventional shredders and detailed cost estimates were established for construction of a Cryofracture facility at the Idaho National Engineering Laboratory. Although cost estimates for conventional shredding are higher for Cryofracture, the potential for fire and explosion during conventional shredding would incur additional costs to preclude these events. These additional costs are unknown and would require considerable research and development. 4 refs., 6 figs., 7 tabs

  18. Summary Report for Online Schools and Programs

    Science.gov (United States)

    Colorado Department of Education, 2014

    2014-01-01

    Pursuant to State Law, the Colorado Department of Education, Office of Blended and Online Learning is required to prepare an annual summary report for submission. The passage of a later State House Bill repealed the annual requirement for the Summary Report and also the annual reporting mandates that were required of all online schools and…

  19. Fission energy program of the U. S. Department of Energy

    Energy Technology Data Exchange (ETDEWEB)

    1978-06-01

    The document describes programs managed by the Program Director for Nuclear Energy, Department of Energy, and under the cognizance of the Committee on Science and Technology, United States House of Representatives. The major portion of the document is concerned with civilian nuclear power development, the policy for which has been established by the National Energy Plan of April 1977, but it also includes descriptions of the space applications and naval reactor programs.

  20. Geothermal Energy Research and Development Program; Project Summaries

    Energy Technology Data Exchange (ETDEWEB)

    None

    1994-03-01

    This is an internal DOE Geothermal Program document. This document contains summaries of projects related to exploration technology, reservoir technology, drilling technology, conversion technology, materials, biochemical processes, and direct heat applications. [DJE-2005

  1. Summary of fission spectrum workshop held at the National Neutron Cross Section Center, Brookhaven National Laboratory, October 23, 1978

    International Nuclear Information System (INIS)

    Stewart, L.

    1979-03-01

    In response to an action by the Standards Subcommittee of the Cross Section Evaluation Working Group, a workshop was convened to determine the status of available information on prompt fission neutron spectra. The experimental data were reviewed and theoretical models were developed. The current ENDF/B fission neutron spectra files were summarized. Further work is currently under way, especially to provide a better theoretical tool to represent energy-dependent fission spectra. 5 references

  2. LASL analytical chemistry program for fissionable materials safeguards

    International Nuclear Information System (INIS)

    Jackson, D.D.; Marsh, S.F.

    1979-01-01

    Gas-solid reactions at elevated temperature, used previously to convert uranium in refractory forms to species readily soluble in acid, are being applied to thorium materials. A microgram-sensitive spectrophotometric method was developed for determining uranium and the LASL Automated Spectrophotometer has been modified to use it. The instrument now is functional for determining milligram amounts of plutonium, and milligram and microgram amounts of uranium. Construction of an automated controlled-potential-coulometric analyzer has been completed. It is giving design performance of 0.1% relative standard deviation for the determination of plutonium using a method developed especially for the instrument. A method has been developed for the microcomplexometric titration of uranium in its stable (VI) oxidation state. A color probe analyzer assembled for this titration also has been used for microcomplexometric titration of thorium. The present status of reference materials prepared for NBS and for the SALE program, as well as examples of working reference materials prepared for use with nondestructive analyzers, is given. The interlaboratory measured value of the 239 Pu half-life is 24,119 y. Just completed measurement of the half life of 241 Pu is 14.38 y. Measurement of the 240 Pu half life is in progress

  3. Nuclear fission and reactions

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    The nuclear fission research programs are designed to elucidate basic features of the fission process. Specifically, (1) factors determining how nucleons of a fissioning nucleus are distributed between two fission fragments, (2) factors determining kinetic energy and excitation energies of fragments, and (3) factors controlling fission lifetimes. To these ends, fission studies are reported for several heavy elements and include investigations of spontaneous and neutron-induced fission, heavy ion reactions, and high energy proton reactions. The status of theoretical research is also discussed. (U.S.)

  4. 1981 Magnetic-fusion theory program project summaries

    International Nuclear Information System (INIS)

    1982-02-01

    The theory program supports research projects at three different types of sites: DOE and other government laboratories, universities, and industrial contractors. This report is organized into three sections corresponding to the three types of sites and within each section is organized alphabetically by site name. Summaries of each program are given

  5. Summary report on focusing HTGR technology programs

    International Nuclear Information System (INIS)

    The program effort to focus technology development activities consists of work in three areas: the identification of Reference Plant Options; the identification of design data needs and supporting program requirements for these plants; and the development of management plans and tools consistent with the execution of candidate systems

  6. Satellite Power System (SPS) Program Summary

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-01

    The joint DOE/NASA SPS program has as its objective to achieve by the end of 1980 an initial understanding of the technical feasibility, economic practicability, and the social and environmental acceptability of the SPS concepts so that recommendations concerning program continuation can be made. The four major study areas include (1) systems definition; (2) environmental assessment; (3) societal assessment; and (4) comparative assessment of alternative energy systems. All the projects on the SPS program are listed and summarized for FY 1978. (WHK)

  7. FEMA Hazard Mitigation Grants Program Summary - API

    Data.gov (United States)

    Department of Homeland Security — The Hazard Mitigation Grant Program (HMGP, CFDA Number: 97.039) provides grants to States and local governments to implement long-term hazard mitigation measures...

  8. Summary of DOD Acquisition Program Audit Coverage

    National Research Council Canada - National Science Library

    2001-01-01

    This report will provide the DoD audit community with information to support their planning efforts and provide management with information on the extent of audit coverage of DoD acquisition programs...

  9. FEMA Hazard Mitigation Grants Program Summary

    Data.gov (United States)

    Department of Homeland Security — The Hazard Mitigation Grant Program (HMGP, CFDA Number: 97.039) provides grants to States and local governments to implement long-term hazard mitigation measures...

  10. Sea Turtle Research Program Summary Report

    National Research Council Canada - National Science Library

    1997-01-01

    The USACE Sea Turtle Research Program (STRP) was conducted to minimize the risk to sea turtle populations in channels along the southeast Atlantic region of the United States from hopper-dredging activities...

  11. Nuclear Waste Management Program summary document, FY 1981

    International Nuclear Information System (INIS)

    1980-03-01

    The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel

  12. Nuclear Waste Management Program summary document, FY 1981

    Energy Technology Data Exchange (ETDEWEB)

    Meyers, Sheldon

    1980-03-01

    The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel.

  13. Draft 1992 Resource Program : Summary Report.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1992-01-01

    The Resource Program is the Bonneville Power Administration's primary process for deciding how to meet future resource needs -- how much new resource development is needed by BPA, which types of resources to acquire and option, how to go about acquiring them, and how much to spend. The Northwest Power Planning Council completed a new Northwest Power Plan in 1991. This Draft Resource Program describes how BPA proposes to do its part to meet the Council's regional resource objectives.

  14. Systematic evaluation program, status summary report

    International Nuclear Information System (INIS)

    1983-01-01

    Status reports are presented on the systematic evaluation program for the Big Rock Point reactor, Dresden-1 reactor, Dresden-2 reactor, Ginna-1 reactor, Connecticut Yankee reactor, LACBWR reactor, Millstone-1 reactor, Oyster Creek-1 reactor, Palisades-1 reactor, San Onofre-1 reactor, and Rowe Yankee reactor

  15. Renewable energy water supply - Mexico program summary

    Energy Technology Data Exchange (ETDEWEB)

    Foster, R. [New Mexico State Univ., Las Cruces, NM (United States)

    1997-12-01

    This paper describes a program directed by the US Agency for International Development and Sandia National Laboratory which installed sustainable energy sources in the form of photovoltaic modules and wind energy systems in rural Mexico to pump water and provide solar distillation services. The paper describes the guidelines which appeared most responsible for success as: promote an integrated development program; install quality systems that develop confidence; instill local project ownership; train local industry and project developers; develop a local maintenance infrastructure; provide users training and operations guide; develop clear lines of responsibilities for system upkeep. The paper emphasizes the importance of training. It also presents much collected data as to the characteristics and performance of the installed systems.

  16. Heavy-section steel irradiation program summary

    International Nuclear Information System (INIS)

    Corwin, W.R.; Nanstad, R.K.; Iskander, S.K.; Haggag, F.M.

    1992-01-01

    Since a failure of the RPV carries the potential of major contamination release and severe accident, it is imperative to safe reactor operation to understand and be able to accurately predict failure models of the vessel material. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established with its primary goal to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties, of typical pressure vessel steels as they relate to light-water RPVs. The program includes the direct continuation of irradiation studies previously conducted within the Heavy-Section Steel Technology Program augmented by enhanced examinations of the accompanying microstructural changes. Effects of specimen size, material chemistry, product form and microstructure, irradiation fluence, flux, temperature and spectrum, and postirradiation annealing are being examined on a wide range of fracture properties including fracture toughness (K Ic and J Ic ), crack-arrest toughness (K Ia ), ductile tearing resistance (dJ/da), Charpy V-notch impact energy, dropweight nil-ductility temperature (NDT), and tensile properties. Models based on observations of radiation-induced microstructural changes using field ion and high-resolution transmission electron microscopy provide a firmer basis for extrapolating the measured changes in fracture properties to wider ranges of irradiation conditions. The principal materials examined within the HSSI Program are highcopper welds since their postirradiation properties are most frequently limiting in the continued safe operation of commercial RPVs. In addition, a limited effort will focus on stainless steel weld overlay cladding, typical of that used on the inner surface of RPVs, since its postirradiation fracture properties have the potential for strongly affecting the extension of small surface flaws during overcooling transients. (orig./GL)

  17. Ocean Margins Programs, Phase I research summaries

    Energy Technology Data Exchange (ETDEWEB)

    Verity, P. [ed.

    1994-08-01

    During FY 1992, the DOE restructured its regional coastal-ocean programs into a new Ocean Margins Program (OMP), to: Quantify the ecological and biogeochemical processes and mechanisms that affect the cycling, flux, and storage of carbon and other biogenic elements at the land/ocean interface; Define ocean-margin sources and sinks in global biogeochemical cycles, and; Determine whether continental shelves are quantitatively significant in removing carbon dioxide from the atmosphere and isolating it via burial in sediments or export to the interior ocean. Currently, the DOE Ocean Margins Program supports more than 70 principal and co-principal investigators, spanning more than 30 academic institutions. Research funded by the OMP amounted to about $6.9M in FY 1994. This document is a collection of abstracts summarizing the component projects of Phase I of the OMP. This phase included both research and technology development, and comprised projects of both two and three years duration. The attached abstracts describe the goals, methods, measurement scales, strengths and limitations, and status of each project, and level of support. Keywords are provided to index the various projects. The names, addresses, affiliations, and major areas of expertise of the investigators are provided in appendices.

  18. Robotics Technology Crosscutting Program. Technology summary

    International Nuclear Information System (INIS)

    1995-06-01

    The Robotics Technology Development Program (RTDP) is a needs-driven effort. A length series of presentations and discussions at DOE sites considered critical to DOE's Environmental Restoration and Waste Management (EM) Programs resulted in a clear understanding of needed robotics applications toward resolving definitive problems at the sites. A detailed analysis of the resulting robotics needs assessment revealed several common threads running through the sites: Tank Waste Retrieval (TWR), Contaminant Analysis Automation (CAA), Mixed Waste Operations (MWO), and Decontamination and Dismantlement (D and D). The RTDP Group also realized that some of the technology development in these four areas had common (Cross Cutting-CC) needs, for example, computer control and sensor interface protocols. Further, the OTD approach to the Research, Development, Demonstration, Testing, and Evaluation (RDDT and E) process urged an additional organizational breakdown between short-term (1--3 years) and long-term (3--5 years) efforts (Advanced Technology-AT). These factors lead to the formation of the fifth application area for Crosscutting and Advanced Technology (CC and AT) development. The RTDP is thus organized around these application areas -- TWR, CAA, MWO, D and D, and CC and AT -- with the first four developing short-term applied robotics. An RTDP Five-Year Plan was developed for organizing the Program to meet the needs in these application areas

  19. Robotics Technology Crosscutting Program. Technology summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Robotics Technology Development Program (RTDP) is a needs-driven effort. A length series of presentations and discussions at DOE sites considered critical to DOE`s Environmental Restoration and Waste Management (EM) Programs resulted in a clear understanding of needed robotics applications toward resolving definitive problems at the sites. A detailed analysis of the resulting robotics needs assessment revealed several common threads running through the sites: Tank Waste Retrieval (TWR), Contaminant Analysis Automation (CAA), Mixed Waste Operations (MWO), and Decontamination and Dismantlement (D and D). The RTDP Group also realized that some of the technology development in these four areas had common (Cross Cutting-CC) needs, for example, computer control and sensor interface protocols. Further, the OTD approach to the Research, Development, Demonstration, Testing, and Evaluation (RDDT and E) process urged an additional organizational breakdown between short-term (1--3 years) and long-term (3--5 years) efforts (Advanced Technology-AT). These factors lead to the formation of the fifth application area for Crosscutting and Advanced Technology (CC and AT) development. The RTDP is thus organized around these application areas -- TWR, CAA, MWO, D and D, and CC and AT -- with the first four developing short-term applied robotics. An RTDP Five-Year Plan was developed for organizing the Program to meet the needs in these application areas.

  20. Summary of NR Program Prometheus Efforts

    International Nuclear Information System (INIS)

    J Ashcroft; C Eshelman

    2006-01-01

    The Naval Reactors Program led work on the development of a reactor plant system for the Prometheus space reactor program. The work centered on a 200 kWe electric reactor plant with a 15-20 year mission applicable to nuclear electric propulsion (NEP). After a review of all reactor and energy conversion alternatives, a direct gas Brayton reactor plant was selected for further development. The work performed subsequent to this selection included preliminary nuclear reactor and reactor plant design, development of instrumentation and control techniques, modeling reactor plant operational features, development and testing of core and plant material options, and development of an overall project plan. Prior to restructuring of the program, substantial progress had been made on defining reference plant operating conditions, defining reactor mechanical, thermal and nuclear performance, understanding the capabilities and uncertainties provided by material alternatives, and planning non-nuclear and nuclear system testing. The mission requirements for the envisioned NEP missions cannot be accommodated with existing reactor technologies. Therefore concurrent design, development and testing would be needed to deliver a functional reactor system. Fuel and material performance beyond the current state of the art is needed. There is very little national infrastructure available for fast reactor nuclear testing and associated materials development and testing. Surface mission requirements may be different enough to warrant different reactor design approaches and development of a generic multi-purpose reactor requires substantial sacrifice in performance capability for each mission

  1. Implementation of a Thermodynamic Solver within a Computer Program for Calculating Fission-Product Release Fractions

    Science.gov (United States)

    Barber, Duncan Henry

    During some postulated accidents at nuclear power stations, fuel cooling may be impaired. In such cases, the fuel heats up and the subsequent increased fission-gas release from the fuel to the gap may result in fuel sheath failure. After fuel sheath failure, the barrier between the coolant and the fuel pellets is lost or impaired, gases and vapours from the fuel-to-sheath gap and other open voids in the fuel pellets can be vented. Gases and steam from the coolant can enter the broken fuel sheath and interact with the fuel pellet surfaces and the fission-product inclusion on the fuel surface (including material at the surface of the fuel matrix). The chemistry of this interaction is an important mechanism to model in order to assess fission-product releases from fuel. Starting in 1995, the computer program SOURCE 2.0 was developed by the Canadian nuclear industry to model fission-product release from fuel during such accidents. SOURCE 2.0 has employed an early thermochemical model of irradiated uranium dioxide fuel developed at the Royal Military College of Canada. To overcome the limitations of computers of that time, the implementation of the RMC model employed lookup tables to pre-calculated equilibrium conditions. In the intervening years, the RMC model has been improved, the power of computers has increased significantly, and thermodynamic subroutine libraries have become available. This thesis is the result of extensive work based on these three factors. A prototype computer program (referred to as SC11) has been developed that uses a thermodynamic subroutine library to calculate thermodynamic equilibria using Gibbs energy minimization. The Gibbs energy minimization requires the system temperature (T) and pressure (P), and the inventory of chemical elements (n) in the system. In order to calculate the inventory of chemical elements in the fuel, the list of nuclides and nuclear isomers modelled in SC11 had to be expanded from the list used by SOURCE 2.0. A

  2. PISCES Program: Summary of research, 1988

    International Nuclear Information System (INIS)

    1988-10-01

    This paper discusses the research of the PISCES Program. Topics discussed are: deuterium pumping by C-C composites and graphites; reduced particle recycling from grooved graphite surfaces; surface analysis of graphite tiles exposed in tokamaks; erosion behavior of redeposition layers from tokamaks (tokamakium); high temperature erosion of graphite; collaboration on TFTR probe measurements of implanted D; spectroscopic studies of carbon containing molecules; presheath profile measurements; biased limiter/divertor experiments; particle transport in the CCT tokamak edge plasma; and experimental studies of biased divertors and limiters. 26 refs., 23 figs

  3. FWP executive summaries: Basic energy sciences materials sciences programs

    Energy Technology Data Exchange (ETDEWEB)

    Samara, G.A.

    1996-02-01

    This report provides an Executive Summary of the various elements of the Materials Sciences Program which is funded by the Division of Materials Sciences, Office of Basic Energy Sciences, U.S. Department of Energy at Sandia National Laboratories, New Mexico.

  4. A Summary of the Naval Postgraduate School Research Program, 1982

    OpenAIRE

    Faculty of the Naval Postgraduate School

    1982-01-01

    Approved For Public Release; Distribution Unlimited This report contains 224 summaries on research projects which were carried out under funding to the Naval Postgraduate School Research Program. This research was carried out in the areas of Computer Science, Mathematics, Administrative Sciences, Operations Research, National Security Affairs, Physics and Chemistry, Electrical Engineering, Meterology, Aeronautics, Oceanography and Mechanical Engineering. The Table of Content...

  5. A Summary of the Naval Postgraduate School Research Program, 1981

    OpenAIRE

    Faculty of the Naval Postgraduate School

    1981-01-01

    Approved for public release; distribution unlimited. This report contains 230 summaries on research projects which were carried out under funding to the Naval Postgraduate School Research Program. This research was carried out in the areas of Computer Science, Mathematics, Administrative Sciences, Defense Resources Management, Operations Resear-h, National Security Affairs, Physics and Chemistry, Electrical Engineering, Meterology, Aeronautics, Oceanography and Mechanical...

  6. A Summary of the Naval Postgraduate School Research Program, 1983

    OpenAIRE

    Faculty of the Naval Postgraduate School

    1983-01-01

    Approved For Public Release; Distribution Unlimited This report contains 249 summaries on research projects which were carried out under funding to the Naval Postgraduate School Research Program. This research was carried out in the areas of Computer Science, Mathematics, Administrative Sciences, Operations Research, National Security Affairs, Physics, Electrical Engineering, Meterology, Aeronautics, Oceanography and Mechanical Engineering. The Table of Contents identifies t...

  7. A Summary of the Naval Postgraduate School Research Program, 1984

    OpenAIRE

    Faculty of the Naval Postgraduate School

    1984-01-01

    Approved for public release; distribution unlimited. This report contains 221 summaries on research projects which were carried out under funding to the Naval Postgraduate School Research Program. This research was carried out in the areas of Computer Science, Mathematics, Administrative Sciences, Operations Research, National Security Affairs, Physics, Electrical Engineering, Meterology, Aeronautics, Oceanography and Mechanical Engineering. The Table of Contents identifies ...

  8. Hanford Site performance summary: EM funded programs

    International Nuclear Information System (INIS)

    Edwards, C.

    1995-09-01

    Hanford performance at fiscal year end reflects a three percent unfavorable schedule variance ($46.3 million*) which was an improvement over August 1995 ($46.3 million for September versus $65.9 million for August) and is below established reporting thresholds (greater than 3 percent). The majority of the behind schedule condition (53 percent) is attributed to EM-40 (Office of Environmental Restoration [ER]) and is a result of late receipt of funds, procurement delays, and US Army Corps of Engineers (USACE) work planned but not accomplished. Other primary contributors to the behind schedule condition are associated with tank farm upgrades, high-level waste disposal and work for others (support to the US Department of Energy-Headquarters [DOE-HQ]). The remaining behind schedule condition is distributed throughout the remaining Hanford programs and do not share common causes. A breakdown of individuals listed on page 8

  9. In Situ Remediation Integrated Program: Technology summary

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    The In Situ Remediation Integrated Program (ISR IP) was instituted out of recognition that in situ remediation could fulfill three important criteria: significant cost reduction of cleanup by eliminating or minimizing excavation, transportation, and disposal of wastes; reduced health impacts on workers and the public by minimizing exposure to wastes during excavation and processing; and remediation of inaccessible sites, including: deep subsurfaces, in, under, and around buildings. Buried waste, contaminated soils and groundwater, and containerized wastes are all candidates for in situ remediation. Contaminants include radioactive wastes, volatile and non-volatile organics, heavy metals, nitrates, and explosive materials. The ISR IP intends to facilitate development of in situ remediation technologies for hazardous, radioactive, and mixed wastes in soils, groundwater, and storage tanks. Near-term focus is on containment of the wastes, with treatment receiving greater effort in future years. ISR IP is an applied research and development program broadly addressing known DOE environmental restoration needs. Analysis of a sample of 334 representative sites by the Office of Environmental Restoration has shown how many sites are amenable to in situ remediation: containment--243 sites; manipulation--244 sites; bioremediation--154 sites; and physical/chemical methods--236 sites. This needs assessment is focused on near-term restoration problems (FY93--FY99). Many other remediations will be required in the next century. The major focus of the ISR EP is on the long term development of permanent solutions to these problems. Current needs for interim actions to protect human health and the environment are also being addressed.

  10. In Situ Remediation Integrated Program: Technology summary

    International Nuclear Information System (INIS)

    1994-02-01

    The In Situ Remediation Integrated Program (ISR IP) was instituted out of recognition that in situ remediation could fulfill three important criteria: significant cost reduction of cleanup by eliminating or minimizing excavation, transportation, and disposal of wastes; reduced health impacts on workers and the public by minimizing exposure to wastes during excavation and processing; and remediation of inaccessible sites, including: deep subsurfaces, in, under, and around buildings. Buried waste, contaminated soils and groundwater, and containerized wastes are all candidates for in situ remediation. Contaminants include radioactive wastes, volatile and non-volatile organics, heavy metals, nitrates, and explosive materials. The ISR IP intends to facilitate development of in situ remediation technologies for hazardous, radioactive, and mixed wastes in soils, groundwater, and storage tanks. Near-term focus is on containment of the wastes, with treatment receiving greater effort in future years. ISR IP is an applied research and development program broadly addressing known DOE environmental restoration needs. Analysis of a sample of 334 representative sites by the Office of Environmental Restoration has shown how many sites are amenable to in situ remediation: containment--243 sites; manipulation--244 sites; bioremediation--154 sites; and physical/chemical methods--236 sites. This needs assessment is focused on near-term restoration problems (FY93--FY99). Many other remediations will be required in the next century. The major focus of the ISR EP is on the long term development of permanent solutions to these problems. Current needs for interim actions to protect human health and the environment are also being addressed

  11. Program summary for the Civilian Reactor Development Program

    International Nuclear Information System (INIS)

    1982-07-01

    This Civilian Reactor Development Program document has the prime purpose of summarizing the technical programs supported by the FY 1983 budget request. This section provides a statement of the overall program objectives and a general program overview. Section II presents the technical programs in a format intended to show logical technical interrelationships, and does not necessarily follow the structure of the formal budget presentation. Section III presents the technical organization and management structure of the program

  12. Energy-efficient buildings program evaluations. Volume 2: Evaluation summaries

    Energy Technology Data Exchange (ETDEWEB)

    Lee, A.D.; Mayi, D.; Edgemon, S.D.

    1997-04-01

    This document presents summaries of code and utility building program evaluations reviewed as the basis for the information presented in Energy-Efficient Buildings Program Evaluations, Volume 1: Findings and Recommendations, DOE/EE/OBT-11569, Vol. 1. The main purpose of this volume is to summarize information from prior evaluations of similar programs that may be useful background for designing and conducting an evaluation of the BSGP. Another purpose is to summarize an extensive set of relevant evaluations and provide a resource for program designers, mangers, and evaluators.

  13. MIxed Waste Integrated Program (MWIP): Technology summary

    International Nuclear Information System (INIS)

    1994-02-01

    The mission of the Mixed Waste Integrated Program (MWIP) is to develop and demonstrate innovative and emerging technologies for the treatment and management of DOE's mixed low-level wastes (MLLW) for use by its customers, the Office of Waste Operations (EM-30) and the Office of Environmental Restoration (EM-40). The primary goal of MWIP is to develop and demonstrate the treatment and disposal of actual mixed waste (MMLW and MTRU). The vitrification process and the plasma hearth process are scheduled for demonstration on actual radioactive waste in FY95 and FY96, respectively. This will be accomplished by sequential studies of lab-scale non-radioactive testing followed by bench-scale radioactive testing, followed by field-scale radioactive testing. Both processes create a highly durable final waste form that passes leachability requirements while destroying organics. Material handling technology, and off-gas requirements and capabilities for the plasma hearth process and the vitrification process will be established in parallel

  14. Summary: special waste form lysimeters - arid program

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  15. FY1983 HTGR summary level program plan

    International Nuclear Information System (INIS)

    1983-01-01

    The major focus and priority of the FY1983 HTGR Program is the development of the HTGR-SC/C Lead Project through one of the candidate lead utilities. Accordingly, high priority will be given to work described in WBS 04 for site and user specific studies toward the development of the Lead Project. Asessment of advanced HTGR systems will continue during FY1983 in accordance with the High Temperature Process Heat (HTPH) Concept Evaluation Plan. Within the context of that plan, the assessment of the monolithic HTPH concepts has been essentially completed in FY1982 and FY1983 activities and will be limited to documentation only. the major advanced HTGR systems efforts in FY1983 will be focused on the further definition of the Modular Reactor Systems concepts in both the reforming (MRS-R) and Steam Cycle/Cogeneration 9MRS-SC/C) configurations in WBS 41. The effort will concentrate upon key technical issues and trade studies oriented to reduction in expected cost and schedule duration. With regard to the latter, the most significant will be trade study addressing the degree of modularization of reactor plant structures. particular attention will be given to the confinement building which currently defines the critical path for construction

  16. Stripa Project - Summary of defined programs

    International Nuclear Information System (INIS)

    Carlsson, L.; Olsson, T.; Pusch, R.

    1980-11-01

    An international cooperation project, the Stripa Project, in the field of nuclear waste management has been established as an autonomous OECH/NEA project. The management of the project has been entrusted to the Divsion Nuclear Fuel Safety (KBS) of the Swedish Nuclear Fuel Supply Company (SKBF). Technical input and contribution of funds are given by the following countries: Canada, Finland, Japan, Sweden, Switzerland and the United States. The report summarizes the programs for investigations funded at this stage. A number of investigations of a geophysical, geochemical and hydraulic nature will be carried out in the boreholes and the drill cores will be mapped and analysed. Another experiment is with various tracers which represent all important types of radionuclides and will be introduced in the naturally flowing water in a single fissure in granite. The experiment will show how well sorption data from the laboratory can be used to predict radionuclide migration in the field with real surfaces and waters. The third project aims at the verification of the suitability of the buffer materials at real conditions on site. Highly compacted bentonite and mixtures of bentonite and quartz sand are proposed as buffer materials in final repositories for high-level radioactive wastes. (GB)

  17. TMI-2 accident evaluation program sample acquisition and examination plan. Executive summary

    International Nuclear Information System (INIS)

    Russell, M.L.; McCardell, R.K.; Broughton, J.M.

    1985-12-01

    The purpose of the TMI-2 Accident Evaluation Program Sample Acquisition and Examination (TMI-2 AEP SA and E) program is to develop and implement a test and inspection plan that completes the current-condition characterization of (a) the TMI-2 equipment that may have been damaged by the core damage events and (b) the TMI-2 core fission product inventory. The characterization program includes both sample acquisitions and examinations and in-situ measurements. Fission product characterization involves locating the fission products as well as determining their chemical form and determining material association

  18. USERDA computer program summaries. Numbers 177--239

    International Nuclear Information System (INIS)

    1975-10-01

    Since 1960 the Argonne Code Center has served as a U. S. Atomic Energy Commission information center for computer programs developed and used primarily for the solution of problems in nuclear physics, reactor design, reactor engineering and operation. The Center, through a network of registered installations, collects, validates, maintains, and distributes a library of these computer programs and publishes a compilation of abstracts describing them. In 1972 the scope of the Center's activities was officially expanded to include computer programs developed in all of the U. S. Atomic Energy Commission program areas and the compilation and publication of this report. The Computer Program Summary report contains summaries of computer programs at the specification stage, under development, being checked out, in use, or available at ERDA offices, laboratories, and contractor installations. Programs are divided into the following categories: cross section and resonance integral calculations; spectrum calculations, generation of group constants, lattice and cell problems; static design studies; depletion, fuel management, cost analysis, and reactor economics; space-independent kinetics; space--time kinetics, coupled neutronics--hydrodynamics--thermodynamics and excursion simulations; radiological safety, hazard and accident analysis; heat transfer and fluid flow; deformation and stress distribution computations, structural analysis and engineering design studies; gamma heating and shield design programs; reactor systems analysis; data preparation; data management; subsidiary calculations; experimental data processing; general mathematical and computing system routines; materials; environmental and earth sciences; space sciences; electronics and engineering equipment; chemistry; particle accelerators and high-voltage machines; physics; controlled thermonuclear research; biology and medicine; and data

  19. Fission 2009 4. International Workshop on Nuclear Fission and Fission Product Spectroscopy - Compilation of slides

    International Nuclear Information System (INIS)

    2009-01-01

    This conference is dedicated to the last achievements in experimental and theoretical aspects of the nuclear fission process. The topics include: mass, charge and energy distribution, dynamical aspect of the fission process, nuclear data evaluation, quasi-fission and fission lifetime in super heavy elements, fission fragment spectroscopy, cross-section and fission barrier, and neutron and gamma emission. This document gathers the program of the conference and the slides of the presentations

  20. Gas Research Institute research program summary: Goals and accomplishments

    International Nuclear Information System (INIS)

    1991-07-01

    Gas Research Institute's research and development programs pursue technologies that maximize the value of gas energy services while minimizing the cost of supplying and delivering gaseous fuels. Four program areas, Supply Options, End Use, Gas Operations, and Crosscutting Research, are described in the report, together with related project titles and numbers. Also included are summaries of 1990 research results, research collaboration and supported work, and patents and licensing agreements. Glossaries of budget and program terms and of acronyms and abbreviations often used in the GRI literature are added

  1. Summary reports of activities under visiting research program (1992)

    International Nuclear Information System (INIS)

    1992-09-01

    Now the summary report of activities under visiting research program in the Research Reactor Institute, Kyoto University, in fiscal year 1991 has been put in order and published. As compared with the past reports, in the report of this year, pages increased and the style changed, but this is due to the change of the method of adopting researches to that throughout one year from fiscal year 1991. So far one page was allotted to every subject, but this limit was relaxed according to the contents. This style is not yet fixed. As well known, discussion is going on about the way the research reactor and the Research Reactor Institute should be. As for this summary report, in order to receive the international evaluation, it was decided to publish the report in English from fiscal year 1992, and the Progress Report on the research by the Institute personnel is included in it. In this report, 98 summaries of the researches using the KUR and 15 summaries of the researches using the KUCA are collected. One summary which was not reported in fiscal year 1990 is added. (K.I.)

  2. Investigations of the natural fission reactor program. Progress report, October 1977--September 1978

    International Nuclear Information System (INIS)

    Cowan, G.A.; Norris, A.E.

    1978-10-01

    The U.S. study of the Oklo natural reactor began in 1973 with the principal objectives of understanding the processes that produced the reactor and that led to the retention of many of its products. Major facets of the program have been the chemical separation and mass spectrometric analysis of the reactor components and products, the petrological and mineralogical examination of samples taken from the reactor zones, and an interdisciplinary modeling of possible processes consistent with reactor physics, geophysics, and geochemistry. Most of the past work has been on samples taken within the reactor zones. Presently, these studies give greater emphasis to the measurement of mobile products in additional suites of samples collected peripherally and ''downstream'' from the reactor zones. This report summarizes the current status of research and the views of U.S. investigators, with particular reference to the extensive work of the French scientists, concerning the main features of the Oklo natural fission reactor. Also mentioned briefly is the U.S. search for natural fission reactors at other locations

  3. Biomass Program 2007 Program Peer Review - Thermochemical Conversion Platform Summary

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2009-10-27

    This document discloses the comments provided by a review panel at the U.S. Department of Energy Office of the Biomass Program Peer Review held on November 15-16, 2007 in Baltimore, MD and the Biomass Program Peer Review for the Thermochemical Platform, held on July 9th and 10th in Golden, Colorado.

  4. Review of fusion research program: historical summary and program projections

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, E.S.

    1976-09-01

    This report provides a brief review of the history and current status of fusion research in the United States. It also describes the Federally funded program aimed at the development of fusion reactors for electric power generation.

  5. TRAFIC, a computer program for calculating the release of metallic fission products from an HTGR core

    International Nuclear Information System (INIS)

    Smith, P.D.

    1978-02-01

    A special purpose computer program, TRAFIC, is presented for calculating the release of metallic fission products from an HTGR core. The program is based upon Fick's law of diffusion for radioactive species. One-dimensional transient diffusion calculations are performed for the coated fuel particles and for the structural graphite web. A quasi steady-state calculation is performed for the fuel rod matrix material. The model accounts for nonlinear adsorption behavior in the fuel rod gap and on the coolant hole boundary. The TRAFIC program is designed to operate in a core survey mode; that is, it performs many repetitive calculations for a large number of spatial locations in the core. This is necessary in order to obtain an accurate volume integrated release. For this reason the program has been designed with calculational efficiency as one of its main objectives. A highly efficient numerical method is used in the solution. The method makes use of the Duhamel superposition principle to eliminate interior spatial solutions from consideration. Linear response functions relating the concentrations and mass fluxes on the boundaries of a homogeneous region are derived. Multiple regions are numerically coupled through interface conditions. Algebraic elimination is used to reduce the equations as far as possible. The problem reduces to two nonlinear equations in two unknowns, which are solved using a Newton Raphson technique

  6. Biomass Program 2007 Program Peer Review - Feedstock Platform Summary

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2009-10-27

    This document discloses the comments provided by a review panel at the U.S. Department of Energy Office of the Biomass Program Peer Review held on November 15-16, 2007 in Baltimore, MD and the Feedstock Platform Portfolio Peer Review held on August 21st through 23rd in Washington D.C.

  7. Fission gas release from ThO2 and ThO2--UO2 fuels (LWBR development program)

    International Nuclear Information System (INIS)

    Goldberg, I.; Spahr, G.L.; White, L.S.; Waldman, L.A.; Giovengo, J.F.; Pfennigwerth, P.L.; Sherman, J.

    1978-08-01

    Fission gas release data are presented from 51 fuel rods irradiated as part of the LWBR irradiations test program. The fuel rods were Zircaloy-4 clad and contained ThO 2 or ThO 2 -UO 2 fuel pellets, with UO 2 compositions ranging from 2.0 to 24.7 weight percent and fuel densities ranging from 77.8 to 98.7 percent of theoretical. Rod diameters ranged from 0.25 to 0.71 inches and fuel active lengths ranged from 3 to 84 inches. Peak linear power outputs ranged from 2 to 22 kw/ft for peak fuel burnups up to 56,000 MWD/MTM. Measured fission gas release was quite low, ranging from 0.1 to 5.2 percent. Fission gas release was higher at higher temperature and burnup and was lower at higher initial fuel density. No sensitivity to UO 2 composition was evidenced

  8. Solar buildings program contract summary, calendar year 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-06-07

    The mission of the US Department of Energy's Solar Buildings Program is to advance the development and widespread deployment of competitive solar thermal technologies for use in buildings. The long-term goal of the Program is to combine solar energy technologies with energy-efficient construction techniques and create cost-effective buildings that have a zero net need for fossil fuel energy on an annual basis. The Solar Buildings Program conducts research and development on solar technologies that can deliver heat, light, and hot water to residential and commercial buildings. By working closely with manufacturers in both the buildings and solar energy industries and by supporting research at universities and national laboratories, the Solar Buildings Program brings together the diverse players developing reliable and affordable solar technologies for building applications. The National Renewable Energy Laboratory (NREL) in Golden, Colorado, and Sandia National Laboratories (SNL) in Albuquerque, New Mexico, jointly participate in the Solar Buildings Program. These two national laboratories work closely with industry researching new concepts, developing technology improvements, reducing manufacturing costs, monitoring system performance, promoting quality assurance, and identifying potential new markets. In calendar year 1999, the Solar Buildings Program focused primarily on solar hot water system research and development (R and D), US industry manufacturing assistance, and US market assistance. The Program also completed a number of other projects that were begun in earlier years. This Contract Summary describes the Program's contracted activities that were active during 1999.

  9. Ocean Thermal Energy Conversion (OTEC) program. FY 1977 program summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    An overview is given of the ongoing research, development, and demonstration efforts. Each of the DOE's Ocean Thermal Energy Conversion projects funded during fiscal year 1977 (October 1, 1976 through September 30, 1977) is described and each project's status as of December 31, 1977 is reflected. These projects are grouped as follows: program support, definition planning, engineering development, engineering test and evaluation, and advanced research and technology. (MHR)

  10. Strengthening the fission reactor nuclear science and engineering program at UCLA. Final technical report

    International Nuclear Information System (INIS)

    Okrent, D.

    1997-01-01

    This is the final report on DOE Award No. DE-FG03-92ER75838 A000, a three year matching grant program with Pacific Gas and Electric Company (PG and E) to support strengthening of the fission reactor nuclear science and engineering program at UCLA. The program began on September 30, 1992. The program has enabled UCLA to use its strong existing background to train students in technological problems which simultaneously are of interest to the industry and of specific interest to PG and E. The program included undergraduate scholarships, graduate traineeships and distinguished lecturers. Four topics were selected for research the first year, with the benefit of active collaboration with personnel from PG and E. These topics remained the same during the second year of this program. During the third year, two topics ended with the departure o the students involved (reflux cooling in a PWR during a shutdown and erosion/corrosion of carbon steel piping). Two new topics (long-term risk and fuel relocation within the reactor vessel) were added; hence, the topics during the third year award were the following: reflux condensation and the effect of non-condensable gases; erosion/corrosion of carbon steel piping; use of artificial intelligence in severe accident diagnosis for PWRs (diagnosis of plant status during a PWR station blackout scenario); the influence on risk of organization and management quality; considerations of long term risk from the disposal of hazardous wastes; and a probabilistic treatment of fuel motion and fuel relocation within the reactor vessel during a severe core damage accident

  11. In Situ Remediation Integrated Program: FY 1994 program summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    The US Department of Energy (DOE) established the Office of Technology Development (EM-50) as an element of the Office of Environmental Management (EM) in November 1989. In an effort to focus resources and address priority needs, EM-50 introduced the concept of integrated programs (IPs) and integrated demonstrations (IDs). The In Situ Remediation Integrated Program (ISR IP) focuses research and development on the in-place treatment of contaminated environmental media, such as soil and groundwater, and the containment of contaminants to prevent the contaminants from spreading through the environment. Using in situ remediation technologies to clean up DOE sites minimizes adverse health effects on workers and the public by reducing contact exposure. The technologies also reduce cleanup costs by orders of magnitude. This report summarizes project work conducted in FY 1994 under the ISR IP in three major areas: treatment (bioremediation), treatment (physical/chemical), and containment technologies. Buried waste, contaminated soils and groundwater, and containerized waste are all candidates for in situ remediation. Contaminants include radioactive waste, volatile and nonvolatile organics, heavy metals, nitrates, and explosive materials.

  12. In Situ Remediation Integrated Program: FY 1994 program summary

    International Nuclear Information System (INIS)

    1995-04-01

    The US Department of Energy (DOE) established the Office of Technology Development (EM-50) as an element of the Office of Environmental Management (EM) in November 1989. In an effort to focus resources and address priority needs, EM-50 introduced the concept of integrated programs (IPs) and integrated demonstrations (IDs). The In Situ Remediation Integrated Program (ISR IP) focuses research and development on the in-place treatment of contaminated environmental media, such as soil and groundwater, and the containment of contaminants to prevent the contaminants from spreading through the environment. Using in situ remediation technologies to clean up DOE sites minimizes adverse health effects on workers and the public by reducing contact exposure. The technologies also reduce cleanup costs by orders of magnitude. This report summarizes project work conducted in FY 1994 under the ISR IP in three major areas: treatment (bioremediation), treatment (physical/chemical), and containment technologies. Buried waste, contaminated soils and groundwater, and containerized waste are all candidates for in situ remediation. Contaminants include radioactive waste, volatile and nonvolatile organics, heavy metals, nitrates, and explosive materials

  13. Summary of the Manufacture, Testing and Model Validation of a Full-Scale Radiator for Fission Surface Power Applications

    Science.gov (United States)

    Ellis, David L.; Calder, James; Siamidis, John

    2011-01-01

    A full-scale radiator for a lunar fission surface power application was manufactured by Material innovations, Inc., for the NASA Glenn Research Center. The radiator was designed to reject 6 kWt with an inlet water temperature of 400 K and a water mass flow rate of 0.5 kg/s. While not flight hardware, the radiator incorporated many potential design features and manufacturing techniques for future flight hardware. The radiator was tested at NASA Glenn Research Center for heat rejection performance. The results showed that the radiator design was capable of rejecting over 6 kWt when operating at the design conditions. The actual performance of the radiator as a function of operational manifolds, inlet water temperature and facility sink temperature was compared to the predictive model developed by NASA Glenn Research Center. The results showed excellent agreement with the model with the actual average face sheet temperature being within 1% of the predicted value. The results will be used in the design and production of NASA s next generation fission power heat rejection systems. The NASA Glenn Research Center s Technology Demonstration Unit will be the first project to take advantage of the newly developed manufacturing techniques and analytical models.

  14. Summaries of the Idaho National Engineering Laboratory Radioecology and Ecology Program research projects

    International Nuclear Information System (INIS)

    Markham, O.D.

    1987-06-01

    This report provides summaries of individual research projects conducted by the Idaho National Engineering Laboratory Radioecology and Ecology Program. Summaries include projects in various stages, from those that are just beginning, to projects that are in the final publication stage

  15. Summary of the Semiscale Program, 1965-1986

    International Nuclear Information System (INIS)

    Loomis, G.G.

    1987-07-01

    This document summarizes significant results from the Semiscale Program, which examined pressurized water reactor (PWR) safety issues from 1965 to 1986. Most of these issues were related to plant response during loss-of-coolant accidents and operational transients. The Semiscale program utilized a series of non-nuclear, scaled, PWR plant simulators to provide thermal-hydraulic data at prototypical pressures and temperatures for a wide range of nuclear safety issues. Presented are: a historical perspective of the Semiscale Program relative to reactor safety with a catalog of the Semiscale experimental facilities and data bases, the relationship of Semiscale results to 10 CFR Part 50 (Appendix K), the impact of Semiscale results on scaling experimental results to full sized operating plants, a summary of safety issues that were addressed by Semiscale testing as they arose throughout the operational lifetime of Semiscale, the contributions of the Semiscale Program to safety technology, a description of phenomena observed during Semiscale testing, the impact of Semiscale data on code development and assessment, the applicability of the Semiscale data base for code development and assessment, and finally, major conclusions and accomplishments of the Semiscale program

  16. Constellation Program: Lessons Learned. Volume 1; Executive Summary

    Science.gov (United States)

    Rhatigan, Jennifer L. (Editor)

    2011-01-01

    This document (Volume I) provides an executive summary of the lessons learned from the Constellation Program. A companion Volume II provides more detailed analyses for those seeking further insight and information. In this volume, Section 1.0 introduces the approach in preparing and organizing the content to enable rapid assimilation of the lessons. Section 2.0 describes the contextual framework in which the Constellation Program was formulated and functioned that is necessary to understand most of the lessons. Context of a former program may seem irrelevant in the heady days of new program formulation. However, readers should take some time to understand the context. Many of the lessons would be different in a different context, so the reader should reflect on the similarities and differences in his or her current circumstances. Section 3.0 summarizes key findings developed from the significant lessons learned at the program level that appear in Section 4.0. Readers can use the key findings in Section 3.0 to peruse for particular topics, and will find more supporting detail and analyses in Section 4.0 in a topical format. Appendix A contains a white paper describing the Constellation Program formulation that may be of use to readers wanting more context or background information. The reader will no doubt recognize some very similar themes from previous lessons learned, blue-ribbon committee reviews, National Academy reviews, and advisory panel reviews for this and other large-scale human spaceflight programs; including Apollo, Space Shuttle, Shuttle/Mir, and the ISS. This could represent an inability to learn lessons from previous generations; however, it is more likely that similar challenges persist in the Agency structure and approach to program formulation, budget advocacy, and management. Perhaps the greatest value of these Constellation lessons learned can be found in viewing them in context with these previous efforts to guide and advise the Agency and its

  17. Delayed fission

    Energy Technology Data Exchange (ETDEWEB)

    Hatsukawa, Yuichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-07-01

    Delayed fission is a nuclear decay process that couples {beta} decay and fission. In the delayed fission process, a parent nucleus undergoes {beta} decay and thereby populates excited states in the daughter. If these states are of energies comparable to or greater than the fission barrier of the daughter, then fission may compete with other decay modes of the excited states in the daughter. In this paper, mechanism and some experiments of the delayed fission will be discussed. (author)

  18. Mirror fusion--fission hybrids

    International Nuclear Information System (INIS)

    Lee, J.D.

    1978-01-01

    The fusion-fission concept and the mirror fusion-fission hybrid program are outlined. Magnetic mirror fusion drivers and blankets for hybrid reactors are discussed. Results of system analyses are presented and a reference design is described

  19. High temperature fission chambers. Fast breeder reactor research and development program

    International Nuclear Information System (INIS)

    Berlin, C.; Perrigueur, J.C.

    1984-04-01

    Development of a high temperature fission chamber and experimentations of measuring channels (detectors and electronic devices) in similar conditions as those of power plants: development of measuring channels (impulses and current) of the Super Phenix neutronic measures auxiliary system, development of a measuring channel with impulses for the surveillance system of the clad failures, based on integrated detectors, and development of a fission chamber for experimentations in similar conditions as in Superphenix [fr

  20. Summary reports of activities under visiting research program

    International Nuclear Information System (INIS)

    1985-01-01

    This report is published any time by summarizing in the form of an interim report the data required for research and experiment such as the results of the functional test on various experimental facilities, the test results of the products manufactured for trial, the state of radiation control and waste management, and the report of study meetings in the Research Reactor Institute, Kyoto University, the conspicuous results obtained halfway in research, new techniques, discussion on other papers and reports and others. In this report, the gists of 71 papers on the research activities under visiting research program performed in the second half of 1984 are collected, and the subject number, the title of research reporters, and the summary of report for each research are given. (Kako, I.)

  1. Future research program on prompt γ-ray emission in nuclear fission

    Science.gov (United States)

    Oberstedt, S.; Billnert, R.; Hambsch, F.-J.; Lebois, M.; Oberstedt, A.; Wilson, J. N.

    2015-12-01

    In recent years the measurement of prompt fission γ-ray spectra (PFGS) has gained renewed interest, after about forty years since the first comprehensive studies of the reactions 235U(n th , f), 239Pu(n th ,f) and 252Cf(sf). The renaissance was initiated by requests for new values especially for γ-ray multiplicity and average total energy release per fission in neutron-induced fission of 235U and 239Pu. Both isotopes are considered the most important ones with respect to the modeling of innovative cores required for the Generation-IV reactors, the majority working with fast neutrons. During the last 5 years we have conducted a systematic study of spectral data for thermal-neutron-induced fission on 235U and 241Pu as well as for the spontaneous fission of 252Cf with unprecedented accuracy. From the new data we conclude that those reactions do not considerably contribute to the observed heat excess and suspect other reactions playing a significant role. Possible contributions may originate from fast-neutron-induced reactions on 238U, which is largely present in the fuel, or from γ-induced fission from neutron capture in the construction material. A first experiment campaign on prompt γ-ray emission from fast-neutron-induced fission on 235,238U was successfully performed in order to test our assumptions. In the following we attempt to summarize, what has been done in the field to date, and to motivate future measurement campaigns exploiting dedicated neutron and photon beams as well as upcoming highly efficient detector assemblies.

  2. Future research program on prompt γ-ray emission in nuclear fission

    Energy Technology Data Exchange (ETDEWEB)

    Oberstedt, S.; Hambsch, F.J. [Joint Research Centre IRMM, European Commission, Geel (Belgium); Billnert, R. [Joint Research Centre IRMM, European Commission, Geel (Belgium); Chalmers Tekniska Hoegskola, Fundamental Fysik, Goeteborg (Sweden); Lebois, M.; Wilson, J.N. [Institut de Physique Nucleaire Orsay, Orsay (France); Oberstedt, A. [Chalmers Tekniska Hoegskola, Fundamental Fysik, Goeteborg (Sweden); Ossolution Consulting, Oerebro (Sweden)

    2015-12-15

    In recent years the measurement of prompt fission γ-ray spectra (PFGS) has gained renewed interest, after about forty years since the first comprehensive studies of the reactions {sup 235}U(n{sub th}, f), {sup 239}Pu(n{sub th},f) and {sup 252}Cf(sf). The renaissance was initiated by requests for new values especially for γ-ray multiplicity and average total energy release per fission in neutron-induced fission of {sup 235}U and {sup 239}Pu. Both isotopes are considered the most important ones with respect to the modeling of innovative cores required for the Generation-IV reactors, the majority working with fast neutrons. During the last 5 years we have conducted a systematic study of spectral data for thermal-neutron-induced fission on {sup 235}U and {sup 241}Pu as well as for the spontaneous fission of {sup 252}Cf with unprecedented accuracy. From the new data we conclude that those reactions do not considerably contribute to the observed heat excess and suspect other reactions playing a significant role. Possible contributions may originate from fast-neutron-induced reactions on {sup 238}U, which is largely present in the fuel, or from γ-induced fission from neutron capture in the construction material. A first experiment campaign on prompt γ-ray emission from fast-neutron-induced fission on {sup 235,238}U was successfully performed in order to test our assumptions. In the following we attempt to summarize, what has been done in the field to date, and to motivate future measurement campaigns exploiting dedicated neutron and photon beams as well as upcoming highly efficient detector assemblies. (orig.)

  3. Nez Perce Tribal Hatchery Program: Draft environmental impact statement. Summary

    International Nuclear Information System (INIS)

    1996-06-01

    This summary gives the major points of the Draft Environmental Impact Statement (EIS) prepared for the Nez Perce Tribal Hatchery by the Nez Perce Tribe (NPT), the Bonneville Power Administration (BPA), the Bureau of Indian Affairs (BIA), and other interested parties. The Nez Perce once were one of the largest Plateau tribes in the Northwest and occupied a territory that included north central Idaho, southeastern Washington and northeastern Oregon. Salmon and other migratory fish species are an invaluable food resource and an integral part of the Nez Perce Tribe's culture. Anadromous fish have always made up the bulk of the Nez Perce tribal diet and this dependence on salmon was recognized in the treaties made with the Tribe by the US. The historic economic, social, and religious significance of the fish to the Nez Perce Tribe continues to this day, which makes the decline of fish populations in the Columbia River Basin a substantial detrimental impact to the Nez Perce way of life. The Nez Perce Tribal Hatchery is a supplementation program that would rear and release spring, summer, and fall chinook (Oncorhynchus tshawytscha), biologically similar to wild fish, to reproduce in the Clearwater River Subbasin. Program managers propose techniques that are compatible with existing aquatic and riparian ecosystems and would integrate hatchery-produced salmon into the stream and river environments needed to complete their life cycle

  4. Nez Perce Tribal Hatchery Program : Draft Environmental Impact Statement Summary.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration; Nez Perce Tribal Hatchery (Idaho)

    1996-06-01

    This summary gives the major points of the Draft Environmental Impact Statement (EIS) prepared for the Nez Perce Tribal Hatchery by the Nez Perce Tribe (NPT), the Bonneville Power Administration (BPA), the Bureau of Indian Affairs (BIA), and other interested parties. The Nez Perce once were one of the largest Plateau tribes in the Northwest and occupied a territory that included north central Idaho, southeastern Washington and northeastern Oregon. Salmon and other migratory fish species are an invaluable food resource and an integral part of the Nez Perce Tribe`s culture. Anadromous fish have always made up the bulk of the Nez Perce tribal diet and this dependence on salmon was recognized in the treaties made with the Tribe by the US. The historic economic, social, and religious significance of the fish to the Nez Perce Tribe continues to this day, which makes the decline of fish populations in the Columbia River Basin a substantial detrimental impact to the Nez Perce way of life. The Nez Perce Tribal Hatchery is a supplementation program that would rear and release spring, summer, and fall chinook (Oncorhynchus tshawytscha), biologically similar to wild fish, to reproduce in the Clearwater River Subbasin. Program managers propose techniques that are compatible with existing aquatic and riparian ecosystems and would integrate hatchery-produced salmon into the stream and river environments needed to complete their life cycle.

  5. Summary of ORNL high-temperature gas-cooled reactor program

    International Nuclear Information System (INIS)

    Kasten, P.R.

    1981-01-01

    Oak Ridge National Laboratory (ORNL) efforts on the High-Temperature Gas-Cooled Reactor (HTGR) Program have been on HTGR fuel development, fission product and coolant chemistry, prestressed concrete reactor vessel (PCRV) studies, materials studies, graphite development, reactor physics and shielding studies, application assessments and evaluations and selected component testing

  6. Elements to be considered in planning heavy ion fusion program: a summary

    International Nuclear Information System (INIS)

    Bohachevsky, I.O.

    1978-01-01

    A summary of Battelle's Engineering Development Program Plan for inertial confinement fusion is presented. Included are development objectives, facilities to achieve these objectives, program strategies, and a discussion of heavy-ion driver development

  7. GRSIS program to predict fission gas release and swelling behavior of metallic fast reactor fuel

    International Nuclear Information System (INIS)

    Lee, Chan Bock; Lee, Byung Ho; Nam, Cheol; Sohn, Dong Seong

    1999-03-01

    A mechanistic model of fission gas release and swelling for the U-(Pu)-Zr metallic fuel in the fast reactor, GRSIS (Gas Release and Swelling in ISotropic fuel matrix) was developed. Fission gas bubbles are assumed to nucleate isotropically from the gas atoms in the metallic fuel matrix since they can nucleate at both the grain boundaries and the phase boundaries which are randomly distributed inside the grain. Bubbles can grow to larger size by gas diffusion and coalition with other bubbles so that they are classified as three classes depending upon their sizes. When bubble swelling reaches the threshold value, bubbles become interconnected each other to make the open channel to the external free space, that is, the open bubbles and then fission gases inside the interconnected open bubbles are released instantaneously. During the irradiation, fission gases are released through the open bubbles. GRSIS model can take into account the fuel gap closure by fuel bubble swelling. When the fuel gap is closed by fuel swelling, the contact pressure between fuel and cladding in relation to the bubble swelling and temperature is calculated. GRSIS model was validated by comparison with the irradiation test results of U-(Pu)-Zr fuels in ANL as well as the parametric studies of the key variable in the model. (author). 13 refs., 1 tab., 22 figs

  8. GRSIS program to predict fission gas release and swelling behavior of metallic fast reactor fuel

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chan Bock; Lee, Byung Ho; Nam, Cheol; Sohn, Dong Seong

    1999-03-01

    A mechanistic model of fission gas release and swelling for the U-(Pu)-Zr metallic fuel in the fast reactor, GRSIS (Gas Release and Swelling in ISotropic fuel matrix) was developed. Fission gas bubbles are assumed to nucleate isotropically from the gas atoms in the metallic fuel matrix since they can nucleate at both the grain boundaries and the phase boundaries which are randomly distributed inside the grain. Bubbles can grow to larger size by gas diffusion and coalition with other bubbles so that they are classified as three classes depending upon their sizes. When bubble swelling reaches the threshold value, bubbles become interconnected each other to make the open channel to the external free space, that is, the open bubbles and then fission gases inside the interconnected open bubbles are released instantaneously. During the irradiation, fission gases are released through the open bubbles. GRSIS model can take into account the fuel gap closure by fuel bubble swelling. When the fuel gap is closed by fuel swelling, the contact pressure between fuel and cladding in relation to the bubble swelling and temperature is calculated. GRSIS model was validated by comparison with the irradiation test results of U-(Pu)-Zr fuels in ANL as well as the parametric studies of the key variable in the model. (author). 13 refs., 1 tab., 22 figs.

  9. Assessment of the high temperature fission chamber technology for the French fast reactor program

    Energy Technology Data Exchange (ETDEWEB)

    Jammes, C.; Filliatre, P.; Geslot, B.; Domenech, T.; Normand, S. [Commissariat a l' Energie Atomique, CEA (France)

    2011-07-01

    High temperature fission chambers are key instruments for the control and protection of the sodium-cooled fast reactor. First, the developments of those neutron detectors, which are carried out either in France or abroad are reviewed. Second, the French realizations are assessed with the use of the technology readiness levels in order to identify tracks of improvement. (authors)

  10. The LANL/LLNL Program to Measure Prompt Fission Neutron Spectra at LANSCE

    Science.gov (United States)

    Haight, Robert; Wu, Ching Yen; Lee, Hye Young; Taddeucci, Terry; Mosby, Shea; O'Donnell, John; Fotiades, Nikolaos; Devlin, Mattew; Ullmann, John; Nelson, Ronald; Wender, Stephen; White, Morgan; Solomon, Clell; Neudecker, Denise; Talou, Patrick; Rising, Michael; Bucher, Brian; Buckner, Matthew; Henderson, Roger

    2015-10-01

    Accurate data on the spectrum of neutrons emitted in neutron-induced fission are needed for applications and for a better understanding of the fission process. At LANSCE we have made important progress in understanding systematic uncertainties and in obtaining data for 235U on the low-energy part of the prompt fission neutron spectra (PFNS), a particularly difficult region because down-scattered neutrons go in this direction. We use a double time-of-flight technique to determine energies of incoming and outgoing neutrons. With data acquisition via waveform digitizers, accidental coincidences between fission chamber and neutron detector are measured to high statistical accuracy and then subtracted from measured events. Monte Carlo simulations with high performance computers have proven to be essential in the design to minimize neutron scattering and in calculating detector response. Results from one of three approaches to analyzing the data will be presented. This work is funded by the US Department of Energy, National Nuclear Security Administration and Office of Nuclear Physics.

  11. Summary reports of activities under visiting research program

    International Nuclear Information System (INIS)

    1984-01-01

    Technical Report of the Research Reactor Institute, Kyoto University, is published any time as a prompt report as occasion requires. In this report, the title, names of reporters and summary of each of 53 researches which were carried out under the visiting research program in the first half of 1983 are given. The titles are, for example, a mechanism for the anodic oxidation of GaAs, gamma-gamma perturbed angular correlation study of relaxation phenomena, the studies on the genesis of volcanic rocks by partition of trace elements, neutron activation analysis of geochemical standard rock samples, studies on the changes of elements in the fur of rats with various disease, neutron activation analysis on glacier ice strata and glaciegla lake sediments in Nepal Himalayas, low temperature irradiation effects on bcc metals, organ and its subcellular distribution of manganese ion in animals, structure analysis of orthorhombic BaTiO 3 by profile analysis method, regional distribution of Mn, Zn and Cu in human brain, neutron diffraction study of Mn-Ni alloy, structural change of KCoF 3 in the vicinity of the critical region, activation analysis of trace elements in tumor tissues (thyroid) and so on. (Kako, I.)

  12. Expanded BPA residential weatherization program: summary of regional health effects

    International Nuclear Information System (INIS)

    Sandusky, W.F.; Thor, P.W.; Alton, C.C.; Mellinger, P.J.; Cross, F.T.

    1984-11-01

    The Final Environmental Impact Statement (FEIS) for the Bonneville Power Administration (BPA) Expanded Residential Weatherization Program has been completed, printed, and distributed. This document incorporates numerous revisions based on both oral and written comments received during the public comment of the Draft Environmental Impact Statement (DEIS). The estimates of regional health effects were revised to incorporate results of the second Pacific Northwest Residential Energy Survey (PNWRES). The FEIS now expresses the estimated regional health effects in terms of incidence of cancers per 100,000 people exposed, which allows comparison to be made to the annual average risk of fatality by other causes. The estimates of regional health effects are also compared to health effects resulting from supplying and operating a conventional coal plant at a power level equal to the amount of energy saved from installation of additional tightening measures. Numerical results for the estimated health effects described above are provided. A summary of the comments received on the DEIS is also provided, along with estimated health effects associated with the Environmentally Preferred and BPA Preferred Alternatives to the Proposed Action. 8 refs., 3 figs., 5 tabs

  13. Summary of the Nevada Applied Ecology Group and correlative programs

    International Nuclear Information System (INIS)

    Friesen, H.N.

    1992-10-01

    This summary document presents results in a broad context; it is not limited to findings of the Nevada Applied Ecology Group. This book is organized to present the findings of the Nevada Applied Ecology Group and correlative programs in accordance with the originally stated objectives of the Nevada Applied Ecology Group. This plan, in essence, traces plutonium from its injection into the environment to movement in the ecosystem to development of cleanup techniques. Information on other radionuclides was also obtained and will be presented briefly. Chapter 1 presents a brief description of the ecological setting of the Test Range Complex. The results of investigations for plutonium distribution are presented in Chapter 2 for the area surrounding the Test Range Complex and in Chapter 3 for on-site locations. Chapters 4 and 5 present the results of investigations concerned with concentrations and movement, respectively, of plutonium in the ecosystem of the Test Range Complex, and Chapter 6 summarizes the potential hazard from this plutonium. Development of techniques for cleanup and treatment is presented in Chapter 7, and the inventory of radionuclides other than plutonium is presented briefly in Chapter 8

  14. Summary of sodium removal and decontamination programs in the USA

    International Nuclear Information System (INIS)

    Steele, O.P.; Brehm, W.F.

    1978-01-01

    The goals of the United States Department of Energy sodium removal and decontamination programs are: 1) to identify plant requirements and develop safe effective processes for sodium removal, both for experimental facilities and for reactor components; 2) to develop effective decontamination processes for removing deposited radioactivity; 3) to establish and put into use a set of workable criteria for requalification and return to service of components after sodium removal and decontamination; 4) to design, build and operate facilities in which to perform the sodium removal and decontamination operations. This paper gives a summary of progress toward each of these goals; details will be presented in other papers at this meeting. Three basic processes for sodium removal have been investigated extensively: the use of water vapor in an inert carrier gas, the use of an alcohol-type reagent, and evaporation. The process development work on the first two processes has been essentially completed. The evaporative process is still under development, but preliminary parameters have been established

  15. Geothermal energy program summary: Volume 1: Overview Fiscal Year 1988

    Science.gov (United States)

    1989-02-01

    Geothermal energy is a here-and-now technology for use with dry steam resources and high-quality hydrothermal liquids. These resources are supplying about 6 percent of all electricity used in California. However, the competitiveness of power generation using lower quality hydrothermal fluids, geopressured brines, hot dry rock, and magma still depends on the technology improvements sought by the DOE Geothermal Energy R and D Program. The successful outcome of the R and D initiatives will serve to benefit the U.S. public in a number of ways. First, if a substantial portion of our geothermal resources can be used economically, they will add a very large source of secure, indigenous energy to the nation's energy supply. In addition, geothermal plants can be brought on line quickly in case of a national energy emergency. Geothermal energy is also a highly reliable resource, with very high plant availability. For example, new dry steam plants at The Geysers are operable over 99 percent of the time, and the small flash plant in Hawaii, only the second in the United States, has an availability factor of 98 percent. Geothermal plants also offer a viable baseload alternative to fossil and nuclear plants -- they are on line 24 hours a day, unaffected by diurnal or seasonal variations. The hydrothermal power plants with modern emission control technology have proved to have minimal environmental impact. The results to date with geopressured and hot dry rock resources suggest that they, too, can be operated so as to reduce environmental effects to well within the limits of acceptability. Preliminary studies on magma are also encouraging. In summary, the character and potential of geothermal energy, together with the accomplishments of DOE's Geothermal R and D Program, ensure that this huge energy resource will play a major role in future U.S. energy markets.

  16. Summary

    International Nuclear Information System (INIS)

    2004-01-01

    The fourth workshop of the OECD/NEA Forum on Stakeholder Confidence (FSC) was hosted by ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste Management and enriched fissile materials. The central theme of the workshop was ''Dealing with interests, values and knowledge in managing risk''within the Belgian context of local partnerships for the long term management of low-level, short-lived radioactive waste. The four-day workshop started with a half-day session in Brussels giving a general introduction on the Belgian context and the local partnership methodology. This was followed by community visits to three local partnerships, PaLoFF in Fleurus-Farciennes, MONA in Mol, and STOLA in Dessel. After the visits, the workshop continued with two full-day sessions in Brussels. One hundred and nineteen registered participants, representing 13 countries, attended the workshop or participated in the community visits. About two thirds were Belgian stakeholders; the remainder came from FSC member organisations. The participants included representatives of municipal governments, civil society organisations, government agencies, industrial companies, the media, and international organisations as well as private citizens, consultants and academics. This Executive Summary gives an overview of the presentations and discussions that took place at the workshop and the community visits. The structure of the Executive Summary follows the structure of the workshop itself. Complementary to this Executive Summary and also provided with this document, is a NEA Secretariat's reflection aiming to place the main lessons of the workshop into an international perspective. (author)

  17. Nuclear fission

    International Nuclear Information System (INIS)

    Kodama, T.

    1981-01-01

    The nuclear fission process is pedagogically reviewed from a macroscopic-microscopic point of view. The Droplet model is considered. The fission dynamics is discussed utilizing path integrals and semiclassical methods. (L.C.) [pt

  18. 3013/9975 Surveillance Program Interim Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Dunn, K.; Hackney, B.; McClard, J.

    2011-06-22

    The K-Area Materials Storage (KAMS) Documented Safety Analysis (DSA) requires a surveillance program to monitor the safety performance of 3013 containers and 9975 shipping packages stored in KAMS. The SRS surveillance program [Reference 1] outlines activities for field surveillance and laboratory tests that demonstrate the packages meet the functional performance requirements described in the DSA. The SRS program also supports the complexwide Integrated Surveillance Program (ISP) [Reference 2] for 3013 containers. The purpose of this report is to provide a summary of the SRS portion of the surveillance program activities through fiscal year 2010 (FY10) and formally communicate the interpretation of these results by the Surveillance Program Authority (SPA). Surveillance for the initial 3013 container random sampling of the Innocuous bin and the Pressure bin has been completed and there has been no indication of corrosion or significant pressurization. The maximum pressure observed was less than 50 psig, which is well below the design pressure of 699 psig for the 3013 container [Reference 3]. The data collected during surveillance of these bins has been evaluated by the Materials Identification and Surveillance (MIS) Working Group and no additional surveillance is necessary for these bins at least through FY13. A decision will be made whether additional surveillance of these bins is needed during future years of storage and as additional containers are generated. Based on the data collected to date, the SPA concludes that 3013 containers in these bins can continue to be safely stored in KAMS. This year, 13 destructive examinations (DE) were performed on random samples from the Pressure & Corrosion bin. To date, DE has been completed for approximately 30% of the random samples from the Pressure & Corrosion bin. In addition, DE has been performed on 6 engineering judgment (EJ) containers, for a total of 17 to date. This includes one container that exceeded the 3013

  19. 3013/9975 Surveillance Program Interim Summary Report

    International Nuclear Information System (INIS)

    Dunn, K.; Hackney, B.; McClard, J.

    2011-01-01

    The K-Area Materials Storage (KAMS) Documented Safety Analysis (DSA) requires a surveillance program to monitor the safety performance of 3013 containers and 9975 shipping packages stored in KAMS. The SRS surveillance program (Reference 1) outlines activities for field surveillance and laboratory tests that demonstrate the packages meet the functional performance requirements described in the DSA. The SRS program also supports the complexwide Integrated Surveillance Program (ISP) (Reference 2) for 3013 containers. The purpose of this report is to provide a summary of the SRS portion of the surveillance program activities through fiscal year 2010 (FY10) and formally communicate the interpretation of these results by the Surveillance Program Authority (SPA). Surveillance for the initial 3013 container random sampling of the Innocuous bin and the Pressure bin has been completed and there has been no indication of corrosion or significant pressurization. The maximum pressure observed was less than 50 psig, which is well below the design pressure of 699 psig for the 3013 container (Reference 3). The data collected during surveillance of these bins has been evaluated by the Materials Identification and Surveillance (MIS) Working Group and no additional surveillance is necessary for these bins at least through FY13. A decision will be made whether additional surveillance of these bins is needed during future years of storage and as additional containers are generated. Based on the data collected to date, the SPA concludes that 3013 containers in these bins can continue to be safely stored in KAMS. This year, 13 destructive examinations (DE) were performed on random samples from the Pressure and Corrosion bin. To date, DE has been completed for approximately 30% of the random samples from the Pressure and Corrosion bin. In addition, DE has been performed on 6 engineering judgment (EJ) containers, for a total of 17 to date. This includes one container that exceeded the 3013

  20. Fission product release during MCCI. CEC nuclear safety program: MCCI project

    Energy Technology Data Exchange (ETDEWEB)

    Cenerino, G [CEA Centre d` Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Cordfunke, E H.P. [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Hunterlaar, M E [Netherlands Energy Research Foundation (ECN), Petten (Netherlands)

    1995-01-01

    The assessment of the consequences of severe accidents in nuclear reactors involving molten core-concrete interactions (MCCls) requires estimates of the quantities and physicochemical forms of the radioactive species released from the melt into the cavity atmosphere. Such estimates in turn require a detailed knowledge of the complex chemical interactions which would occur between the fission products, fuel and the components of the core structural materials and the concrete. In recent years, effort has been put into the thermodynamic characterization of these processes. The results of such studies are important for predicting several aspects of MCCls, including: 1. The release of species by vaporization; 2. the extent of concrete penetration: a. The melt solidus and liquidus temperatures, which in turn affect the heat transfer processes and hence tile predictions of the melt temperature and the onset of solidification, b. the amounts of the solid and liquid phases and the respective compositions, which determines the viscosity of the melt, and c. the composition of the crust formed following the addition of water to quench the interaction. d. the distribution of fission products among metallic and oxidic phases. This SOAR is devoted to thermochemical calculations in the context of MCCI where most fission products and the metallic components of the melt are transferred into an oxidic form sooner or later. Calculations on fission product release from a molten pool without MCCI are underway in the source term project of the CEC-RCA. The following conditions have to be taken into account in order to be able to perform reliable thermodynamic calculations. (orig./HP).

  1. Fission product release during MCCI. CEC nuclear safety program: MCCI project

    International Nuclear Information System (INIS)

    Cenerino, G.; Hunterlaar, M.E.

    1995-01-01

    The assessment of the consequences of severe accidents in nuclear reactors involving molten core-concrete interactions (MCCls) requires estimates of the quantities and physicochemical forms of the radioactive species released from the melt into the cavity atmosphere. Such estimates in turn require a detailed knowledge of the complex chemical interactions which would occur between the fission products, fuel and the components of the core structural materials and the concrete. In recent years, effort has been put into the thermodynamic characterization of these processes. The results of such studies are important for predicting several aspects of MCCls, including: 1. The release of species by vaporization; 2. the extent of concrete penetration: a. The melt solidus and liquidus temperatures, which in turn affect the heat transfer processes and hence tile predictions of the melt temperature and the onset of solidification, b. the amounts of the solid and liquid phases and the respective compositions, which determines the viscosity of the melt, and c. the composition of the crust formed following the addition of water to quench the interaction. d. the distribution of fission products among metallic and oxidic phases. This SOAR is devoted to thermochemical calculations in the context of MCCI where most fission products and the metallic components of the melt are transferred into an oxidic form sooner or later. Calculations on fission product release from a molten pool without MCCI are underway in the source term project of the CEC-RCA. The following conditions have to be taken into account in order to be able to perform reliable thermodynamic calculations. (orig./HP)

  2. Chemical Weapons Improved Response Program. 2000 Summary Report

    National Research Council Canada - National Science Library

    2000-01-01

    The purpose of this summary report is to inform members of the first responder and emergency management communities about the on-going activities, initiatives, and lessons learned from the Chemical...

  3. Packaging and transportation of radioactive materials: summary program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    This document contains summaries or abstracts of reports presented at the Symposium on Packaging and Transportation of Radioactive Materials. Separate indexing has been performed on individual items presented at this conference. (DC)

  4. Packaging and transportation of radioactive materials: summary program

    International Nuclear Information System (INIS)

    1978-01-01

    This document contains summaries or abstracts of reports presented at the Symposium on Packaging and Transportation of Radioactive Materials. Separate indexing has been performed on individual items presented at this conference

  5. Radiochemistry and the Study of Fission

    Energy Technology Data Exchange (ETDEWEB)

    Rundberg, Robert S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-11-14

    These are slides from a lecture given at UC Berkeley. Radiochemistry has been used to study fission since its discovery. Radiochemical methods are used to determine cumulative mass yields. These measurements have led to the two-mode fission hypothesis to model the neutron energy dependence of fission product yields. Fission product yields can be used for the nuclear forensics of nuclear explosions. The mass yield curve depends on both the fuel and the neutron spectrum of a device. Recent studies have shown that the nuclear structure of the compound nucleus can affect the mass yield distribution. The following topics are covered: In the beginning: the discovery of fission; forensics using fission products: what can be learned from fission products, definitions of R-values and Q-values, fission bases, K-factors and fission chambers, limitations; the neutron energy dependence of the mass yield distribution (the two mode fission hypothesis); the influence of nuclear structure on the mass yield distribution. In summary: Radiochemistry has been used to study fission since its discovery. Radiochemical measurement of fission product yields have provided the highest precision data for developing fission models and for nuclear forensics. The two-mode fission hypothesis provides a description of the neutron energy dependence of the mass yield curve. However, data is still rather sparse and more work is needed near second and third chance fission. Radiochemical measurements have provided evidence for the importance of nuclear states in the compound nucleus in predicting the mass yield curve in the resonance region.

  6. Radiochemistry and the Study of Fission

    International Nuclear Information System (INIS)

    Rundberg, Robert S.

    2016-01-01

    These are slides from a lecture given at UC Berkeley. Radiochemistry has been used to study fission since its discovery. Radiochemical methods are used to determine cumulative mass yields. These measurements have led to the two-mode fission hypothesis to model the neutron energy dependence of fission product yields. Fission product yields can be used for the nuclear forensics of nuclear explosions. The mass yield curve depends on both the fuel and the neutron spectrum of a device. Recent studies have shown that the nuclear structure of the compound nucleus can affect the mass yield distribution. The following topics are covered: In the beginning: the discovery of fission; forensics using fission products: what can be learned from fission products, definitions of R-values and Q-values, fission bases, K-factors and fission chambers, limitations; the neutron energy dependence of the mass yield distribution (the two mode fission hypothesis); the influence of nuclear structure on the mass yield distribution. In summary: Radiochemistry has been used to study fission since its discovery. Radiochemical measurement of fission product yields have provided the highest precision data for developing fission models and for nuclear forensics. The two-mode fission hypothesis provides a description of the neutron energy dependence of the mass yield curve. However, data is still rather sparse and more work is needed near second and third chance fission. Radiochemical measurements have provided evidence for the importance of nuclear states in the compound nucleus in predicting the mass yield curve in the resonance region.

  7. Biomass energy systems program summary. Information current as of September 30, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    This program summary describes each of the DOE's Biomass Energy System's projects funded or in existence during fiscal year 1979 and reflects their status as of September 30, 1979. The summary provides an overview of the ongoing research, development, and demonstration efforts of the preceding fiscal year as well. (DMC)

  8. Final summary report of the Nordic Nuclear Safety Research Program 1994 - 1997

    International Nuclear Information System (INIS)

    Bennerstedt, T.; Lemmens, A.

    1999-11-01

    This is a summary report of the NKS research program carried out 1994 - 1997. It is basically a compilation of the executive summaries of the final reports on the nine scientific projects carried out during that period. It highlights the conclusions, recommendations and other results of the projects. (au)

  9. The GEM code. A simulation program for the evaporation and the fission process of an excited nucleus

    Energy Technology Data Exchange (ETDEWEB)

    Furihata, Shiori [Mitsubishi Research Institute Inc., Tokyo (Japan); Niita, Koji [Research Organization for Information Science and Technology, Tokai, Ibaraki (Japan); Meigo, Shin-ichiro; Ikeda, Yujiro; Maekawa, Fujio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    The GEM code is a simulation program which describes the de-excitation process of an excited nucleus, which is based on the Generalized Evaporation Model and the Atchison fission model. It has been shown that the combination of the Bertini intranuclear cascade model and GEM accurately predicts the cross sections of light fragments, such as Be produced from the proton-induced reactions. It has also been shown that the use of the reevaluated parameters in the Atchison model improves predictions of cross sections of fission fragments produced from the proton-induced reaction on Au. In this report, we present details and the usage of the GEM code. Furthermore, the results of benchmark calculations are shown by using the combination of the Bertini intranuclear cascade model and the GEM code (INC/GEM). Neutron spectra and isotope production cross sections from the reactions on various targets irradiated by protons are calculated with INC/GEM. Those results are compared with experimental data as well as the calculation results with LAHET. INC/GEM reproduces the experiments of double differential neutron emissions from the reaction on Al and Pb. The isotopic distributions for He, Li, and Be produced from the reaction on Ag are in good agreement with experimental data within 50%, although INC/GEM underestimates those of heavier nuclei than O. It is also shown that the predictions with INC/GEM for isotope production of light fragments, such as Li and Be, are better than those calculation with LAHET, particularly for heavy target. INC/GEM also gives better estimates of the cross sections of fission products than LAHET. (author)

  10. Fission gas release from oxide fuels at high burnups (AWBA development program)

    International Nuclear Information System (INIS)

    Dollins, C.C.

    1981-02-01

    The steady state gas release, swelling and densification model previously developed for oxide fuels has been modified to accommodate the slow transients in temperature, temperature gradient, fission rate and pressure that are encountered in normal reactor operation. The gas release predictions made by the model were then compared to gas release data on LMFBR-EBRII fuels obtained by Dutt and Baker and reported by Meyer, Beyer, and Voglewede. Good agreement between the model and the data was found. A comparison between the model and three other sets of gas release data is also shown, again with good agreement

  11. Summary reports of activities under visiting research program

    International Nuclear Information System (INIS)

    1984-01-01

    The Research Reactor Institute, Kyoto University, publishes any time the necessary data at the time of research and experiment, the conspicuous results obtained during research, new methods, the discussion on other papers and reports and so on as prompt reports, for example, the results of the functional test of various experimental facilities, the results of the test on things made for trial, radiation control, the state of waste treatment and the reports of study meetings. This is the summary report of the research carried out in the second half of 1983 by the common utilization of the facilities in the KURRI. The title, reporters and summary of 64 researches are reported. (Kako, I.)

  12. Microscopic Theory of Fission

    International Nuclear Information System (INIS)

    Younes, W; Gogny, D

    2008-01-01

    In recent years, the microscopic method has been applied to the notoriously difficult problem of nuclear fission with unprecedented success. In this paper, we discuss some of the achievements and promise of the microscopic method, as embodied in the Hartree-Fock method using the Gogny finite-range effective interaction, and beyond-mean-field extensions to the theory. The nascent program to describe induced fission observables using this approach at the Lawrence Livermore National Laboratory is presented

  13. A Research Program for Fission Product/Dust Transport in HTGR's

    International Nuclear Information System (INIS)

    Loyalka, Sudarshan

    2016-01-01

    High and Very High Temperatures Gas Reactors (HTGRs/VHTRs) have five barriers to fission product (FP) release: the TRISO fuel coating, the fuel elements, the core graphite, the primary coolant system, and the reactor building. This project focused on measurements and computations of FP diffusion in graphite, FP adsorption on graphite and FP interactions with dust particles of arbitrary shape. Diffusion Coefficients of Cs and Iodine in two nuclear graphite were obtained by the release method and use of Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS) and Instrumented Neutron Activation Analysis (INAA). A new mathematical model for fission gas release from nuclear fuel was also developed. Several techniques were explored to measure adsorption isotherms, notably a Knudsen Effusion Mass Spectrometer (KEMS) and Instrumented Neutron Activation Analysis (INAA). Some of these measurements are still in progress. The results will be reported in a supplemental report later. Studies of FP interactions with dust and shape factors for both chain-like particles and agglomerates over a wide size range were obtained through solutions of the diffusion and transport equations. The Green's Function Method for diffusion and Monte Carlo technique for transport were used, and it was found that the shape factors are sensitive to the particle arrangements, and that diffusion and transport of FPs can be hindered. Several journal articles relating to the above work have been published, and more are in submission and preparation.

  14. A Research Program for Fission Product/Dust Transport in HTGR’s

    Energy Technology Data Exchange (ETDEWEB)

    Loyalka, Sudarshan [Univ. of Missouri, Columbia, MO (United States)

    2016-02-01

    High and Very High Temperatures Gas Reactors (HTGRs/VHTRs) have five barriers to fission product (FP) release: the TRISO fuel coating, the fuel elements, the core graphite, the primary coolant system, and the reactor building. This project focused on measurements and computations of FP diffusion in graphite, FP adsorption on graphite and FP interactions with dust particles of arbitrary shape. Diffusion Coefficients of Cs and Iodine in two nuclear graphite were obtained by the release method and use of Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS) and Instrumented Neutron Activation Analysis (INAA). A new mathematical model for fission gas release from nuclear fuel was also developed. Several techniques were explored to measure adsorption isotherms, notably a Knudsen Effusion Mass Spectrometer (KEMS) and Instrumented Neutron Activation Analysis (INAA). Some of these measurements are still in progress. The results will be reported in a supplemental report later. Studies of FP interactions with dust and shape factors for both chain-like particles and agglomerates over a wide size range were obtained through solutions of the diffusion and transport equations. The Green's Function Method for diffusion and Monte Carlo technique for transport were used, and it was found that the shape factors are sensitive to the particle arrangements, and that diffusion and transport of FPs can be hindered. Several journal articles relating to the above work have been published, and more are in submission and preparation.

  15. A summary of the assessment of fuel behaviour, fission product release and pressure tube integrity following a postulated large loss-of-coolant accident

    International Nuclear Information System (INIS)

    Langman, V.J.; Weaver, K.R.

    1984-05-01

    The Ontario Hydro analyses of fuel and pressure tube temperatures, fuel behaviour, fission product release and pressure tube integrity for large break loss-of-coolant accidents in Bruce A or Pickering A have been critically reviewed. The determinations of maximum fuel temperatures and fission product release are very uncertain, and pressure tube integrity cannot be assured where low steam flows are predicted to persist for times on the order of minutes

  16. K Basin Fuel Characterization Program Technical Baseline Summary

    International Nuclear Information System (INIS)

    SUYAMA, R.M.

    1999-01-01

    This document provides a summary of the systematic process used by the SNF Project to characterize K-Basin spent fuel, and to develop and apply the appropriate conservative safety margins to the resulting parameters for technical designs and safety analyses

  17. Fusion Engineering Device. Volume 1. Mission and program summary

    International Nuclear Information System (INIS)

    1981-10-01

    This volume presents, in summary form, a recommended approach to implementing the Magnetic Fusion Energy Engineering Act of 1980. These recommendations constitute the findings of the FED Technical Management Board (TMB). The TMB and the affiliated technical managers gave particular scrutiny to elucidating the role of FED in fusion development and to defining the device mission

  18. FPDCYS and FPSPEC: computer programs for calculating fission-product beta and gamma multigroup spectra from ENDF/B-IV data

    International Nuclear Information System (INIS)

    Stamatelatos, M.G.; England, T.R.

    1977-05-01

    FPDCYS and FPSPEC are two FORTRAN computer programs used at the Los Alamos Scientific Laboratory (LASL), in conjunction with the CINDER-10 program, for calculating cumulative fission-product beta and/or gamma multigroup spectra in arbitrary energy structures, and for arbitrary neutron irradiation periods and cooling times. FPDCYS processes ENDF/B-IV fission-product decay energy data to generate multigroup beta and gamma spectra from individual ENDF/B-IV fission-product nuclides. FPSPEC further uses these spectra and the corresponding nuclide activities calculated by the CINDER-10 code to produce cumulative beta and gamma spectra in the same energy grids in which FPDCYS generates individual isotope decay spectra. The code system consisting of CINDER-10, FPDCYS, and FPSPEC has been used for comparisons with experimental spectra and continues to be used at LASL for generating spectra in special user-oriented group structures. 3 figures

  19. DHS National Technical Nuclear Forensics Program FY 10 Summary Report: Graduate Mentoring Assistance Program (GMAP)

    International Nuclear Information System (INIS)

    Finck, Martha R.

    2011-01-01

    This program provides practical training to DHS graduate fellows in the DOE laboratory complex. It involves coordinating students, their thesis advisors, and their laboratory project mentors in establishing a meaningful program of research which contributes to the graduate student's formation as a member of the nuclear forensics community. The summary report details the student/mentor experience and future plans after the first summer practicum. This program provides practical training to DHS graduate fellows in the DOE laboratory complex. It involves coordinating students, their thesis advisors, and their laboratory project mentors in establishing a meaningful program of research which contributes to the graduate student's formation as a member of the nuclear forensics community. This final written report includes information concerning the overall mentoring experience, including benefits (to the lab, the mentors, and the students), challenges, student research contributions, and lab mentor interactions with students home universities. Idaho National Laboratory hosted two DHS Nuclear Forensics graduate Fellows (nuclear engineering) in summer 2011. Two more Fellows (radiochemistry) are expected to conduct research at the INL under this program starting in 2012. An undergraduate Fellow (nuclear engineering) who worked in summer 2011 at the laboratory is keenly interested in applying for the NF Graduate Fellowship this winter with the aim of returning to INL. In summary, this program appears to have great potential for success in supporting graduate level students who pursue careers in nuclear forensics. This relatively specialized field may not have been an obvious choice for some who have already shown talent in the traditional areas of chemistry or nuclear engineering. The active recruiting for this scholarship program for candidates at universities across the U.S. brings needed visibility to this field. Not only does this program offer critical practical training

  20. Post-scission fission theory: Neutron emission in fission

    International Nuclear Information System (INIS)

    Madland, D.G.

    1997-01-01

    A survey of theoretical representations of two of the observables in neutron emission in fission is given, namely, the prompt fission neutron spectrum N (E) and the average prompt neutron multiplicity bar ν p . Early representations of the two observables are presented and their deficiencies are discussed. This is followed by summaries and examples of recent theoretical models for the calculation of these quantities. Emphasis is placed upon the predictability and accuracy of the recent models. In particular, the dependencies of N (E) and bar ν p upon the fissioning nucleus and its excitation energy are treated. Recent work in the calculation of the prompt fission neutron spectrum matrix N (E, E n ), where E n is the energy of the neutron inducing fission, is then discussed. Concluding remarks address the current status of our ability to calculate these observables with confidence, the direction of future theoretical efforts, and limitations to current (and future) approaches

  1. A Summary of the Naval Postgraduate School Research Program.

    Science.gov (United States)

    1982-05-01

    1975. 86 Title: Navy Officer Sea Tour Opportunity Models (Part of the research in Officer Manpower and Personnel Planning with Professor J. K. Arima ...circulations by C. P. Chang. 221 .k-...IlII I ilOI II ," .. .... C. P. Chang and K. M Lau continue to use domain-averaged climatic numerical models to...ADMINISTRATIVE SCIENCES 25 Administrative Sciences Department Summary 27 Estimation and Prediction In Enlistment Supply Models ---- 30 Measurement of

  2. FHWA research and technology evaluation program summary report spring 2016

    Science.gov (United States)

    2016-08-01

    This report summarizes the 16 evaluations being conducted by the Volpe National Transportation Systems Center on behalf of FHWAs Research and Technology Program. The FHWA R&T Program furthers the Turner-Fairbank Highway Research Centers goal of...

  3. 1976 Survey of Collegiate Programs for Older Adults. Summary Report.

    Science.gov (United States)

    Florio, Carol

    Questionnaires were mailed to the directors of continuing education or special programs at 816 colleges and universities in the United States that were believed to offer programs for older adults. 84 percent of the 286 responding institutions reported programs for older adults; 1 percent had them in the planning stages; 3 percent had…

  4. Alpena Community College Commercial Driver's License Program. Evaluation Summary.

    Science.gov (United States)

    Alpena Community Coll., MI.

    The Alpena Community College (ACC) Drivers Education Program was developed to deliver a basic skills program providing specific job-related basic skills instruction to approximately 300 workers throughout Michigan who desired to pass the Commercial Drivers License (CDL) examination. Other program goals were to establish greater partnerships…

  5. FISSION 2120: a program for assessing the need for engineered safety feature grade air cleaning systems in post accident environments

    International Nuclear Information System (INIS)

    Martin, G. Jr.; Michlewicz, D.; Thomas, J.

    1979-01-01

    A computer program FISSION 2120, has been developed to evaluate the need for various engineered Safety Feature grade air cleaning systems to mitigate radiation exposures resulting from accidential releases of radioactivity. Those systems which are generally investigated include containment sprays with chemical additives, containment fan coolers with charcoal filters, and negative pressure maintenance systems for double barrier containments with either one-pass filtration or recirculation with filtration. The program can also be used to calculate the radiation doses to control room personnel. This type of analysis is directed towards the various protection aspects of the emergency ventilation system and involves the modeling of the radiological source terms and the atmospheric transport of the radioactive releases. The modeling is enhanced by the inherent capability of the program to accommodate simultaneous release of activity from several sources and to perform a dose evaluation for a wide range of the design characteristics of control room emergency air filtration systems. Use of the program has resulted in considerable savings in the time required to perform such analyses and in the selection of the most cost-effective Engineered Safety Features

  6. Summary

    International Nuclear Information System (INIS)

    1982-01-01

    The International Tokamak Reactor (INTOR) Workshop is an unique collaborative effort among Euratom, Japan, the USA and the USSR, under the auspices of the IAEA, to assess, define, design, construct and operate the next major experiment in the World Tokamak Program beyond the TFTR, JET, JT-60, T-15 generation. During the Zero-Phase (1979), a technical data base assessment was performed, leading to a positive assessment of feasibility. During Phase-1 (1/80-6/81), a conceptual design was developed to define the concept. The programmatic objectives are that INTOR should: (1) be the maximum reasonable step beyond the TFTR, JET, JT-60, T-15 generation of tokamaks, (2) demonstrate the plasma performance required for tokamak DEMOs, (3) test the development and integration into a reactor system of those technologies required for a DEMO, (4) serve as a test facility for blanket, tritium production, materials, and plasma engineering technology, (5) test fusion reactor component reliability, (6) test the maintainability of a fusion reactor, and (7) test the factors affecting the reliability, safety and environmental acceptability of a fusion reactor. A conceptual design has been developed to define a device which is consistent with these objectives. The design concept could, with a reasonable degree of confidence, be developed into a workable engineering design of a tokamak that met the performance objectives of INTOR. There is some margin in the design to allow for uncertainty. While design solutions have been found for all of the critical issues, the overall design may not yet be optimal

  7. Review and summary of Solar Thermal Conversion Program planning assistance

    Energy Technology Data Exchange (ETDEWEB)

    1975-06-01

    The Solar Thermal Conversion Program comprises a major part of the national solar energy program which must be continuously reviewed and modified where necessary. Modifications are typically required to reflect technical achievements and uncertainties which arise from within the program or from other technical programs, changes in budgets available for supporting the program as well as internal program funding priorities, changing goals such as through acceleration or stretch-out of the program schedule, significant organizational changes involving responsible governmental agencies, the introduction of new project management support contractors, and required budget or schedule changes occurring within individual projects that make up the Solar Thermal Conversion Program. The Aerospace Corporation has provided data to assist in planning, review, coordination, and documentation of the overall Solar Thermal Conversion Program. The Solar Thermal Conversion Program Plan is described in detail. Sections 2.0 through 5.0 cover the discussion and detail planning covering the objectives, justification, basic and alternative plans, budgets, and schedules for the Solar Thermal sub-unit portion of the Solar Electric Applications effort. Appendices B1, B2, and B3 include the March 21, March 28, and April 5, 1975, Program Plan submissions of the complete Solar Electric Applications effort. In Appendix B the Solar Thermal, Solar Photovoltaic, Wind Energy, and Ocean Thermal sub-unit texts have been condensed and formatted for integration in the overall ERDA budget package. (WHK)

  8. Summary

    International Nuclear Information System (INIS)

    Bickerton, George

    1997-01-01

    The Chernobyl accident has pushed many countries in analyzing critically their radiological emergency plans in order to identify the fields requiring amelioration or reinforcement. A common topic was the necessity of informing and drilling efficiently the civil population as well as different intervening agents against effects of nuclear accidents. It was stressed that the health and safety of populations, potentially most exposed, constitute a top priority, followed by the protection of food storage. The majority of the countries, were the management of public affairs is effected at two or more echelons, is confronted with the difficulty of developing plans clearly defining the missions and responsibilities of different administration levels as well as the interactions between them in case of emergency. Emphasized are also the requirements of information tools able of computing the contamination of foods or forages taking into account of factors like annual season, the phase of crop growth and the meteorological conditions. Obviously, such programs permit forecasting, surveying and evaluating the contamination and consequently, establishing the proper level of intervention. Also, the question of intervention thresholds was approached as well as the necessity of harmonizing intervention on international scale. A number of topics were mentioned to be under current study among which the relations between soil contamination and radionuclide concentration in milk and forage as well as the methods of managing the highly cesium-contaminated milk. Finally, it was argued for the necessity of ensuring the population confidence in the measures of intervention as well as in the indications of competent officials in charge with emergency actions

  9. Photovoltaic Energy Program Contract Summary; Fiscal Year 1998

    Energy Technology Data Exchange (ETDEWEB)

    Surek, T.

    1999-02-16

    This document provides individual summaries of some 200 photovoltaics research projects performed in house and by subcontractors to Department of Energy national laboratories and field offices, including the National Renewable Energy Laboratory, Sandia National Laboratories, Golden Field Office, Brookhaven National Laboratory, Albuquerque Field Office, and Boston Support Office. The document is divided into the following sections: research and development, technology development, and systems engineering and applications. Three indexes are included: performing organizations by name, performing organizations by state, and performing organizations by technology area.

  10. Hydrogen Energy Coordinating Committee annual report: Summary of DOE hydrogen programs for FY 1988

    International Nuclear Information System (INIS)

    1989-01-01

    The FY 1988 Summary is the eleventh consecutive yearly report providing an overview of the hydrogen-related programs of the DOE offices represented on the HECC. A historical summary of the hydrogen budgets of these offices is given. The distribution by mission-related program element for FY 1988, and the non-mission-related activities are given. Total DOE funding in FY 1988 for mission-related hydrogen research was $5.2 million; DOE non-mission-related hydrogen research funding totaled $30.0 million. The individual program elements are described in the body of this report, and more specific program information is given in the Technology Summary Forms in Appendix A. 2 tabs

  11. Building Management Information Systems to Coordinate Citywide Afterschool Programs: A Toolkit for Cities. Executive Summary

    Science.gov (United States)

    Kingsley, Chris

    2012-01-01

    This executive summary describes highlights from the report, "Building Management Information Systems to Coordinate Citywide Afterschool Programs: A Toolkit for Cities." City-led efforts to build coordinated systems of afterschool programming are an important strategy for improving the health, safety and academic preparedness of children…

  12. Ternary fission

    International Nuclear Information System (INIS)

    Wagemans, C.

    1991-01-01

    Since its discovery in 1946, light (charged) particle accompanied fission (ternary fission) has been extensively studied, for spontaneous as well as for induced fission reactions. The reason for this interest was twofold: the ternary particles being emitted in space and time close to the scission point were expected to supply information on the scission point configuration and the ternary fission process was an important source of helium, tritium, and hydrogen production in nuclear reactors, for which data were requested by the nuclear industry. Significant experimental progress has been realized with the advent of high-resolution detectors, powerful multiparameter data acquisition systems, and intense neutron and photon beams. As far as theory is concerned, the trajectory calculations (in which scission point parameters are deduced from the experimental observations) have been very much improved. An attempt was made to explain ternary particle emission in terms of a Plateau-Rayleigh hydrodynamical instability of a relatively long cylindrical neck or cylindrical nucleus. New results have also been obtained on the so-called open-quotes trueclose quotes ternary fission (fission in three about-equal fragments). The spontaneous emission of charged particles has also clearly been demonstrated in recent years. This chapter discusses the main characteristics of ternary fission, theoretical models, light particle emission probabilities, the dependence of the emission probabilities on experimental variables, light particle energy distributions, light particle angular distributions, correlations between light particle accompanied fission observables, open-quotes trueclose quotes ternary fission, and spontaneous emission of heavy ions. 143 refs., 18 figs., 8 tabs

  13. Fission product release under severe accidental conditions: general presentation of the program and synthesis of VERCORS 1-6 results

    International Nuclear Information System (INIS)

    Ducros, G.; Malgouyres, P.P.; Kissane, M.; Boulaud, D.; Durin, M.

    2001-01-01

    The French Nuclear Protection and Safety Institute (IPSN) launched the HEVA-VERCORS program in 1983, in collaboration with Electricite de France (EDF). This program is devoted to the source term of fission products (FP) released from PWR fuel samples during a sequence representative of a severe accident. The analytical experiments are conducted in a shielded hot cell of the LAMA facility of the Grenoble center of CEA (Commissariat a l'Energie Atomique); as simplified tests addressing a limited number of phenomena, they give results complementary to those of the more global in-pile PHEBUS experiments. Six VERCORS tests have been conducted from 1989-1994 with higher fuel temperatures (up to 2600 K) compared with the earlier HEVA tests in order, in particular, to quantify better the release of lower volatile FPs. This paper gives an overview of the experimental facility, a synthesis of FP release from these tests and exhibits, as an example, some specific results of the VERCORS 6 test, performed with high burn-up fuel (60 GWd tU -1 ). The on-going VERCORS HT-RT program, designed to reach fuel liquefaction temperatures, is described before conclusions are drawn

  14. Critical evaluation of the nonradiological environmental technical specifications. Program description, summary, and recommendations. Vol. 1

    International Nuclear Information System (INIS)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.; Witten, A.J.

    1976-01-01

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for eight nuclear power plants was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory commission. This report includes a summary of the screening phase in which the adequacy of the hydrothermal and ecological monitoring data for each plant were evaluated, and the summary and recommendations resulting from a detailed examination of the three nuclear power plants selected in the initial screening

  15. Systems autonomy technology: Executive summary and program plan

    Science.gov (United States)

    Bull, John S (Editor)

    1987-01-01

    The National Space Strategy approved by the President and Congress in 1984 sets for NASA a major goal of conducting effective and productive space applications and technology programs which contribute materially toward United States leadership and security. To contribute to this goal, OAST supports the Nation's civil and defense space programs and overall economic growth. OAST objectives are to ensure timely provision of new concepts and advanced technologies, to support both the development of NASA missions in space and the space activities of industry and other organizations, to utilize the strengths of universities in conducting the NASA space research and technology program, and to maintain the NASA centers in positions of strength in critical space technology areas. In line with these objectives, NASA has established a new program in space automation and robotics that will result in the development and transfer and automation technology to increase the capabilities, productivity, and safety of NASA space programs including the Space Station, automated space platforms, lunar bases, Mars missions, and other deep space ventures. The NASA/OAST Automation and Robotics program is divided into two parts. Ames Research Center has the lead role in developing and demonstrating System Autonomy capabilities for space systems that need to make their own decisions and do their own planning. The Jet Propulsion Laboratory has the lead role for Telerobotics (that portion of the program that has a strong human operator component in the control loop and some remote handling requirement in space). This program is intended to be a working document for NASA Headquarters, Program Offices, and implementing Project Management.

  16. The Role of Leadership in Navy Program Offices. Executive Summary

    Science.gov (United States)

    1973-05-01

    PROGRAM MANAGEMENT COURSE- SSTUDENT STUDY PROGRAM Fort Beivoir, Virginia, 22060 THE ROLE OF LEADERSHIP IN NAVY PROGRAM OFFICES STUDY REPORT PMC 73-1...jLa I1 • 1. Men at the Top. Osborne kLliott 1 2. "Understanding Leadership ". W. 0. H. Prentice, HBR Sep- Oct 1966 j 3. "A Theory of Human Motivation...Drucker, IMI reprint 9. Technical Management Institute Thifnkpiece, " Leadership " 1 • 0. "The Effective Manager ". Peter Drucker, LMI r~print 11. Sur-ival In

  17. Fission energy program of the U.S. Department of Energy

    International Nuclear Information System (INIS)

    1978-06-01

    The document describes programs managed by the Program Director for Nuclear Energy, Department of Energy, and under the cognizance of the Committee on Science and Technology, United States House of Representatives. The major portion of the document is concerned with civilian nuclear power development, the policy for which has been established by the National Energy Plan of April 1977, but it also includes descriptions of the space applications and naval reactor programs

  18. Physical Research Program: research contracts and statistical summary

    International Nuclear Information System (INIS)

    1975-01-01

    The physical research program consists of fundamental theoretical and experimental investigations designed to support the objectives of ERDA. The program is directed toward discovery of natural laws and new knowledge, and to improved understanding of the physical sciences as related to the development, use, and control of energy. The ultimate goal is to develop a scientific underlay for the overall ERDA effort and the fundamental principles of natural phenomena so that these phenomena may be understood and new principles, formulated. The physical research program is organized into four functional subprograms, high-energy physics, nuclear sciences, materials sciences, and molecular sciences. Approximately four-fifths of the total physical research program costs are associated with research conducted in ERDA-owned, contractor-operated federally funded research and development centers. A little less than one-fifth of the costs are associated with the support of research conducted in other laboratories

  19. Atmospheric Science Program. Summaries of research in FY 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    This report provides descriptions for all projects funded by ESD under annual contracts in FY 1994. Each description contains the project`s title; three-year funding history (in thousands of dollars); the contract period over which the funding applies; the name(s) of the principal investigator(s); the institution(s) conducting the projects; and the project`s objectives, products, approach, and results to date (for most projects older than one year). Project descriptions are categorized within the report according to program areas: atmospheric chemistry, atmospheric dynamics, and support operations. Within these categories, the descriptions are ordered alphabetically by principal investigator. Each program area is preceded by a brief text that defines the program area, states it goals and objectives, lists principal research questions, and identifies program managers. Appendixes provide the addresses and telephone numbers of the principal investigators and define the acronyms used.

  20. A Summary of the Naval Postgraduate School Research Program.

    Science.gov (United States)

    1979-09-30

    Objective: To provide statistical analysis support to the Naval Analysis Programs to assess the impact of OSHA on Navy Programs. The primary task is to...the total in estimating efficiently the amount of asbestiform in Naval installations. Also participated in two workshops to assess the impact of OSHA on... Malaysia Since 1965, Capt. Ronald Toms, USA. "Arms Transfer to The Korean Peninsula, 1945-1979: Impact and Implications, Capt. Richard P. Cassidy, USA

  1. Laboratory Directed Research and Development Program FY2016 Annual Summary of Completed Projects

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2017-03-30

    ORNL FY 2016 Annual Summary of Laboratory Directed Research and Development Program (LDRD) Completed Projects. The Laboratory Directed Research and Development (LDRD) program at ORNL operates under the authority of DOE Order 413.2C, “Laboratory Directed Research and Development” (October 22, 2015), which establishes DOE’s requirements for the program while providing the Laboratory Director broad flexibility for program implementation. The LDRD program funds are obtained through a charge to all Laboratory programs. ORNL reports its status to DOE in March of each year.

  2. Load monitoring program: Status and results report. Volume 1: Summary

    International Nuclear Information System (INIS)

    1994-06-01

    British Columbia Hydro conducts a monitoring program to provide information on customer needs and values for planning; to measure customer response, energy savings impacts, and load shape impacts due to changes in rate level, rate restructuring, and Power Smart programs; to estimate end-use consumption and load shapes by customer class; and to provide load information for distribution and system load studies. To achieve these objectives, the monitoring program tracks the characteristics and energy use patterns of a sample of BC Hydro residential, commercial, and industrial customers over a period of several years. The entire sample will be surveyed periodically to obtain information on changes in building characteristics, equipment stocks, and energy-use behavior and attitudes. A report is provided on the status of monitoring program activities and some results obtained in 1993/94. For the residential sector, the results include typical load profiles, end-user demographics, and extent of electric space heating and water heating. In the commercial sector, customers were divided into two main groups. The large-building group was relatively well organized in terms of energy needs and participated in Power Smart programs. The small-building group was relatively energy-inefficient and relatively unaware of Power Smart programs. 43 figs., 15 tabs

  3. AICD -- Advanced Industrial Concepts Division Biological and Chemical Technologies Research Program. 1993 Annual summary report

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, G.; Bair, K.; Ross, J. [eds.

    1994-03-01

    The annual summary report presents the fiscal year (FY) 1993 research activities and accomplishments for the United States Department of Energy (DOE) Biological and Chemical Technologies Research (BCTR) Program of the Advanced Industrial Concepts Division (AICD). This AICD program resides within the Office of Industrial Technologies (OIT) of the Office of Energy Efficiency and Renewable Energy (EE). The annual summary report for 1993 (ASR 93) contains the following: A program description (including BCTR program mission statement, historical background, relevance, goals and objectives), program structure and organization, selected technical and programmatic highlights for 1993, detailed descriptions of individual projects, a listing of program output, including a bibliography of published work, patents, and awards arising from work supported by BCTR.

  4. Evaluation of fission-product gases in program GAPCON series and FREG-3 to estimate the gap heat transfer coefficient

    International Nuclear Information System (INIS)

    Ohki, Naohisa; Harayama, Yasuo; Takeda, Tsuneo; Izumi, Fumio.

    1977-12-01

    In safety evaluation of a fuel rod, estimation of the stored energy in the fuel rod is indispensable. For this estimation, the temperature distribution in the fuel rod is calculated. Most important in determination of the temperature distribution is the gap heat transfer coefficient (gap conductance) between pellet surface and cladding inner surface. Under fuel rod operating condition, the mixed gas in the gap is composed of He, Xe and Kr. He is initial seald gas. Xe and Kr are fission-product gases, of which the quantities depend on the fuel burn-up. In program GAPCON series (GAPCON and GAPCON-THERMAL-1 and -2) and FREG-3, these quantities are given as a function of the irradiation time, power rating and neutron flux in estimation of the thermal conductivity of the mixed gas. The methods of calculating the quantities of Xe and Kr in the programs have been examined. Input of the neutron flux which influences F.P. gas production rates is better than the determination from the fuel-rod power rating. (auth.)

  5. Coulex fission of 234U, 235U, 237Np, and 238Np studied within the SOFIA experimental program

    International Nuclear Information System (INIS)

    Martin, Julie-Fiona

    2014-01-01

    SOFIA (Studies On FIssion with Aladin) is an experimental project which aims at systematically measuring the fission fragments' isotopic yields as well as their total kinetic energy, for a wide variety of fissioning nuclei. The PhD work presented in this dissertation takes part in the SOFIA project, and covers the fission of nuclei in the region of the actinides: 234 U, 235 U, 237 Np and 238 Np. The experiment is led at the heavy-ion accelerator GSI in Darmstadt, Germany. This facility provides intense relativistic primary beam of 238 U. A fragmentation reaction of the primary beam permits to create a secondary beam of radioactive ions, some of which the fission is studied. The ions of the secondary beam are sorted and identified through the FR-S (Fragment Separator), a high resolution recoil spectrometer which is tuned to select the ions of interest.The selected - fissile - ions then fly further to Cave-C, an experimental area where the fission experiment itself takes place. At the entrance of the cave, the secondary beam is excited by Coulomb interaction when flying through an target; the de-excitation process involves low-energy fission. Both fission fragments fly forward in the laboratory frame, due to the relativistic boost inferred from the fissioning nucleus.A complete recoil spectrometer has been designed and built by the SOFIA collaboration in the path of the fission fragments, around the existing ALADIN magnet. The identification of the fragments is performed by means of energy loss, time of flight and deviation in the magnet measurements. Both fission fragments are fully (in mass and charge) and simultaneously identified.This document reports on the analysis performed for (1) the identification of the fissioning system, (2) the identification of both fission fragments, on an event-by-event basis, and (3) the extraction of fission observables: yields, TKE, total prompt neutron multiplicity. These results, concerning the actinides, are discussed, and

  6. Atmospheric Sciences Program summaries of research in FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    This document describes the activities and products of the Atmospheric Science Program of the Environmental Sciences Division, Office of Health and Environmental Research, Office of Energy Research, in FY 1993. Each description contains the project`s title; three-year funding history; the contract period over which the funding applies; the name(s) of the principal investigator(s); the institution(s) conducting the projects; and the project`s objectives, products, approach, and results to date. Project descriptions are categorized within the report according to program areas: atmospheric chemistry, atmospheric dynamics, and support operations. Within these categories, the descriptions are ordered alphabetically by principal investigator. Each program area is preceded by a brief text that defines the program area, states its goals and objectives, lists principal research questions, and identifies program managers. Appendixes provide the addresses and telephone numbers of the principal investigators and define the acronyms used. This document has been indexed to aid the reader in locating research topics, participants, and research institutions in the text and the project descriptions. Comprehensive subject, principal investigator, and institution indexes are provided at the end of the text for this purpose. The comprehensive subject index includes keywords from the introduction and chapter texts in addition to those from the project descriptions.

  7. 2D/3D Program work summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The 2D/3D Program was carried out by Germany, Japan and the United States to investigate the thermal-hydraulics of a PWR large-break LOCA. A contributory approach was utilized in which each country contributed significant effort to the program and all three countries shared the research results. Germany constructed and operated the Upper Plenum Test Facility (UPTF), and Japan constructed and operated the Cylindrical Core Test Facility (CCTF) and the Slab Core Test Facility (SCTF). The US contribution consisted of provision of advanced instrumentation to each of the three test facilities, and assessment of the TRAC computer code against the test results. Evaluations of the test results were carried out in all three countries. This report summarizes the 2D/3D Program in terms of the contributing efforts of the participants, and was prepared in a coordination among three countries. US and Germany have published the report as NUREG/IA-0126 and GRS-100, respectively. (author).

  8. Agriculture and Food Processes Branch program summary document

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-06-01

    The work of the Agriculture and Food Processes Branch within the US DOE's Office of Industrial Programs is discussed and reviewed. The Branch is responsible for assisting the food and agricultural sectors of the economy in increasing their energy efficiency by cost sharing with industry the development and demonstration of technologies industry by itself would not develop because of a greater than normal risk factor, but have significant energy conservation benefits. This task is made more difficult by the diversity of agriculture and the food industry. The focus of the program is now on the development and demonstration of energy conservation technology in high energy use industry sectors and agricultural functions (e.g., sugar processing, meat processing, irrigation, and crop drying, high energy use functions common to many sectors of the food industry (e.g., refrigeration, drying, and evaporation), and innovative concepts (e.g., energy integrated farm systems. Specific projects within the program are summarized. (LCL)

  9. 2D/3D Program work summary report

    International Nuclear Information System (INIS)

    1995-09-01

    The 2D/3D Program was carried out by Germany, Japan and the United States to investigate the thermal-hydraulics of a PWR large-break LOCA. A contributory approach was utilized in which each country contributed significant effort to the program and all three countries shared the research results. Germany constructed and operated the Upper Plenum Test Facility (UPTF), and Japan constructed and operated the Cylindrical Core Test Facility (CCTF) and the Slab Core Test Facility (SCTF). The US contribution consisted of provision of advanced instrumentation to each of the three test facilities, and assessment of the TRAC computer code against the test results. Evaluations of the test results were carried out in all three countries. This report summarizes the 2D/3D Program in terms of the contributing efforts of the participants, and was prepared in a coordination among three countries. US and Germany have published the report as NUREG/IA-0126 and GRS-100, respectively. (author)

  10. Biofuels Program Plan, FY 1992--FY 1996. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    This five-year program plan describes the goals and philosophy of the US Department of Energy`s (DOE) Biofuels Systems Division (BSD) program and the BSD`s major research and development (R&D) activities for fiscal years (FY) 1992 through 1996. The plan represents a consensus among government and university researchers, fuel and automotive manufacturers, and current and potential users of alternative fuels and fuel additives produced from biomass. It defines the activities that are necessary to produce versatile, domestic, economical, renewable liquid fuels from biomass feedstocks. The BSD program focuses on the production of alternative liquid fuels for transportation-fuels such as ethanol, methanol, biodiesel, and fuel additives for reformulated gasoline. These fuels can be produced from many plant materials and from a significant portion of the wastes generated by municipalities and industry. Together these raw materials and wastes, or feedstocks, are called biomass.

  11. Weatherization Innovation Pilot Program (WIPP): Technical Assistance Summary

    Energy Technology Data Exchange (ETDEWEB)

    Hollander, A.

    2014-09-01

    The U.S. Department of Energy (DOE) Energy Efficiency and Renewable Energy (EERE) Weatherization and Intergovernmental Programs Office (WIPO) launched the Weatherization Innovation Pilot Program (WIPP) to accelerate innovations in whole-house weatherization and advance DOE's goal of increasing the energy efficiency and health and safety of low-income residences without the utilization of additional taxpayer funding. Sixteen WIPP grantees were awarded a total of $30 million in Weatherization Assistance Program (WAP) funds in September 2010. These projects focused on: including nontraditional partners in weatherization service delivery; leveraging significant non-federal funding; and improving the effectiveness of low-income weatherization through the use of new materials, technologies, behavior-change models, and processes.

  12. Summary reports of activities under visiting research program

    International Nuclear Information System (INIS)

    1991-02-01

    The book carries a large number of summary studies made by using the Research Reactor (KUR) or the Critical Assembly (KUCA). These studies include low temperature irradiation effect on iron-alloy and ceramics, study on the influence of the neutron irradiation on the low temperature strength of various welded joint of dissimilar materials, effects of neutron irradiation on superconducting properties under stress in superconducting wires, neutron activation analysis and photo-emission phenomena from gamma-ray irradiated rock-forming minerals, study of irradiation effects in non-metallic conductors, distribution and mobility of ions of metal elements in stem, activation analysis of high purity metals, Moessbauer spectroscopic studies of superionic conductor, neutron spectrometry with CR-39 track detector, geochemical study on trace element abundances in island arc igneous rocks, experiment for measurement of neutron flux distribution in a tight pitch-lattice with a dy-wir, reactor rate distribution measurement of tight pitch lattice core with internal blanket, measurement of the foil reaction rates in a critical core, and many more. (N.K.)

  13. UNIVERSITY TURBINE SYSTEMS RESEARCH PROGRAM SUMMARY AND DIRECTORY

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence P. Golan; Richard A. Wenglarz

    2004-07-01

    The South Carolina Institute for Energy Studies (SCIES), administratively housed at Clemson University, has participated in the advancement of combustion turbine technology for over a decade. The University Turbine Systems Research Program, previously referred to as the Advanced Gas Turbine Systems Research (AGTSR) program, has been administered by SCIES for the U.S. DOE during the 1992-2003 timeframe. The structure of the program is based on a concept presented to the DOE by Clemson University. Under the supervision of the DOE National Energy Technology Laboratory (NETL), the UTSR consortium brings together the engineering departments at leading U.S. universities and U.S. combustion turbine developers to provide a solid base of knowledge for the future generations of land-based gas turbines. In the UTSR program, an Industrial Review Board (IRB) (Appendix C) of gas turbine companies and related organizations defines needed gas turbine research. SCIES prepares yearly requests for university proposals to address the research needs identified by the IRB organizations. IRB technical representatives evaluate the university proposals and review progress reports from the awarded university projects. To accelerate technology transfer technical workshops are held to provide opportunities for university, industry and government officials to share comments and improve quality and relevancy of the research. To provide educational growth at the Universities, in addition to sponsored research, the UTSR provides faculty and student fellowships. The basis for all activities--research, technology transfer, and education--is the DOE Turbine Program Plan and identification, through UTSR consortium group processes, technology needed to meet Program Goals that can be appropriately researched at Performing Member Universities.

  14. Waste isolation safety assessment program. Summary of FY-77 progress

    International Nuclear Information System (INIS)

    Burkholder, H.C.; Greenborg, J.; Stottlemyre, J.A.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.

    1977-11-01

    Objective is to provide long-term safety information for the National Waste Terminal Storage Program. Work in FY 77 supported the development of the generic assessment method (release scenario analysis, release consequence analysis) and of the generic data base (waste form release rate data, radionuclide geochemical interaction data)

  15. Biomass Program 2007 Peer Review - Integrated Biorefinery Platform Summary

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2009-10-27

    This document discloses the comments provided by a review panel at the U.S. Department of Energy Office of the Biomass Program Peer Review held on November 15-16, 2007 in Baltimore, MD and the Integrated Biorefinery Platform Review held on August 13-15, 2007 in Golden, Colorado.

  16. Summary of DOE/PERF water program review.

    Energy Technology Data Exchange (ETDEWEB)

    Veil, J.; Gasper, J.; Puder, M.; Leath, P.; Environmental Science Division

    2006-01-31

    For many years, the U.S. Department of Energy (DOE) has supported and sponsored various types of water research relating to the oil and gas industry through its Office of Fossil Energy and its National Energy Technology Laboratory (NETL). In early 2005, the Petroleum Environmental Research Forum (PERF) submitted a proposal to DOE for funding an upcoming PERF meeting that would feature water research in the petroleum industry. PERF is a nonprofit organization created in 1986 to provide a stimulus to and a forum for the collection, exchange, and analysis of research information related to the development of technology concerning the petroleum industry, and a mechanism for establishing joint research projects in that field. Additional information on PERF can be accessed at http://www.perf.org. DOE agreed to provide funding to hold a review of its water research program in conjunction with the fall 2005 PERF meeting. Argonne National Laboratory (Argonne) was asked to coordinate and host the meeting, which was referred to as the DOE/PERF Water Program Review. The program review was held on November 1-4, 2005, in Annapolis, Maryland, at the Historic Inns of Annapolis. The purpose of the program review was to provide a forum for sharing information, reviewing current programs (especially recent unpublished research), and reviewing industry and regulatory needs regarding water use and reuse issues. PERF and DOE/NETL can use this information to plan for future water-related research projects. The water program review provided a unique opportunity in several ways. First, DOE was able to have all of the contractors currently receiving DOE funds for water research present in one room at the same time. Each contractor described his or her research and was able to learn about the research being conducted by the other researchers. Second, this forum allowed representatives of many large oil and gas companies to hear about the DOE research projects and offer their reactions to DOE

  17. Summary of research for the Inertial Confinement Fusion Program at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Cartwright, D.C.

    1985-03-01

    The information presented in this report is a summary of the status of the Inertial Confinement Fusion (ICF) program at the Los Alamos National Laboratory as of February 1985. This report contains material on the existing high-power CO 2 laser driver (Antares), the program to determine the potential of KrF as an ICF driver, heavy-ion accelerators as drivers for ICF, target fabrication for ICF, and a summary of our understanding of laser-plasma interactions. A classified companion report contains material on our current understanding of capsule physics and lists the contributions to the Laboratory's weapons programs made by the ICF program. The information collected in these two volumes is meant to serve as a report on the status of some of the technological components of the Los Alamos ICF program rather than a detailed review of specific technical issues

  18. Program description and summaries of fiscal year 1981 activities

    International Nuclear Information System (INIS)

    1981-10-01

    This Division supports exploratory research on novel concepts related to energy. The research is usually aimed at establishing the scientific feasibility of a concept and, where appropriate, also at estimating its economic viability. Because projects supported inevitably involve a high degree of risk, an indication of a high potential payoff is required. An immediate, specific application of the concept is not an absolute prerequisite for consideration; thus, for example, proposers of schemes leading to the development of x-ray lasers are not required to justify their proposals by discussing potential applications of such lasers. The concepts supported are typically at too early a stage of scientific verification to qualify for funding by DOE programs responsible for technology development. Where doubt exists, such programs are consulted, prior to proposal consideration by AEP, in order to establish their possible interest in the project

  19. Structural aging program -- a summary of activities, results, and conclusions

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.R.

    1997-01-01

    Research has been conducted by the Oak Ridge National Laboratory to address aging management of nuclear power plant concrete structures. The purpose was to identify potential structural safety issues and acceptance criteria for use in continued service assessments. Primary program accomplishments have included formulation of a Structural Materials Information Center that contains data and information on the time variation of material properties under the influence of pertinent environmental stressors and aging factors for 144 materials, an aging assessment methodology to identify critical structures and degradation factors that can potentially impact their performance, guidelines and evaluation criteria for use in condition assessments of reinforced concrete structures, and a reliability-based methodology for current condition assessments and estimations of future performance of reinforced concrete nuclear power plant structures. In addition, the Structural Aging Program conducted in-depth evaluations of several nondestructive evaluation and repair-related technologies to develop guidance on their applicability

  20. Zeolite Vitrification Demonstration Program nonradioactive-process operations summary

    International Nuclear Information System (INIS)

    Bryan, G.H.; Knox, C.A.; Goles, R.G.; Ethridge, L.J.; Siemens, D.H.

    1982-09-01

    The Submerged Demineralizer System is a process developed to decontaminate high-activity level water at Three Mile Island by sorbing the activity (primarily Cs and Sr) onto beds of zeolite. Pacific Northwest Laboratory's Zeolite Vitrification Demonstration Program has the responsibility of demonstrating the full-scale vitrification of this zeolite material. The first phase of this program has been to develop a glass formulation and demonstrate the vitrification process with the use of nonradioactive materials. During this phase, four full-scale nonradioactive demonstration runs were completed. The same zeolite mixture being used in the SDS system was loaded with nonradioactive isotopes of Cs and Sr, dried, blended with glass-forming chemicals and fed to a canister in an in-can melter furnace. During each run, the gaseous effluents were sampled. After each run, glass samples were removed and analyzed

  1. Summary of multi-core hardware and programming model investigations

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, Suzanne Marie; Pedretti, Kevin Thomas Tauke; Levenhagen, Michael J.

    2008-05-01

    This report summarizes our investigations into multi-core processors and programming models for parallel scientific applications. The motivation for this study was to better understand the landscape of multi-core hardware, future trends, and the implications on system software for capability supercomputers. The results of this study are being used as input into the design of a new open-source light-weight kernel operating system being targeted at future capability supercomputers made up of multi-core processors. A goal of this effort is to create an agile system that is able to adapt to and efficiently support whatever multi-core hardware and programming models gain acceptance by the community.

  2. Fission yield data evaluation system FYDES

    International Nuclear Information System (INIS)

    Liu Tingjin

    1998-01-01

    Taking account of some features of fission yield data, to do the fission yield data evaluation conveniently, a fission yield data evaluation system FYDES has been developed for last two years. Outline of the system, data retrieval and data table standardization, data correction codes, data averaging code, simultaneous evaluation code and data fit programs were introduced

  3. Summary of neutron measurements for the Viking Program

    International Nuclear Information System (INIS)

    Anderson, M.E.

    1975-01-01

    The results of neutron measurements for 238 Pu-fueled, 683-W (thermal) capsules fabricated for the Viking Program (Mars Lander) are presented. These results include, for each capsule, the total neutron emission rate and neutron multiplication and, for one capsule, the neutron energy spectrum. A precision long counter was used for the neutron emission rate measurements and a single stilbene crystal for the neutron spectrum measurement. (U.S.)

  4. Summary of national and international radioactive waste management programs

    International Nuclear Information System (INIS)

    Harmon, K.M.

    1979-03-01

    This report summarizes information collected on the status of fuel cycle and waste management programs in Argentina, Australia, Austria, Belgium, Brazil, Canada, China, Denmark, Finland, France, Democratic Republic of Germany, Federal Republic of Germany, India, Iran, Italy, Japan, Mexico, the Netherlands, Pakistan, Spain, Sweden, Switzerland, United Kingdom, United States, and USSR. This compilation attempts to provide current information as of the end of January 1979

  5. Idaho National Laboratory Human Capitol Development Program Summary

    Energy Technology Data Exchange (ETDEWEB)

    Rynes, Amanda R. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    The Next Generation Safeguards Initiative HCD Subprogram has successfully employed unique nuclear capabilities and employee expertise through INL to achieve multiple initiatives in FY14. These opportunities range from internship programs to university and training courses. One of the central facets of this work has been the international safeguards pre inspector training course. Another significant milestone is the INL led university engagement effort which resulted in courses being offered at ISU and University of Utah.

  6. Summary of indicators of Nth country weapon development programs

    International Nuclear Information System (INIS)

    Dougherty, J.E.

    1978-01-01

    A discussion of indicators that various phases of weapon development programs are being carried out is presented. An attempt is made to answer the question ''what observations can be made that would help in deciding whether country X is developing nuclear explosive devices.'' The indicators themselves are accompanied by some general discussions of what is likely to be going on in the areas of nuclear materials ''manufacture,'' nuclear materials chemistry, development and testing, scientific personnel, delivery systems, and evasion of safeguards

  7. Oak Ridge TNS Program: summary of FY 1978 activities

    International Nuclear Information System (INIS)

    Steiner, D.; Becraft, W.R.; Brown, T.G.

    1979-07-01

    The Next Step (TNS) represents the stage of fusion energy development in which the major emphasis is on engineering testing and demonstration. In this document, the activities of the Oak Ridge TNS Program for FY 1978 are described and summarized. The Reference Design that has evolved from these activities is described, its operating characteristics are examined, and project planning issues are considered. Major conclusions from the FY 1978 effort are stated

  8. MHD magnet technology development program summary, September 1982

    Energy Technology Data Exchange (ETDEWEB)

    1983-11-01

    The program of MHD magnet technology development conducted for the US Department of Energy by the Massachusetts Institute of Technology during the past five years is summarized. The general strategy is explained, the various parts of the program are described and the results are discussed. Subjects covered include component analysis, research and development aimed at improving the technology base, preparation of reference designs for commercial-scale magnets with associated design evaluations, manufacturability studies and cost estimations, the detail design and procurement of MHD test facility magnets involving transfer of technology to industry, investigations of accessory subsystem characteristics and magnet-flow-train interfacing considerations and the establishment of tentative recommendations for design standards, quality assurance procedures and safety procedures. A systematic approach (framework) developed to aid in the selection of the most suitable commercial-scale magnet designs is presented and the program status as of September 1982 is reported. Recommendations are made for future work needed to complete the design evaluation and selection process and to provide a sound technological base for the detail design and construction of commercial-scale MHD magnets. 85 references.

  9. MHD magnet technology development program summary, September 1982

    International Nuclear Information System (INIS)

    1983-11-01

    The program of MHD magnet technology development conducted for the US Department of Energy by the Massachusetts Institute of Technology during the past five years is summarized. The general strategy is explained, the various parts of the program are described and the results are discussed. Subjects covered include component analysis, research and development aimed at improving the technology base, preparation of reference designs for commercial-scale magnets with associated design evaluations, manufacturability studies and cost estimations, the detail design and procurement of MHD test facility magnets involving transfer of technology to industry, investigations of accessory subsystem characteristics and magnet-flow-train interfacing considerations and the establishment of tentative recommendations for design standards, quality assurance procedures and safety procedures. A systematic approach (framework) developed to aid in the selection of the most suitable commercial-scale magnet designs is presented and the program status as of September 1982 is reported. Recommendations are made for future work needed to complete the design evaluation and selection process and to provide a sound technological base for the detail design and construction of commercial-scale MHD magnets. 85 references

  10. Final summary report on the Peach Bottom End-of-Life Program

    International Nuclear Information System (INIS)

    Steward, K.P.

    1978-07-01

    HTGR design methods verifications have been performed under the Peach Bottom End-of-Life Program by comparison of actual with predicted physics, thermal, fission product, and materials behavior in Peach Bottom. These design methods verifications have utilized the data determined from nondestructive fuel and circuit gamma scanning on-site, from laboratory examinations of samples removed from the primary circuit, and from a complementary program of Peach Bottom fuel element postirradiation examinations at Oak Ridge National Laboratory. Fifty-five driver fuel elements were axially gamma scanned to determine fission product distributions for use in burnup calculations, power profile determinations, and fission product release and redistribution studies. The cesium plateout distribution in the primary circuit was subsequently mapped by gamma scanning the ducting at 12 locations, axially traversing 79 steam generator tubes with Cd Te detectors from the water side, and internally scanning two vertical runs of ducting. Component removal involved trepanning of the primary circuit ducting, obtaining access to the steam generator internals, and removing over 100 superheater, evaporator, and economizer tubing samples. During this phase, macroscopic examinations of the steam generator and ducting internals were performed. Subsequent laboratory examinations of removed samples included radiochemical tests to substantiate in-situ gamma scans and to determine 90 Sr distributions; metallurgical tests to evaluate surface films, microstructural changes, and residual mechanical properties; and tritium permeation tests to provide data for improving HTGR tritium release predictions. The condition and metallurgical integrity of all components examined were found to be excellent, with minimal coolant/substrate interaction and entirely acceptable residual mechanical properties. The suitability of the materials used in the construction of the Peach Bottom HTGR was thereby confirmed

  11. Measurement of Fission Product Yields from Fast-Neutron Fission

    Science.gov (United States)

    Arnold, C. W.; Bond, E. M.; Bredeweg, T. A.; Fowler, M. M.; Moody, W. A.; Rusev, G.; Vieira, D. J.; Wilhelmy, J. B.; Becker, J. A.; Henderson, R.; Kenneally, J.; Macri, R.; McNabb, D.; Ryan, C.; Sheets, S.; Stoyer, M. A.; Tonchev, A. P.; Bhatia, C.; Bhike, M.; Fallin, B.; Gooden, M. E.; Howell, C. R.; Kelley, J. H.; Tornow, W.

    2014-09-01

    One of the aims of the Stockpile Stewardship Program is a reduction of the uncertainties on fission data used for analyzing nuclear test data [1,2]. Fission products such as 147Nd are convenient for determining fission yields because of their relatively high yield per fission (about 2%) and long half-life (10.98 days). A scientific program for measuring fission product yields from 235U,238U and 239Pu targets as a function of bombarding neutron energy (0.1 to 15 MeV) is currently underway using monoenergetic neutron beams produced at the 10 MV Tandem Accelerator at TUNL. Dual-fission chambers are used to determine the rate of fission in targets during activation. Activated targets are counted in highly shielded HPGe detectors over a period of several weeks to identify decaying fission products. To date, data have been collected at neutron bombarding energies 4.6, 9.0, 14.5 and 14.8 MeV. Experimental methods and data reduction techniques are discussed, and some preliminary results are presented.

  12. Efficient Separations and Processing Crosscutting Program. Technology summary

    International Nuclear Information System (INIS)

    1995-06-01

    The Efficient Separations and Processing (ESP) Crosscutting Program was created in 1991 to identify, develop, and perfect separations technologies and processes to treat wastes and address environmental problems throughout the DOE Complex. The ESP funds several multi-year tasks that address high-priority waste remediation problems involving high-level, low-level, transuranic, hazardous, and mixed (radioactive and hazardous) wastes. The ESP supports applied research and development (R and D) leading to demonstration or use of these separations technologies by other organizations within DOE-EM. Treating essentially all DOE defense wastes requires separation methods that concentrate the contaminants and/or purify waste streams for release to the environment or for downgrading to a waste form less difficult and expensive to dispose of. Initially, ESP R and D efforts focused on treatment of high-level waste (HLW) from underground storage tanks (USTs) because of the potential for large reductions in disposal costs and hazards. As further separations needs emerge and as waste management and environmental restoration priorities change, the program has evolved to encompass the breadth of waste management and environmental remediation problems

  13. ENVIRONMENTAL MONITORING AND ASSESSMENT PROGRAM (EMAP): WESTERN STREAMS AND RIVERS STATISTICAL SUMMARY

    Science.gov (United States)

    This statistical summary reports data from the Environmental Monitoring and Assessment Program (EMAP) Western Pilot (EMAP-W). EMAP-W was a sample survey (or probability survey, often simply called 'random') of streams and rivers in 12 states of the western U.S. (Arizona, Californ...

  14. FWP executive summaries: basic energy sciences materials sciences and engineering program (SNL/NM).

    Energy Technology Data Exchange (ETDEWEB)

    Samara, George A.; Simmons, Jerry A.

    2006-07-01

    This report presents an Executive Summary of the various elements of the Materials Sciences and Engineering Program which is funded by the Division of Materials Sciences and Engineering, Office of Basic Energy Sciences, U.S. Department of Energy at Sandia National Laboratories, New Mexico. A general programmatic overview is also presented.

  15. NRC research program on plant aging: Listing and summaries of reports issued through July 1992

    International Nuclear Information System (INIS)

    Kondic, N.N.

    1992-09-01

    The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research program focused on understanding the aging mechanisms of components and systems in nuclear power plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. In addition, it provides recommendations for effective maintenance to manage aging and for implementation of the research results in the regulatory process. This document contains a listing and index of reports generated in the NPAR Program that were issued through July 1992 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject

  16. NRC Research Program on Plant Aging: Listing and summaries of reports issued through June 1991

    International Nuclear Information System (INIS)

    Kondic, N.N.; Hill, E.L.

    1991-07-01

    The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research program focused on understanding the aging mechanisms of components and systems in nuclear power plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. In addition, it provides recommendations for effective maintenance to manage aging and for the implementation of the research results in the regulatory process. This document contains a listing and index of reports generated in the NPAR Program that were issued through June 1991 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject. 102 refs

  17. NRC research program on plant aging: Listing and summaries of reports issued through May 1990

    International Nuclear Information System (INIS)

    Kondic, N.N.; Hill, E.L.

    1990-07-01

    The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research program focused on understanding the aging mechanisms of components and systems in nuclear plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. In addition, it provides recommendations for effective maintenance to manage aging and for the implementation of the research results in the regulatory process. This document contains a listing and index of reports generated in the NPAR Program that were issued through May 1990 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject

  18. Characterization, monitoring, and sensor technology crosscutting program: Technology summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The purpose of the Characterization, Monitoring, and Sensor Technology Crosscutting Program (CMST-CP) is to deliver appropriate characterization, monitoring, and sensor technology (CMST) to the Office of Waste Management (EM-30), the Office of Environmental Restoration (EM-40), and the Office of Facility Transition and Management (EM-60). The technology development must also be cost effective and appropriate to EM-30/40/60 needs. Furthermore, the required technologies must be delivered and implemented when needed. Accordingly, and to ensure that available DOE and other national resources are focused an the most pressing needs, management of the technology development is concentrated on the following Focus Areas: Contaminant Plume Containment and Remediation (PFA); Landfill Stabilization (LSFA); High-Level Waste Tank Remediation (TFA); Mixed Waste Characterization, Treatment, and Disposal (MWFA); and Facility Deactivation, Decommissioning, and Material Disposition (FDDMDFA). Brief descriptions of CMST-CP projects funded in FY95 are presented.

  19. Characterization, monitoring, and sensor technology crosscutting program: Technology summary

    International Nuclear Information System (INIS)

    1995-06-01

    The purpose of the Characterization, Monitoring, and Sensor Technology Crosscutting Program (CMST-CP) is to deliver appropriate characterization, monitoring, and sensor technology (CMST) to the Office of Waste Management (EM-30), the Office of Environmental Restoration (EM-40), and the Office of Facility Transition and Management (EM-60). The technology development must also be cost effective and appropriate to EM-30/40/60 needs. Furthermore, the required technologies must be delivered and implemented when needed. Accordingly, and to ensure that available DOE and other national resources are focused an the most pressing needs, management of the technology development is concentrated on the following Focus Areas: Contaminant Plume Containment and Remediation (PFA); Landfill Stabilization (LSFA); High-Level Waste Tank Remediation (TFA); Mixed Waste Characterization, Treatment, and Disposal (MWFA); and Facility Deactivation, Decommissioning, and Material Disposition (FDDMDFA). Brief descriptions of CMST-CP projects funded in FY95 are presented

  20. Urban Dispersion Program Overview and MID05 Field Study Summary

    Energy Technology Data Exchange (ETDEWEB)

    Allwine, K Jerry; Flaherty, Julia E.

    2007-07-31

    The Urban Dispersion Program (UDP) was a 4-year project (2004–2007) funded by the U.S. Department of Homeland Security with additional support from the Defense Threat Reduction Agency. The U.S. Environmental Protection Agency (EPA) also contributed to UDP through funding a human-exposure component of the New York City (NYC) field studies in addition to supporting an EPA scientist in conducting modeling studies of NYC. The primary goal of UDP was to improve the scientific understanding of the flow and diffusion of airborne contaminants through and around the deep street canyons of NYC. The overall UDP project manager and lead scientist was Dr. Jerry Allwine of Pacific Northwest National Laboratory. UDP had several accomplishments that included conducting two tracer and meteorological field studies in Midtown Manhattan.

  1. A summary description of the flammable gas tank safety program

    International Nuclear Information System (INIS)

    Johnson, G.D.; Sherwood, D.J.

    1994-10-01

    Radioactive liquid waste may produce hydrogen as result of the interaction of gamma radiation and water. If the waste contains organic chelating agents, additional hydrogen as well as nitrous oxide and ammonia may be produced by thermal and radiolytic decomposition of these organics. Several high-level radioactive liquid waste storage tanks, located underground at the Hanford Site in Washington State, are on a Flammable Gas Watch List. Some contain waste that produces and retains gases until large quantities of gas are released rapidly to the tank vapor space. Tanks nearly-filled to capacity have relatively little vapor space; therefore if the waste suddenly releases a large amount of hydrogen and nitrous oxide, a flammable gas mixture could result. The most notable example of a Hanford waste tank with a flammable gas problem is tank 241-SY-101. Upon occasion waste stored in this tank has released enough flammable gas to burn if an ignition source had been present inside of the tank. Several, other Hanford waste tanks exhibit similar behavior although to a lesser magnitude. Because this behavior was hot adequately-addressed in safety analysis reports for the Hanford Tank Farms, an unreviewed safety question was declared, and in 1990 the Flammable Gas Tank Safety Program was established to address this problem. The purposes of the program are a follows: (1) Provide safety documents to fill gaps in the safety analysis reports, and (2) Resolve the safety issue by acquiring knowledge about gas retention and release from radioactive liquid waste and developing mitigation technology. This document provides the general logic and work activities required to resolve the unreviewed safety question and the safety issue of flammable gas mixtures in radioactive liquid waste storage tanks

  2. Summary report on the Seismic Safety Margins Research Program

    International Nuclear Information System (INIS)

    Cummings, G.E.

    1986-01-01

    The Seismic Safety Margins Research Program (SSMRP) was a program to develop a complete, fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. The SSMRP was the first effort to trace seismically induced failure modes in a reactor system down to the individual component level, and to take into account common-cause earthquake-induced failures at the component level. This report summarizes methods and results generated by SSMRP. The SSMRP method makes use of three computer codes, HAZARD, SMACS and SEISIM to calculate ground motion acceleration time histories, structure and component responses and failure, and radioactive release probabilities. To demonstrate the methodology, an analysis was done of the Zion Nuclear Power Plant. The median frequency of core melt was computed to be 3E-5 per year, with upper (90%) and lower (10%) bounds of 8E-4 and 6E-7 per year. The main contribution to risk came from earthquakes about 2 through 4 times the design basis earthquake level. Risk was dominated by structural and inter-building piping failures and loss of off-site power. Sensitivity studies were undertaken to test assumptions and modeling procedures relative to soil-structure interaction effects, feed-and-bleed cooling, and structural failures. Assumptions made could have an order-of-magnitude effect on core melt frequency. Also, guidelines were developed for simplifying the SSMRP method, and importance rankings were generated based on the Zion analysis. 56 refs., 6 figs

  3. Capture and fission with DANCE and NEUANCE

    Energy Technology Data Exchange (ETDEWEB)

    Jandel, M.; Baramsai, B.; Bond, E.; Rusev, G.; Walker, C.; Bredeweg, T.A.; Chadwick, M.B.; Couture, A.; Fowler, M.M.; Hayes, A.; Kawano, T.; Mosby, S.; Stetcu, I.; Taddeucci, T.N.; Talou, P.; Ullmann, J.L.; Vieira, D.J.; Wilhelmy, J.B. [Los Alamos National Laboratory, Los Alamos, New Mexico (United States)

    2015-12-15

    A summary of the current and future experimental program at DANCE is presented. Measurements of neutron capture cross sections are planned for many actinide isotopes with the goal to reduce the present uncertainties in nuclear data libraries. Detailed studies of capture gamma rays in the neutron resonance region will be performed in order to derive correlated data on the de-excitation of the compound nucleus. New approaches on how to remove the DANCE detector response from experimental data and retain the correlations between the cascade gamma rays are presented. Studies on {sup 235}U are focused on quantifying the population of short-lived isomeric states in {sup 236}U after neutron capture. For this purpose, a new neutron detector array NEUANCE is under construction. It will be installed in the central cavity of the DANCE array and enable the highly efficient tagging of fission and capture events. In addition, developments of fission fragment detectors are also underway to expand DANCE capabilities to measurements of fully correlated data on fission observables. (orig.)

  4. XII All-Russian conference on gas chromatography. Program. Summary of reports

    International Nuclear Information System (INIS)

    2002-01-01

    Program and summary of reports of the XII All-Russian conference on gas chromatography are performed. The conference took place in Samara, 10-14 June, 2002. Reports on physicochemical regularities of gas chromatography, application of chromatographic methods in atomic energetics are included in the program of the conference. Part of the reports are deleted to the analytical application of the gas chromatography. Adsorbents for the gas chromatography, complex methods, mathematic methods in chromatography, ecological aspects of the gas chromatography [ru

  5. A suitability study of the fission product phantom and the bottle manikin absorption phantom for calibration of in vivo bioassay equipment for the DOELAP accreditation testing program

    International Nuclear Information System (INIS)

    Olsen, P.C.; Lynch, T.P.

    1991-08-01

    Pacific Northwest laboratory (PNL) conducted an intercomparison study of the Fission Product phantom and the bottle manikin absorption (BOMAB) phantom for the US Department of Energy (DOE) to determine the consistency of calibration response of the two phantoms and their suitability for certification and use under a planned bioassay laboratory accreditation program. The study was initiated to determine calibration factors for both types of phantoms and to evaluate the suitability of their use in DOE Laboratory Accreditation Program (DOELAP) round-robin testing. The BOMAB was found to be more appropriate for the DOELAP testing program. 9 refs., 9 figs., 9 tabs

  6. The 3D Elevation Program: summary for Kentucky

    Science.gov (United States)

    Carswell, William J.

    2014-01-01

    Elevation data are essential to a broad range of applications, including forest resources management, wildlife and habitat management, national security, recreation, and many others. For the Commonwealth of Kentucky, elevation data are critical for agriculture and precision farming, natural resources conservation, flood risk management, infrastructure and construction management, forest resources management, geologic resource assessment and hazards mitigation, and other business uses. Today, high-density light detection and ranging (lidar) data are the primary sources for deriving elevation models and other datasets. Federal, State, Tribal, and local agencies work in partnership to (1) replace data that are older and of lower quality and (2) provide coverage where publicly accessible data do not exist. A joint goal of State and Federal partners is to acquire consistent, statewide coverage to support existing and emerging applications enabled by lidar data. “Kentucky from Above,” the Kentucky Aerial Photography and Elevation Data Program (http://kygeonet.ky.gov/kyfromabove/), provides statewide lidar coordination with local, Commonwealth, and national groups in support of 3DEP for the Commonwealth.

  7. The 3D Elevation Program: summary for Rhode Island

    Science.gov (United States)

    Carswell, William J.

    2013-01-01

    Elevation data are essential to a broad range of applications, including forest resources management, wildlife and habitat management, national security, recreation, and many others. For the State of Rhode Island, elevation data are critical for flood risk management, natural resources conservation, coastal zone management, sea level rise and subsidence, agriculture and precision farming, and other business uses. Today, high-quality light detection and ranging (lidar) data are the sources for creating elevation models and other elevation datasets. Federal, State, and local agencies work in partnership to (1) replace data, on a national basis, that are (on average) 30 years old and of lower quality and (2) provide coverage where publicly accessible data do not exist. A joint goal of State and Federal partners is to acquire consistent, statewide coverage to support existing and emerging applications enabled by lidar data. The new 3D Elevation Program (3DEP) initiative (Snyder, 2012a,b), managed by the U.S. Geological Survey (USGS), responds to the growing need for high-quality topographic data and a wide range of other three-dimensional representations of the Nation’s natural and constructed features.

  8. The 3D Elevation Program: summary for Wisconsin

    Science.gov (United States)

    Carswell, William J.

    2013-01-01

    Elevation data are essential to a broad range of applications, including forest resources management, wildlife and habitat management, national security, recreation, and many others. For the State of Wisconsin, elevation data are critical for agriculture and precision farming, natural resources conservation, flood risk management, infrastructure and construction management, water supply and quality, and other business uses. Today, high-quality light detection and ranging (lidar) data are the sources for creating elevation models and other elevation datasets. Federal, State, and local agencies work in partnership to (1) replace data, on a national basis, that are (on average) 30 years old and of lower quality and (2) provide coverage where publicly accessible data do not exist. A joint goal of State and Federal partners is to acquire consistent, statewide coverage to support existing and emerging applications enabled by lidar data. The new 3D Elevation Program (3DEP) initiative, managed by the U.S. Geological Survey (USGS), responds to the growing need for high-quality topographic data and a wide range of other three-dimensional representations of the Nation’s natural and constructed features.

  9. The 3D Elevation Program: summary for Virginia

    Science.gov (United States)

    Carswell, William J.

    2013-01-01

    Elevation data are essential to a broad range of applications, including forest resources management, wildlife and habitat management, national security, recreation, and many others. For the Commonwealth of Virginia, elevation data are critical for urban and regional planning, natural resources conservation, flood risk management, agriculture and precision farming, resource mining, infrastructure and construction management, and other business uses. Today, high-quality light detection and ranging (lidar) data are the sources for creating elevation models and other elevation datasets. Federal, State, and local agencies work in partnership to (1) replace data, on a national basis, that are (on average) 30 years old and of lower quality and (2) provide coverage where publicly accessible data do not exist. A joint goal of State and Federal partners is to acquire consistent, statewide coverage to support existing and emerging applications enabled by lidar data. The new 3D Elevation Program (3DEP) initiative, managed by the U.S. Geological Survey (USGS), responds to the growing need for high-quality topographic data and a wide range of other three-dimensional representations of the Nation’s natural and constructed features.

  10. The 3D Elevation Program: summary for Minnesota

    Science.gov (United States)

    Carswell, William J.

    2013-01-01

    Elevation data are essential to a broad range of applications, including forest resources management, wildlife and habitat management, national security, recreation, and many others. For the State of Minnesota, elevation data are critical for agriculture and precision farming, natural resources conservation, flood risk management, infrastructure and construction management, water supply and quality, coastal zone management, and other business uses. Today, high-quality light detection and ranging (lidar) data are the sources for creating elevation models and other elevation datasets. Federal, State, and local agencies work in partnership to (1) replace data, on a national basis, that are (on average) 30 years old and of lower quality and (2) provide coverage where publicly accessible data do not exist. A joint goal of State and Federal partners is to acquire consistent, statewide coverage to support existing and emerging applications enabled by lidar data. The new 3D Elevation Program (3DEP) initiative, managed by the U.S. Geological Survey (USGS), responds to the growing need for high-quality topographic data and a wide range of other three-dimensional representations of the Nation’s natural and constructed features.

  11. Hanford Site performance summary -- EM funded programs, July 1995

    International Nuclear Information System (INIS)

    Schultz, E.A.

    1995-07-01

    Performance data for July 1995 reflects a 4% unfavorable schedule variance and is an improvement over June 1995. The majority of the behind schedule condition is attributed to EM-30, (Office of Waste Management). The majority of the EM-30 schedule variance is associated with the Tank Waste Remediation System (TWRS) Program. The TWRS schedule variance is attributed to the delay in obtaining key decision 0 (KD-0) for Project W-314, ''Tank Farm Restoration and Safe Operations'' and the Multi-Function Waste Tank Facility (MWTF) workscope still being a part of the baseline. Baseline Change Requests (BCRs) are in process rebaselining Project W-314 and deleting the MWTF from the TWRS baseline. Once the BCR's are approved and implemented, the overall schedule variance will be reduced to $15.0 million. Seventy-seven enforceable agreement milestones were scheduled FYTD. Seventy-one (92%) of the seventy-seven were completed on or ahead of schedule, two were completed late and four are delinquent. Performance data reflects a continued significant favorable cost variance of $124.3 million (10%). The cost variance is attributed to process improvements/efficiencies, elimination of low-value work, workforce reductions and is expected to continue for the remainder of this fiscal year. A portion of the cost variance is attributed to a delay in billings which should self-correct by fiscal year-end

  12. Office of Industrial Technologies: Summary of program results

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-01-01

    Working in partnership with industry, the US Department of Energy`s (DOE`s) Office of Industrial Technologies (OIT) is helping reduce industrial energy use, emissions, and waste while boosting productivity. Operating within the Office of Energy Efficiency and Renewable Energy (EE), OIT conducts research, development, demonstration, and technology transfer efforts that are producing substantial, measurable benefits to industry. This document summarizes some of the impacts of OIT`s programs through 1997. OIT tracks energy savings as well as other benefits associated with the successfully commercialized technologies resulting from OIT-supported research partnerships. Specifically, a chart shows current and cumulative energy savings as well as cumulative reductions of various air pollutants including particulates, volatile organic compounds (VOCs), nitrogen oxides (NO{sub x}), sulfur oxides (SO{sub x}), and the greenhouse gas, carbon dioxide (CO{sub 2}). The bulk of the document consists of four appendices. Appendix 1 describes the technologies currently available commercially, along with their applications and benefits; Appendix 2 describes the OIT-supported emerging technologies that are likely to be commercialized within the next year or two; Appendix 3 describes OIT-sponsored technologies used in commercial applications in the past that are no longer tracked; and Appendix 4 describes the methodology used to assess and track OIT-supported technologies.

  13. Summary of theory and techniques, sample selection and project organization for potassium-argon, rubidium-strontium and fission track dating and strontium isotope studies

    International Nuclear Information System (INIS)

    Adams, C.J.; Graham, I.J.; Seward, D.

    1987-02-01

    A brief outline is given of the theory and techniques of the potassium-argon, rubidium-strontium and fission-track dating methods and related isotope studies which are currently in use at the Institute of Nuclear Sciences, DSIR. Some limitations of each technique are set out in terms of age range and materials for dating, and the appropriate choice of various mineral and rock types and subsequent age interpretations are discussed. The organisation of project proposals and categories is described and procedures for sample submission and documentation are given

  14. The 3D Elevation Program: summary for Hawaii

    Science.gov (United States)

    Carswell, William J.

    2016-01-01

    Elevation data are essential to a broad range of applications, including forest resources management, wildlife and habitat management, national security, recreation, and many others. For the State of Hawaii, elevation data are critical for infrastructure and construction management, flood risk management, geologic resource assessment and hazard mitigation, natural resources conservation, coastal zone management, and other business uses. Today, high-density light detection and ranging (lidar) data are the primary sources for deriving elevation models and other datasets. Federal, State, Tribal, U.S. territorial, and local agencies work in partnership to (1) replace data that are older and of lower quality and (2) provide coverage where publicly accessible data do not exist. A joint goal of State and Federal partners is to acquire consistent, statewide coverage to support existing and emerging applications enabled by lidar data.The National Enhanced Elevation Assessment evaluated multiple elevation data acquisition options to determine the optimal data quality and data replacement cycle relative to cost to meet the identified requirements of the user community. The evaluation demonstrated that lidar acquisition at quality level 2 for the conterminous United States, Hawaii, and selected U.S. territories, and quality level 5 interferometric synthetic aperture radar (IfSAR) data for Alaska, all with a 6- to 10-year acquisition cycle, provided the highest benefit/cost ratios. The 3D Elevation Program (3DEP) initiative selected an 8-year acquisition cycle for the respective quality levels. 3DEP, managed by the U.S. Geological Survey, the Office of Management and Budget Circular A–16 lead agency for terrestrial elevation data, responds to the growing need for high-quality topographic data and a wide range of other three-dimensional (3D) representations of the Nation’s natural and constructed features.

  15. The 3D Elevation Program: summary for Puerto Rico

    Science.gov (United States)

    Carswell, William J.

    2016-02-03

    Elevation data are essential to a broad range of applications, including forest resources management, wildlife and habitat management, scientific research, national security, recreation, and many others. For the Commonwealth of Puerto Rico, elevation data are critical for flood risk management, landslide mitigation, natural resources conservation, sea level rise and subsidence, coastal zone management, infrastructure and construction management, and other business uses. Today, high-density light detection and ranging (lidar) data are the primary sources for deriving elevation models and other datasets. Federal, State, Tribal, U.S. territorial, and local agencies work in partnership to (1) replace data that are older and of lower quality and (2) provide coverage where publicly accessible data do not exist. A joint goal of State and Federal partners is to acquire consistent, statewide coverage to support existing and emerging applications enabled by lidar data.The National Enhanced Elevation Assessment evaluated multiple elevation data acquisition options to determine the optimal data quality and data replacement cycle relative to cost to meet the identified requirements of the user community. The evaluation demonstrated that lidar acquisition at quality level 2 for the conterminous United States, Hawaii, and selected U.S. territories, and quality level 5 interferometric synthetic aperture radar (IfSAR) data for Alaska, all with a 6- to 10-year acquisition cycle, provided the highest benefit/cost ratios. The 3D Elevation Program (3DEP) initiative selected an 8-year acquisition cycle for the respective quality levels. 3DEP, managed by the U.S. Geological Survey (USGS), the Office of Management and Budget Circular A‒16 lead agency for terrestrial elevation data, responds to the growing need for high-quality topographic data and a wide range of other three-dimensional (3D) representations of the Nation’s natural and constructed features.

  16. Ternary fission

    Indian Academy of Sciences (India)

    the energy minimization of all possible ternary breakups of a heavy radioactive nucleus. Further, within the TCM we have analysed the competition between different geometries as well as different positioning of the fragments. Also, an attempt was made to calculate the mass distribution of ternary fission process within the ...

  17. High-safety and economical small molten-salt fission power stations and their developmental program

    International Nuclear Information System (INIS)

    Furukawa, K.; Mitachi, K.; Minami, K.; Kato, Y.

    1988-01-01

    The nuclear energy industry is not settled yet as one of the sound economical industries. Its establishment should obviously depend on the solution of the following problems: ''natural'' safety (depending on inherent natures), nuclear proliferation resistance - nearly non-production and effective incineration of Pu, Am and Om, universal resource, flexible power-size and excellent economy - wide applicability including Developing Countries. Therefore, some essentially new principles have to introduce in the nuclear energy system design. These are thorium utilization, fluid-fuel concepts, especially molten-fluoride technology, and separation of fissile-breeding and power-generation. This philosophy is named Thorium Molten-Salt Nuclear Energy Synergetics [THOMSNES]. Its practical development program is presented

  18. Subseabed disposal program annual report, January-December 1979. Volume I. Summary and status

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1981-08-01

    This is the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program, which was begun in June 1973. The program was initiated by Sandia National Laboratories to explore the utility of stable, uniform, and relatively unproductive areas of the world's oceans as possible repositories for high-level nuclear wastes. The program, now international in scope, is currently focused on the stable submarine geologic formations under the deep oceans. Summaries are presented in the following areas: systems analysis; barrier system characterization and assessment; environmental studies; emplacement; sampling and instrumentation development; and transportation studies

  19. Environmental hazards assessment program. Summary report, June 23, 1992--September 30, 1997

    International Nuclear Information System (INIS)

    1997-01-01

    This summary report describes activities and reports for the grant period from June 1992 to September 1997. It reports progress against grant objectives and the Program Implementation Plan published during the first year of the grant program. The program consists of six major elements: (1) public and professional outreach, (2) clinical science, (3) biomedical research, (4) information systems, (5) education, and (6) community development. Research is focused on toxicological and epidemiological investigation into environmental problems that pose a direct risk to human health, and methods to translate basic research into risk assessment and preventive medicine applications for health care providers

  20. Spent fuel sabotage aerosol test program :FY 2005-06 testing and aerosol data summary

    International Nuclear Information System (INIS)

    Gregson, Michael Warren; Brockmann, John E.; Nolte, O.; Loiseau, O.; Koch, W.; Molecke, Martin Alan; Autrusson, Bruno; Pretzsch, Gunter Guido; Billone, M. C.; Lucero, Daniel A.; Burtseva, T.; Brucher, W; Steyskal, Michele D.

    2006-01-01

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program has been underway for several years. This program provides source-term data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assessments. This document focuses on an updated description of the test program and test components for all work and plans made, or revised, primarily during FY 2005 and about the first two-thirds of FY 2006. It also serves as a program status report as of the end of May 2006. We provide details on the significant findings on aerosol results and observations from the recently completed Phase 2 surrogate material tests using cerium oxide ceramic pellets in test rodlets plus non-radioactive fission product dopants. Results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; status on determination of the spent fuel ratio, SFR (the ratio of respirable particles from real spent fuel/respirables from surrogate spent fuel, measured under closely matched test conditions, in a contained test chamber); and, measurements of enhanced volatile fission product species sorption onto respirable particles. We discuss progress and results for the first three, recently performed Phase 3 tests using depleted uranium oxide, DUO 2 , test rodlets. We will also review the status of preparations and the final Phase 4 tests in this program, using short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. These data plus testing results and design are tailored to support and guide, follow-on computer modeling of aerosol dispersal hazards and radiological consequence assessments

  1. United States Nuclear Regulatory Commission research program on core debris/concrete interactions and ex-vessel fission-product release

    International Nuclear Information System (INIS)

    Burson, S.B.

    1987-01-01

    The study of core debris/concrete interaction phenomena has been a significant element of the NRC's Severe Accident Research Program for a number of years. The CORCON and VANESA codes used to predict the consequences of high-temperature debris attack on concrete and fission-product aerosol release are state-of-the-art computational tools. The major thrust of current NRC sponsored research focuses on the refinement, verification, and validation of these codes. An overview of the analytical and experimental aspects of the NRC research program is presented

  2. Summary of NRC LWR safety research programs on fuel behavior, metallurgy/materials and operational safety

    International Nuclear Information System (INIS)

    Bennett, G.L.

    1979-09-01

    The NRC light-water reactor safety-research program is part of the NRC regulatory program for ensuring the safety of nuclear power plants. This paper summarizes the results of NRC-sponsored research into fuel behavior, metallurgy and materials, and operational safety. The fuel behavior research program provides a detailed understanding of the response of nuclear fuel assemblies to postulated off-normal or accident conditions. Fuel behavior research includes studies of basic fuel rod properties, in-reactor tests, computer code development, fission product release and fuel meltdown. The metallurgy and materials research program provides independent confirmation of the safe design of reactor vessels and piping. This program includes studies on fracture mechanics, irradiation embrittlement, stress corrosion, crack growth, and nondestructive examination. The operational safety research provides direct assistance to NRC officials concerned with the operational and operational-safety aspects of nuclear power plants. The topics currently being addressed include qualification testing evaluation, fire protection, human factors, and noise diagnostics

  3. Fission meter

    Science.gov (United States)

    Rowland, Mark S [Alamo, CA; Snyderman, Neal J [Berkeley, CA

    2012-04-10

    A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source.

  4. Executive Summary: 30th Report on Physician Assistant Educational Programs in the United States.

    Science.gov (United States)

    Huang, Lindsey M

    2015-09-01

    The purpose of this executive summary was to provide an overview of key findings from By the Numbers: 30th Report on Physician Assistant Educational Programs in the United States. The 2014 Program Survey is a Web-based survey and is administered annually to all member physician assistant (PA) program directors. This executive summary will focus on 4 of the 7 sections of the survey instrument: general, financial, program personnel, and students. The typical PA program's sponsoring institution is private and in a nonacademic health center. Most PA programs (93.0%) offer a master's degree as the primary or highest credential. The average total program budget was $2,221,751 (SD=$2,426,852). The average total resident tuition was $64,961, and the average total nonresident tuition was $75,964. Overall, 181 programs reported 1843 program faculty. Of those, 1467 were identified as core faculty and 376 were identified as adjunct faculty. A typical first-year PA student is 26 years old (SD=2.51), female (70.3%, n=5898), non-Hispanic (89.3%, n=3631), White (79.9%, n=3712), and has an overall undergraduate and science grade point average (GPA) of 3.52 (SD=0.14) and 3.47 (SD=0.16), respectively. In 2014, there were approximately 7556 graduates from 164 responding programs. By gaining a better understanding of the characteristics of PA programs and their faculty and students, policy makers can be better informed. Physician assistant educators and stakeholders are encouraged to use this information to advance and advocate for the profession.

  5. A summary of the environmental restoration program retrieval demonstration project at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    McQuary, J.

    1991-02-01

    This report provides a summary of the Environmental Restoration Program's Retrieval Demonstration Project at the Idaho National Engineering Laboratory. This project developed concepts for demonstrating facilities and equipment for the retrieval of buried transuranic mixed waste at the INEL. Included is a brief assessment of the viability, cost effectiveness, and safety of retrieval based on the developed concept. Changes made in Revision 1 reflect editorial changes only. 31 refs., 1 fig

  6. VIII All-Russian symposium on molecular liquid chromatography and capillary electrophoresis. Program. Summary of reports

    International Nuclear Information System (INIS)

    2001-01-01

    Program and summary of reports of the VIII All-Russian symposium on molecular liquid chromatography and capillary electrophoresis are performed. The meeting took place 15-19 October, 2001 in Moscow. Many problems of liquid and ion exchange chromatography, capillary electrophoresis, thin-layer chromatography have been discussed extensively. Reports covering properties of sorbents and devices for chromatography are incorporated in the collection [ru

  7. Hydrogen Energy Coordinating Committee annual report: Summary of DOE hydrogen programs for FY 1991

    International Nuclear Information System (INIS)

    1991-07-01

    The HECC was established over 13 years ago to ensure that the many varied aspects of hydrogen technology within the Department are coordinated. Each year the committee brings together technical representative within the Department to coordinate activities, share research results and discuss future priorities and directions. This FY 1990 summary is the thirteenth consecutive yearly report. It provides an overview of the hydrogen-related programs of the DOE offices represented in the HECC for the fiscal year. For the purposes of this report, the research projects within each division have been organized into two categories: Fuels-related Research and Non-fuels-related Research. An historical summary of the hydrogen budgets of the several divisions is given. Total DOE funding in FY 1990 was $6.8 million for fuels-related research and $32.9 million for non-fuels-related research. The individual program elements are described in the body of this report, and more specific program information can be found in the Technology Summary Forms in Appendix A

  8. Spent fuel sabotage aerosol ratio program : FY 2004 test and data summary

    International Nuclear Information System (INIS)

    Brucher, Wenzel; Koch, Wolfgang; Pretzsch, Gunter Guido; Loiseau, Olivier; Mo, Tin; Billone, Michael C.; Autrusson, Bruno A.; Young, F. I.; Coats, Richard Lee; Burtseva, Tatiana; Luna, Robert Earl; Dickey, Roy R.; Sorenson, Ken Bryce; Nolte, Oliver; Thompson, Nancy Slater; Hibbs, Russell S.; Gregson, Michael Warren; Lange, Florentin; Molecke, Martin Alan; Tsai, Han-Chung

    2005-01-01

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program has been underway for several years. This program provides data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assessments. The program also provides significant technical and political benefits in international cooperation. We are quantifying the Spent Fuel Ratio (SFR), the ratio of the aerosol particles released from HEDD-impacted actual spent fuel to the aerosol particles produced from surrogate materials, measured under closely matched test conditions, in a contained test chamber. In addition, we are measuring the amounts, nuclide content, size distribution of the released aerosol materials, and enhanced sorption of volatile fission product nuclides onto specific aerosol particle size fractions. These data are the input for follow-on modeling studies to quantify respirable hazards, associated radiological risk assessments, vulnerability assessments, and potential cask physical protection design modifications. This document includes an updated description of the test program and test components for all work and plans made, or revised, during FY 2004. It also serves as a program status report as of the end of FY 2004. All available test results, observations, and aerosol analyses plus interpretations--primarily for surrogate material Phase 2 tests, series 2/5A through 2/9B, using cerium oxide sintered ceramic pellets are included. Advanced plans and progress are described for upcoming tests with unirradiated, depleted uranium oxide and actual spent fuel test rodlets. This spent fuel sabotage--aerosol test program is coordinated with the international Working Group for Sabotage Concerns of

  9. Spent fuel sabotage aerosol ratio program : FY 2004 test and data summary.

    Energy Technology Data Exchange (ETDEWEB)

    Brucher, Wenzel (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Koch, Wolfgang (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Pretzsch, Gunter Guido (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Loiseau, Olivier (Institut de Radioprotection et de Surete Nucleaire, France); Mo, Tin (U.S. Nuclear Regulatory Commission, Washington, DC); Billone, Michael C. (Argonne National Laboratory, Argonne, IL); Autrusson, Bruno A. (Institut de Radioprotection et de Surete Nucleaire, France); Young, F. I. (U.S. Nuclear Regulatory Commission, Washington, DC); Coats, Richard Lee; Burtseva, Tatiana (Argonne National Laboratory, Argonne, IL); Luna, Robert Earl; Dickey, Roy R.; Sorenson, Ken Bryce; Nolte, Oliver (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Thompson, Nancy Slater (U.S. Department of Energy, Washington, DC); Hibbs, Russell S. (U.S. Department of Energy, Washington, DC); Gregson, Michael Warren; Lange, Florentin (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Molecke, Martin Alan; Tsai, Han-Chung (Argonne National Laboratory, Argonne, IL)

    2005-07-01

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program has been underway for several years. This program provides data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assessments. The program also provides significant technical and political benefits in international cooperation. We are quantifying the Spent Fuel Ratio (SFR), the ratio of the aerosol particles released from HEDD-impacted actual spent fuel to the aerosol particles produced from surrogate materials, measured under closely matched test conditions, in a contained test chamber. In addition, we are measuring the amounts, nuclide content, size distribution of the released aerosol materials, and enhanced sorption of volatile fission product nuclides onto specific aerosol particle size fractions. These data are the input for follow-on modeling studies to quantify respirable hazards, associated radiological risk assessments, vulnerability assessments, and potential cask physical protection design modifications. This document includes an updated description of the test program and test components for all work and plans made, or revised, during FY 2004. It also serves as a program status report as of the end of FY 2004. All available test results, observations, and aerosol analyses plus interpretations--primarily for surrogate material Phase 2 tests, series 2/5A through 2/9B, using cerium oxide sintered ceramic pellets are included. Advanced plans and progress are described for upcoming tests with unirradiated, depleted uranium oxide and actual spent fuel test rodlets. This spent fuel sabotage--aerosol test program is coordinated with the international Working Group for Sabotage Concerns of

  10. Waste Isolation Pilot Plant transuranic wastes experimental characterization program: executive summary

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1978-11-01

    A general overview of the Waste Isolation Pilot Plant transuranic wastes experimental characterization program is presented. Objectives and outstanding concerns of this program are discussed. Characteristics of transuranic wastes are also described. Concerns for the terminal isolation of such wastes in a deep bedded salt facility are divided into two phases, those during the short-term operational phase of the facility, and those potentially occurring in the long-term, after decommissioning of the repository. An inclusive summary covering individual studies, their importance to the Waste Isolation Pilot Plant, investigators, general milestones, and comments are presented

  11. Summary of fire protection programs of the United States Department of Energy

    International Nuclear Information System (INIS)

    1991-10-01

    This edition of the Annual Summary of DOE Fire Protection Programs continues the series started in 1972. Since May 1950, an annual report has been required from each field organization. The content has varied through the years and most of the accident data reporting requirements have been superseded by the Computerized Accident/Incident Reporting System administered by EG ampersand G, Idaho. However, this report is the sole source of information relating to fire protection programs, and to the actions of the field offices and to headquarters that are of general fire protection interest

  12. Summary of Program Evaluation Results: 1985-1986 School Year Pre-Kindergarten Educational Program.

    Science.gov (United States)

    Heath, Robert W.; And Others

    Reported are findings of the 1985-86 program evaluation of the prenatal-to-preschool and preschool programs operating under the auspices of the Kamehameha Schools/Bishop Estate. Evaluation of the prenatal-to-preschool program (the Kupulani Program) included item analysis of the Questions about Pregnancy Test, development of a revised data…

  13. Final summary report of the Nordic Nuclear Safety Research Program 1994 - 1997; Sammanfattning av det nordiska forskningsprogrammet foer kaernsaekerhet

    Energy Technology Data Exchange (ETDEWEB)

    Bennerstedt, T.; Lemmens, A. [eds.

    1999-11-01

    This is a summary report of the NKS research program carried out 1994 - 1997. It is basically a compilation of the executive summaries of the final reports on the nine scientific projects carried out during that period. It highlights the conclusions, recommendations and other results of the projects. (au)

  14. Description of the blowdown test facility COG program on in-reactor fission product release, transport, and deposition under severe accident conditions

    International Nuclear Information System (INIS)

    Fehrenbach, P.J.; Wood, J.C.

    1987-06-01

    Loss-of-coolant accidents with additional impairment of emergency cooling would probably result in high fuel temperatures leading to severe fuel damage (SFD) and significant fission product activity would then be transported along the PHTS to the break where a fraction of it would be released and transport under such conditions, there are many interacting and sometimes competing phenomena to consider. Laboratory simulations are being used to provide data on these individual phenomena, such as UO 2 oxidation and Zr-UO 2 interaction, from which mathematical models can be constructed. These are then combined into computer codes to include the interaction effects and assess the overall releases. In addition, in-reactor tests are the only source of data on release and transport of short-lived fission product nuclides, which are important in the consequence analysis of CANDU reactor accidents. Post-test decontamination of an in-reactor test facility also provides a unique opportunity to demonstrate techniques and obtain decontamination data relevant to post-accident rehabilitation of CANDU power reactors. Specialized facilities are required for in-reactor testing because of the extensive release of radioactive fission products and the high temperatures involved (up to 2500 degrees Celsius). To meet this need for the Canadian program, the Blowdown Test Facility (BTF) has been built in the NRU reactor at Chalk River. Between completion of construction in mid-1987 and the first Zircaloy-sheathed fuel test in fiscal year 1987/88, several commissioning tests are being performed. Similarly, extensive development work has been completed to permit application of instrumentation to irradiated fuel elements, and in support of post-test fuel assembly examination. A program of decontamination studies has also been developed to generate information relevant to post-accident decontamination of power reactors. The BTF shared cost test program funded by the COG High Temperature

  15. Ideological Fission

    DEFF Research Database (Denmark)

    Christiansen, Steen Ledet

    ; it is a materialisation of an ideological fission which attempts to excise certain ideological constructions, yet paradoxically casting them in a form that is recognizable and familiar. The monstrous metonomy which is used shows us glimpses of a horrid being, intended to vilify the attack on New York City. However......, it is a being which is reminiscent of earlier monsters - from Godzilla to The Blob. It is evident that the Cloverfield monster is a paradoxical construction which attempts to articulate fear and loathing about terrorism, but ends up trapped in an ideological dead-end maze, unable to do anything other than...

  16. U.S. Department of Energy Photovoltaic Energy Program Contract Summary: Fiscal Year 2000

    Energy Technology Data Exchange (ETDEWEB)

    Surek, T.

    2001-02-21

    This report summarizes the in-house and subcontracted research and development (R and D) activities under the National Center for Photovoltaics (NCPV) and U.S. Department of Energy (DOE) National Photovoltaics Program from October 1, 1999, through September 30, 2000 (FY 2000). The mission of the DOE National Photovoltaics Program is to make PV a significant part of the domestic economy-as an industry and an energy resource. The two primary goals of the national program are to (1) maintain the U.S. industry's world leadership in research and technology development and (2) help the U.S. industry remain a major, profitable force in the world market. The NCPV is part of the National PV Program and provides leadership and support to the national program toward achieving its mission and goals. This Contract Summary for fiscal year (FY) 2000 documents some 179 research projects supported by the PV Program, performed by 107 organizations in 32 states, including 69 projects performed by universities and 60 projects performed by our industry partners. Of the total FY 2000 PV Program budget of $65.9 million, the industry and university research efforts received $36.9 million, or nearly 56%. And, of this amount, more than 93% was for contractors selected on a competitive basis. Much of the funding to industry was matched by industry cost-sharing. Each individual effort described in this summary represents another step toward improving PV manufacturing, performance, cost, and applications, and another step toward accomplishing the DOE PV Program's overall mission.

  17. FRESCO-II: A computer program for analysis of fission product release from spherical HTGR-fuel elements in irradiation and annealing experiments

    International Nuclear Information System (INIS)

    Krohn, H.; Finken, R.

    1983-06-01

    The modular computer code FRESCO has been developed to describe the mechanism of fission product release from a HTGR-Core under accident conditions. By changing some program modules it has been extended to take into account the transport phenomena (i.e. recoil) too, which only occur under reactor operating conditions and during the irradiation experiments. For this report, the release of cesium and strontium from three HTGR-fuel elements has been evaluated and compared with the experimental data. The results show that the measured release can be described by the considered models. (orig.) [de

  18. Summary of the planning, management, and evaluation process for the Geothermal Program Review VI conference

    Energy Technology Data Exchange (ETDEWEB)

    1988-10-01

    The purpose of this document is to present an overview of the planning, facilitation, and evaluation process used to conduct the Geothermal Program Review VI (PR VI) conference. This document was also prepared to highlight lessons learned from PR VI and, by utilizing the evaluation summaries and recommendations, be used as a planning tool for PR VII. The conference, entitled Beyond Goals and Objectives,'' was sponsored by the US Department of Energy's (DOE) Geothermal Technology Division (GTD), PR VI was held in San Francisco, California on April 19--21, 1988 and was attended by 127 participants. PR VI was held in conjunction with the National Geothermal Association's (NGA) Industry Round Table. This document presents a brief summary of the activities, responsibilities, and resources for implementing the PR VI meeting and provides recommendations, checklists, and a proposed schedule for assisting in planning PR VII.

  19. Mica fission detectors

    International Nuclear Information System (INIS)

    Wong, C.; Anderson, J.D.; Hansen, L.; Lehn, A.V.; Williamson, M.A.

    1977-01-01

    The present development status of the mica fission detectors is summarized. It is concluded that the techniques have been refined and developed to a state such that the mica fission counters are a reliable and reproducible detector for fission events

  20. Nuclear fission and fission-product spectroscopy: 3. International workshop on nuclear fission and fission-product spectroscopy

    International Nuclear Information System (INIS)

    Goutte, Heloise; Fioni, Gabriele; Faust, Herbert; Goutte, Dominique

    2005-01-01

    The present book contains the proceedings of the third workshop in a series of workshops previously held in Seyssins in 1994 and 1998. The meeting was jointly organized by different divisions of CEA and two major international laboratories. In the opening address, Prof. B. Bigot, the French High Commissioner for Atomic Energy, outlined France's energy policy for the next few decades. He emphasized the continuing progress of nuclear fission in both technical and economic terms, allowing it to contribute to the energy needs of the planet even more in the future than it does today. Such progress implies a very strong link between fundamental and applied research based on experimental and theoretical approaches. The workshop gathered the different nuclear communities studying the fission process, including topics as the following: - nuclear fission experiments, - spectroscopy of neutron rich nuclei, - fission data evaluation, - theoretical aspects of nuclear fission, - and innovative nuclear systems and new facilities. The scientific program was suggested by an International Advisory Committee. About 100 scientists from 13 different countries attended the conference in the friendly working atmosphere of the Castle of Cadarache in the heart of the Provence. The proceedings of the workshop were divided into 11 sections addressing the following subject matters: 1. Cross sections and resonances (5 papers); 2. Fission at higher energies - I (5 papers); 3. Fission: mass and charge yields (4 papers); 4. Light particles and cluster emission (4 papers); 5. Spectroscopy of neutron rich nuclei (5 papers); 6. Resonances, barriers, and fission times (5 papers); 7. Fragment excitation and neutron emission (4 papers); 8. Mass and energy distributions (4 papers); 9. Needs for nuclear data and new facilities - I (4 papers); 10. Angular momenta and fission at higher Energies - II (3 papers); 11. New facilities - II (2 papers). A poster session of 8 presentations completed the workshop

  1. Radioactive Waste Management Fellowship Program: Summary of program activities for calendar year 1986

    International Nuclear Information System (INIS)

    1987-01-01

    This document describes a graduate fellowship program designed to guide future scientists and engineers toward a career in high level radioactive waste management. Oak Ridge Associated Universities administers this program on behalf of 17 participating universities. The report summarizes the background and qualifications of the last year's applicants and awardees and provides examples of the distributed literature describing the program. 8 figs

  2. Neutron-induced fission cross sections

    International Nuclear Information System (INIS)

    Weigmann, H.

    1991-01-01

    In the history of fission research, neutron-induced fission has always played the most important role. The practical importance of neutron-induced fission rests upon the fact that additional neutrons are produced in the fission process, and thus a chain reaction becomes possible. The practical applications of neutron-induced fission will not be discussed in this chapter, but only the physical properties of one of its characteristics, namely (n,f) cross sections. The most important early summaries on the subject are the monograph edited by Michaudon which also deals with the practical applications, the earlier review article on fission by Michaudon, and the review by Bjornholm and Lynn, in which neutron-induced fission receives major attention. This chapter will attempt to go an intermediate way between the very detailed theoretical treatment in the latter review and the cited monograph which emphasizes the applied aspects and the techniques of fission cross-section measurements. The more recent investigations in the field will be included. Section II will survey the properties of cross sections for neutron-induced fission and also address some special aspects of the experimental methods applied in their measurement. Section Ill will deal with the formal theory of neutron-induced nuclear reactions for the resolved resonance region and the region of statistical nuclear reactions. In Section IV, the fission width, or fission transmission coefficient, will be discussed in detail. Section V will deal with the broader structures due to incompletely damped vibrational resonances, and in particular will address the special case of thorium and neighboring isotopes. Finally, Section VI will briefly discuss parity violation effects in neutron-induced fission. 74 refs., 14 figs., 3 tabs

  3. Theory of neutron emission in fission

    International Nuclear Information System (INIS)

    Madland, D.G.

    1989-01-01

    Following a summary of the observables in neutron emission in fission, a brief history is given of theoretical representations of the prompt fission neutron spectrum N(E) and average prompt neutron multiplicity /bar /nu///sub p/. This is followed by descriptions, together with examples, of modern approaches to the calculation of these quantities including recent advancements. Emphasis will be placed upon the predictability and accuracy of the modern approaches. In particular, the dependence of N(E) and /bar /nu///sub p/ on the fissioning nucleus and its excitation energy will be discussed, as will the effects of and competition between first-, second- and third-chance fission in circumstances of high excitation energy. Finally, properties of neutron-rich (fission-fragment) nuclei are discussed that must be better known to calculate N(E) and /bar /nu///sub p/ with higher accuracy than is currently possible. 17 refs., 11 figs

  4. Near-Term Electric Vehicle Program. Phase II: Mid-Term Summary Report.

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-08-01

    The Near Term Electric Vehicle (NTEV) Program is a constituent elements of the overall national Electric and Hybrid Vehicle Program that is being implemented by the Department of Energy in accordance with the requirements of the Electric and Hybrid Vehicle Research, Development, and Demonstration Act of 1976. Phase II of the NTEV Program is focused on the detailed design and development, of complete electric integrated test vehicles that incorporate current and near-term technology, and meet specified DOE objectives. The activities described in this Mid-Term Summary Report are being carried out by two contractor teams. The prime contractors for these contractor teams are the General Electric Company and the Garrett Corporation. This report is divided into two discrete parts. Part 1 describes the progress of the General Electric team and Part 2 describes the progress of the Garrett team.

  5. 07051 Executive Summary -- Programming Paradigms for the Web: Web Programming and Web Services

    OpenAIRE

    Hull, Richard; Thiemann, Peter; Wadler, Philip

    2007-01-01

    The world-wide web raises a variety of new programming challenges. To name a few: programming at the level of the web browser, data-centric approaches, and attempts to automatically discover and compose web services. This seminar brought together researchers from the web programming and web services communities and strove to engage them in communication with each other. The seminar was held in an unusual style, in a mixture of short presentations and in-depth discussio...

  6. Magnetic Fusion Science Fellowship program: Summary of program activities for calendar year 1986

    International Nuclear Information System (INIS)

    1986-01-01

    This report describes the 1985-1986 progress of the Magnetic Fusion Science Fellowship program (MFSF). The program was established in January of 1985 by the Office of Fusion Energy (OFE) of the US Department of Energy (DOE) to encourage talented undergraduate and first-year graduate students to enter qualified graduate programs in the sciences related to fusion energy development. The program currently has twelve fellows in participating programs. Six new fellows are being appointed during each of the program's next two award cycles. Appointments are for one year and are renewable for two additional years with a three year maximum. The stipend level also continues at a $1000 a month or $12,000 a year. The program pays all tuition and fee expenses for the fellows. Another important aspect of the fellowship program is the practicum. During the practicum fellows receive three month appointments to work at DOE designated fusion science research and development centers. The practicum allows the MFSF fellows to directly participate in on-going DOE research and development programs

  7. A technology development summary for the AGT101 advanced gas turbine program

    Science.gov (United States)

    Boyd, Gary L.; Kidwell, James R.; Kreiner, Daniel M.

    1987-01-01

    A summary is presented of significant technology developments that have been made in the AGT101 advanced gas turbine program. The AGT101 design features are reviewed, and the power section testing and results are addressed in detail. The results of component testing and evaluation are described for the compressor, turbine, regenerator, and foil bearing. Ceramic component development is discussed, including that of the static seal, turbine shroud seal, regenerator shield planar seal, regenerator shield piston ring, stator rig, ceramic combustor, and turbine rotor. Important areas to be addressed by the Advanced Turbine Technology Applications Project now in the planning stage at DOE and NASA are briefly reviewed.

  8. Final summary report of the Nordic Nuclear Safety Research Program 1998-2001

    International Nuclear Information System (INIS)

    Bennerstedt, T.

    2002-11-01

    The results of the 1998 - 2001 NKS program are presented in the form of executive summaries, highlighting the conclusions, recommendations and other findings and results of the six projects carried out during that period. The titles of the six projects are: Risk assessment and strategies for safety (NKS/SOS-1); Reactor safety (NKS/SOS-2); Radioactive waste (NKS/SOS-3); Nuclear Emergency preparedness (NKS/BOK-1); Radiological and environmental consequences (NKS/BOK-2); Nuclear threats from Nordic surroundings (NKS/SBA-1) (ln)

  9. Fission theory and actinide fission data

    Energy Technology Data Exchange (ETDEWEB)

    Michaudon, A.

    1975-06-01

    The understanding of the fission process has made great progress recently, as a result of the calculation of fission barriers, using the Strutinsky prescription. Double-humped shapes were obtained for nuclei in the actinide region. Such shapes could explain, in a coherent manner, many different phenomena: fission isomers, structure in near-threshold fission cross sections, intermediate structure in subthreshold fission cross sections and anisotropy in the emission of the fission fragments. A brief review of fission barrier calculations and relevant experimental data is presented. Calculations of fission cross sections, using double-humped barrier shapes and fission channel properties, as obtained from the data discussed previously, are given for some U and Pu isotopes. The fission channel theory of A. Bohr has greatly influenced the study of low-energy fission. However, recent investigation of the yields of prompt neutrons and γ rays emitted in the resonances of {sup 235}U and {sup 239}Pu, together with the spin determination for many resonances of these two nuclei cannot be explained purely in terms of the Bohr theory. Variation in the prompt neutron and γ-ray yields from resonance to resonance does not seem to be due to such fission channels, as was thought previously, but to the effect of the (n,γf) reaction. The number of prompt fission neutrons and the kinetic energy of the fission fragments are affected by the energy balance and damping or viscosity effects in the last stage of the fission process, from saddle point to scission. These effects are discussed for some nuclei, especially for {sup 240}Pu.

  10. Analysis of the boron pile measurement of the average neutron yield per fission of 252Cf: (AWBA development program)

    International Nuclear Information System (INIS)

    Ullo, J.J.

    1977-08-01

    The Harwell Boron Pile measurement of the average number of prompt neutrons emitted per fission, ν-bar/sub p/, of 252 Cf was analyzed in detail by a Monte Carlo method. From the calculated energy dependence of the neutron detection efficiency a value of ν-bar/sub p/ = 3.733 +- 0.022 was obtained. This value is 0.76 percent higher than the original reported value of 3.705 +- 0.015. Possible causes for this increase are discussed. 3 figures, 6 tables

  11. Near-term electric-vehicle program. Phase II. Mid-term review summary report

    Energy Technology Data Exchange (ETDEWEB)

    1978-07-27

    The general objective of the Near-Term Electric Vehicle Program is to confirm that, in fact, the complete spectrum of requirements placed on the automobile (e.g., safety, producibility, utility, etc.) can still be satisfied if electric power train concepts are incorporated in lieu of contemporary power train concepts, and that the resultant set of vehicle characteristics are mutually compatible, technologically achievable, and economically achievable. The focus of the approach to meeting this general objective involves the design, development, and fabrication of complete electric vehicles incorporating, where necessary, extensive technological advancements. A mid-term summary is presented of Phase II which is a continuation of the preliminary design study conducted in Phase I of the program. Information is included on vehicle performance and performance simulation models; battery subsystems; control equipment; power systems; vehicle design and components for suspension, steering, and braking; scale model testing; structural analysis; and vehicle dynamics analysis. (LCL)

  12. Summary of LLNL's accomplishments for the FY93 Waste Processing Operations Program

    International Nuclear Information System (INIS)

    Grasz, E.; Domning, E.; Heggins, D.; Huber, L.; Hurd, R.; Martz, H.; Roberson, P.; Wilhelmsen, K.

    1994-04-01

    Under the US Department of Energy's (DOE's) Office of Technology Development (OTD)-Robotic Technology Development Program (RTDP), the Waste Processing Operations (WPO) Program was initiated in FY92 to address the development of automated material handling and automated chemical and physical processing systems for mixed wastes. The Program's mission was to develop a strategy for the treatment of all DOE mixed, low-level, and transuranic wastes. As part of this mission, DOE's Mixed Waste Integrated Program (MWIP) was charged with the development of innovative waste treatment technologies to surmount shortcomings of existing baseline systems. Current technology advancements and applications results from cooperation of private industry, educational institutions, and several national laboratories operated for DOE. This summary document presents the LLNL Environmental Restoration and Waste Management (ER and WM) Automation and Robotics Section's contributions in support of DOE's FY93 WPO Program. This document further describes the technological developments that were integrated in the 1993 Mixed Waste Operations (MWO) Demonstration held at SRTC in November 1993

  13. Measurements of fission yields

    International Nuclear Information System (INIS)

    Denschlag, H.O.

    2000-01-01

    After some historical introductory remarks on the discovery of nuclear fission and early fission yield determinations, the present status of knowledge on fission yields is briefly reviewed. Practical and fundamental reasons motivating the pursuit of fission yield measurements in the coming century are pointed out. Recent results and novel techniques are described that promise to provide new interesting insights into the fission process during the next century. (author)

  14. Radiochemical studies on fission

    Energy Technology Data Exchange (ETDEWEB)

    None

    1973-07-01

    Research progress is reported on nuclear chemistry; topics considered include: recoil range and kinetic energy distribution in the thermal neutron ftssion of /sup 245/Cm; mass distribution and recoil range measurements in the reactor neutron-induced fission of /sup 232/U; fission yields in the thermal neutron fission of /sup 241/PU highly asymmetric binary fission of uranium induced by reactor neutrons; and nuclear charge distribution in low energy fission. ( DHM)

  15. High Burnup Effects Program

    International Nuclear Information System (INIS)

    Barner, J.O.; Cunningham, M.E.; Freshley, M.D.; Lanning, D.D.

    1990-04-01

    This is the final report of the High Burnup Effects Program (HBEP). It has been prepared to present a summary, with conclusions, of the HBEP. The HBEP was an international, group-sponsored research program managed by Battelle, Pacific Northwest Laboratories (BNW). The principal objective of the HBEP was to obtain well-characterized data related to fission gas release (FGR) for light water reactor (LWR) fuel irradiated to high burnup levels. The HBEP was organized into three tasks as follows: Task 1 -- high burnup effects evaluations; Task 2 -- fission gas sampling; and Task 3 -- parameter effects study. During the course of the HBEP, a program that extended over 10 years, 82 fuel rods from a variety of sources were characterized, irradiated, and then examined in detail after irradiation. The study of fission gas release at high burnup levels was the principal objective of the program and it may be concluded that no significant enhancement of fission gas release at high burnup levels was observed for the examined rods. The rim effect, an as yet unquantified contributor to athermal fission gas release, was concluded to be the one truly high-burnup effect. Though burnup enhancement of fission gas release was observed to be low, a full understanding of the rim region and rim effect has not yet emerged and this may be a potential area of further research. 25 refs., 23 figs., 4 tabs

  16. Oldman River Dam wildlife habitat mitigation program, Pincher Creek, Alberta: Final report. Summary of the implementation phase, 1987--1993

    International Nuclear Information System (INIS)

    1998-01-01

    This article summarizes the 1987--1993 implementation phase of the Oldman River Dam Wildlife Habitat Mitigation Program, intended to offset the negative impact of dam construction and operation on plant and animal species. Projects carried out during the program included creation of wetlands, tree and shrub planting, installation of snow and wildlife fences, and installation of replacement nesting sites for birds. Summaries are provided of the process that led to the final program design, the projects undertaken to complete the program, the design strategies, and the proposed habitat mitigation projects. Also included are an inventory of completed projects, an evaluation of the program's success in meeting its objectives and of the mitigation techniques used in the program, and a recommended strategy for future management of the program. Appendices include habitat suitability index models, summaries of related reports, vegetation maps, and a grazing management plan

  17. FY 1981 HTGR program summary-level program outline (revision 1/30/81)

    International Nuclear Information System (INIS)

    1981-01-01

    The objective of the DOE HTGR Program is the development of technology for the most important HTGR applications. Through this support, DOE seeks to encourage private sector initiatives which will lead to the development of commercially attractive HTGR applications that concurrently support national energy goals. Currently perceived as important to national energy goals are applications that primarily address the process heat market with a view toward reduction of national requirements for oil, natural gas and coal. A high priority during FY 1981, therefore, will be to further identify and define the details of the Technology Program so as to assure that it is both necessary and sufficient to provide the required support. In the establishment of a supportive Technology Program, key elements which will be addressed are as follows: studies will be conducted to further identify and characterize important unique HTGR applications and to evaluate their potential in the context of market opportunities, utility/user interest, and national objectives to develop new energy supply options; based upon the configurations and operating characteristics projected for selected applications, Technology Program requirements must be identified to support development, verification, and ultimately licensing of components and systems comprising the facilities of interest; and in the context of limited resources, sufficient analysis and evaluation must be accomplished so as to prioritize technology elements in accordance with appropriately developed criteria

  18. Biomass Program 2007 Program Peer Review - Biodiesel and Other Technologies Summary

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2009-10-28

    This document discloses the comments provided by a review panel at the U.S. Department of Energy Office of the Biomass Program Peer Review held on November 15-16, 2007 in Baltimore, MD and the Biodiesel and Other Technologies, held on August 14th and 15th in Golden, Colorado.

  19. Magnetic Fusion Energy Technology Fellowship Program: Summary of program activities for calendar year 1985

    International Nuclear Information System (INIS)

    1985-01-01

    This report summarizes the activities of the US Department of Energy (DOE) Magnetic Fusion Energy Technology Fellowship program (MFETF) for the 1985 calendar year. The MFETF program has continued to support the mission of the Office of Fusion Energy (OFE) and its Division of Development and Technology (DDT) by ensuring the availability of appropriately trained engineering manpower needed to implement the OFE/DDT magnetic fusion energy agenda. This program provides training and research opportunities to highly qualified students at DOE-designated academic, private sector, and government magnetic fusion energy institutions. The objectives of the Magnetic Fusion Energy Technology Fellowship program are: (1) to provide support for graduate study, training, and research in magnetic fusion energy technology; (2) to ensure an adequate supply of appropriately trained manpower to implement the nation's magnetic fusion energy agenda; (3) to raise the visibility of careers in magnetic fusion energy technology and to encourage students to pursue such careers; and (4) to make national magnetic fusion energy facilities available for manpower training

  20. IMPACTS. Industrial Technologies Program: Summary of Program Results for CY 2008

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2010-08-02

    The Impacts report summarizes benefits resulting from ITP-sponsored technologies, including energy savings, waste reduction, increased productivity, and lowered emissions. It also provides an overview of the activities of the Industrial Assessment Centers, BestPractices Program, and Combined Heat and Power efforts.

  1. Biomass Program 2007 Program Peer Review - Biochemical and Products Platform Summary

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2009-10-27

    This document discloses the comments provided by a review panel at the U.S. Department of Energy Office of the Biomass Program Peer Review held on November 15-16, 2007 in Baltimore, MD and the Biochemical and Products Platform Review held on August 7-9, 2007 in Denver, Colorado.

  2. Fission gas and iodine release measured in IFA-430 up to 15 GWd/t UO2 burnup

    International Nuclear Information System (INIS)

    Appelhans, A.D.; Turnbull, J.A.; White, R.J.

    1983-01-01

    The release of fission products from fuel pellets to the fuel-cladding gap is dependent on the fuel temperature, the power (fission rate) and the burnup (fuel structure). As part of the US Nuclear Regulatory Commission's Fuel Behavior Program, EG and G Idaho, Inc., is conducting fission product release studies in the Heavy Boiling Water Reactor in Halden, Norway. This paper presents a summary of the results up to December, 1982. The data cover fuel centerline temperatures ranging from 700 to 1500 0 C for average linear heat ratings of 16 to 35 kW/m. The measurements have been performed for the period between 4.2 and 14.8 GWd/t UO 2 of burnup of the Instrumented Fuel Assembly 430 (IFA-430). The measurement program has been directed toward quantifying the release of the short-lived radioactive noble gases and iodines

  3. FWP executive summaries, Basic Energy Sciences Materials Sciences Programs (SNL/NM)

    Energy Technology Data Exchange (ETDEWEB)

    Samara, G.A.

    1997-05-01

    The BES Materials Sciences Program has the central theme of Scientifically Tailored Materials. The major objective of this program is to combine Sandia`s expertise and capabilities in the areas of solid state sciences, advanced atomic-level diagnostics and materials synthesis and processing science to produce new classes of tailored materials as well as to enhance the properties of existing materials for US energy applications and for critical defense needs. Current core research in this program includes the physics and chemistry of ceramics synthesis and processing, the use of energetic particles for the synthesis and study of materials, tailored surfaces and interfaces for materials applications, chemical vapor deposition sciences, artificially-structured semiconductor materials science, advanced growth techniques for improved semiconductor structures, transport in unconventional solids, atomic-level science of interfacial adhesion, high-temperature superconductors, and the synthesis and processing of nano-size clusters for energy applications. In addition, the program includes the following three smaller efforts initiated in the past two years: (1) Wetting and Flow of Liquid Metals and Amorphous Ceramics at Solid Interfaces, (2) Field-Structured Anisotropic Composites, and (3) Composition-Modulated Semiconductor Structures for Photovoltaic and Optical Technologies. The latter is a joint effort with the National Renewable Energy Laboratory. Separate summaries are given of individual research areas.

  4. Department of Energy Small-Scale Hydropower Program: Feasibility assessment and technology development summary report

    International Nuclear Information System (INIS)

    Rinehart, B.N.

    1991-06-01

    This report summarizes two subprograms under the US Department of Energy's Small-Scale Hydroelectric Power Program. These subprograms were part of the financial assistance activities and included the Program Research and Development Announcement (PRDA) feasibility assessments and the technology development projects. The other major subprograms included engineering research and development, legal and institutional aspects, and technology transfer. These other subprograms are covered in their respective summary reports. The problems of energy availability and increasing costs of energy led to a national effort to develop economical and environmental attractive alternative energy resources. One such alternative involved the utilization of existing dams with hydraulic heads of <65 ft and the capacity to generate hydroelectric power of 15 MW or less. Thus, the PRDA program was initiated along with the Technology Development program. The purpose of the PRDA feasibility studies was to encourage development of renewable hydroelectric resources by providing engineering, economic, environmental, safety, and institutional information. Fifty-five feasibility studies were completed under the PRDA. This report briefly summarizes each of those projects. Many of the PRDA projects went on to become technology development projects. 56 refs., 1 fig., 2 tabs

  5. Summary of work completed under the Environmental and Dynamic Equipment Qualification research program (EDQP)

    International Nuclear Information System (INIS)

    Steele, R. Jr.; Bramwell, D.L.; Watkins, J.C.; DeWall, K.G.

    1994-02-01

    This report documents the results of the main projects undertaken under the Environmental and Dynamic Equipment Qualification Research Program (EDQP) sponsored by the U.S. Nuclear Regulatory Commission (NRC) under FIN A6322. Lasting from fiscal year 1983 to 1987, the program dealt with environmental and dynamic (including seismic) equipment qualification issues for mechanical and electromechanical components and systems used in nuclear power plants. The research results have since been used by both the NRC and industry. The program included seven major research projects that addressed the following issues: (a) containment purge and vent valves performing under design basis loss of coolant accident loads, (b) containment piping penetrations and isolation valves performing under seismic loadings and design basis and severe accident containment wall displacements, (c) shaft seals for primary coolant pumps performing under station blackout conditions, (d) electrical cabinet internals responding to in-structure generated motion (rattling), and (e) in situ piping and valves responding to seismic loadings. Another project investigating whether certain containment isolation valves will close under design basis conditions was also started under this program. This report includes eight main section, each of which provides a brief description of one of the projects, a summary of the findings, and an overview of the application of the results. A bibliography lists the journal articles, papers, and reports that document the research

  6. Energy Extension Service Pilot Program: evaluation report after two years. Volume I. Evaluation summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-04-01

    The EES pilot program was initiated in August 1977, when 10 states were selected on a competitive basis for participation. The pilot states (Alabama, Connecticut, Michigan, New Mexico, Pennsylvania, Tennessee, Texas, Washington, Wisconsin, and Wyoming) devoted the first 6 months to start-up activities. This document is a follow-up report to the three volume Evaluation Summary of the first year of the pilot EES program published in September 1979. The purpose of this report is to provide an overview of the impacts and costs of the two years of the pilot program, and to check the consistency of findings over the two year period. The analysis addresses the following: (1) were the impact findings of Year I and Year II consistent, or did Year I and Year II attitudes and behavior vary. If variation existed, could it be attributed to program changes as the EES progressed from a start-up phase (Year I) to more normal service delivery (Year II); and (2) did costs of service delivery change (again reflecting start-up and normal service delivery costs). Did cost changes affect conclusions about the relative cost effectiveness of delivering services to different target audiences.

  7. Department of Energy Small-Scale Hydropower Program: Feasibility assessment and technology development summary report

    Energy Technology Data Exchange (ETDEWEB)

    Rinehart, B.N.

    1991-06-01

    This report summarizes two subprograms under the US Department of Energy's Small-Scale Hydroelectric Power Program. These subprograms were part of the financial assistance activities and included the Program Research and Development Announcement (PRDA) feasibility assessments and the technology development projects. The other major subprograms included engineering research and development, legal and institutional aspects, and technology transfer. These other subprograms are covered in their respective summary reports. The problems of energy availability and increasing costs of energy led to a national effort to develop economical and environmental attractive alternative energy resources. One such alternative involved the utilization of existing dams with hydraulic heads of <65 ft and the capacity to generate hydroelectric power of 15 MW or less. Thus, the PRDA program was initiated along with the Technology Development program. The purpose of the PRDA feasibility studies was to encourage development of renewable hydroelectric resources by providing engineering, economic, environmental, safety, and institutional information. Fifty-five feasibility studies were completed under the PRDA. This report briefly summarizes each of those projects. Many of the PRDA projects went on to become technology development projects. 56 refs., 1 fig., 2 tabs.

  8. Fusion power research and development program. Volume IV. 5-year program, budget and milestone summaries

    International Nuclear Information System (INIS)

    1976-07-01

    Budget data are given for each of the tokamak systems, mirror systems, and high density plasma systems for the years 1976 through 1982. All major facilities currently under ERDA contract are included. In addition, budget data are given for the development and technology program consisting of the following; (1) magnetic systems, (2) plasma engineering, (3) fusion reactor materials, (4) fusion systems engineering, (5) environment and safety, and (6) applied plasma physics

  9. Fission products collecting devices

    International Nuclear Information System (INIS)

    Matsumoto, Hiroshi

    1979-01-01

    Purpose: To enable fission products trap with no contamination to coolants and cover gas by the provision of a fission products trap above the upper part of a nuclear power plant. Constitution: Upon fuel failures in a reactor core, nuclear fission products leak into coolants and move along the flow of the coolants to the coolants above the reactor core. The fission products are collected in a trap container and guided along a pipeline into fission products detector. The fission products detector monitors the concentration of the fission products and opens the downstream valve of the detector when a predetermined concentration of the fission products is detected to introduce the fission products into a waste gas processing device and release them through the exhaust pipe. (Seki, T.)

  10. Energy released in fission

    International Nuclear Information System (INIS)

    James, M.F.

    1969-05-01

    The effective energy released in and following the fission of U-235, Pu-239 and Pu-241 by thermal neutrons, and of U-238 by fission spectrum neutrons, is discussed. The recommended values are: U-235 ... 192.9 ± 0.5 MeV/fission; U-238 ... 193.9 ± 0.8 MeV/fission; Pu-239 ... 198.5 ± 0.8 MeV/fission; Pu-241 ... 200.3 ± 0.8 MeV/fission. These values include all contributions except from antineutrinos and very long-lived fission products. The detailed contributions are discussed, and inconsistencies in the experimental data are pointed out. In Appendix A, the contribution to the total useful energy release in a reactor from reactions other than fission are discussed briefly, and in Appendix B there is a discussion of the variations in effective energy from fission with incident neutron energy. (author)

  11. Electromagnetic pulse research on electric power systems: Program summary and recommendations. Power Systems Technology Program

    Energy Technology Data Exchange (ETDEWEB)

    Barnes, P.R.; McConnell, B.W.; Van Dyke, J.W. [Oak Ridge National Lab., TN (United States); Tesche, F.M. [Tesche (F.M.), Dallas, TX (United States); Vance, E.F. [Vance (E.F.), Fort Worth, TX (United States)

    1993-01-01

    A single nuclear detonation several hundred kilometers above the central United States will subject much of the nation to a high-altitude electromagnetic pulse (BENT). This pulse consists of an intense steep-front, short-duration transient electromagnetic field, followed by a geomagnetic disturbance with tens of seconds duration. This latter environment is referred to as the magnetohydrodynamic electromagnetic pulse (NMENT). Both the early-time transient and the geomagnetic disturbance could impact the operation of the nation`s power systems. Since 1983, the US Department of Energy has been actively pursuing a research program to assess the potential impacts of one or more BENT events on the nation`s electric energy supply. This report summarizes the results of that program and provides recommendations for enhancing power system reliability under HENT conditions. A nominal HENP environment suitable for assessing geographically large systems was developed during the program and is briefly described in this report. This environment was used to provide a realistic indication of BEMP impacts on electric power systems. It was found that a single high-altitude burst, which could significantly disturb the geomagnetic field, may cause the interconnected power network to break up into utility islands with massive power failures in some areas. However, permanent damage would be isolated, and restoration should be possible within a few hours. Multiple bursts would likely increase the blackout areas, component failures, and restoration time. However, a long-term blackout of many months is unlikely because major power system components, such as transformers, are not likely to be damaged by the nominal HEND environment. Moreover, power system reliability, under both HENT and normal operating conditions, can be enhanced by simple, and often low cost, modifications to current utility practices.

  12. Summary report on the Solar Consumer Assurance Network (SOLCAN) Program Planning Task in the southern region

    Energy Technology Data Exchange (ETDEWEB)

    Browne, M. B. [comp.

    1981-03-15

    The goal of the SOLCAN Program Planning Task is to assist in the development, at the state and local levels, of consumer assurance approaches that will support the accelerated adoption and effective use of new products promoted by government incentives to consumers to meet our nation's energy needs. The task includes state-conducted evaluations and state SOLCAN meetings to identify consumer assurance mechanisms, assess their effectiveness, and identify and describe alternative means for strengthening consumer and industry assurance in each state. Results of the SOLCAN process are presented, including: a Solar Consumer Protection State Assessment Guide; State Solar Consumer Assurance Resources for Selected States; State Solar Consumer Protection Assessment Interviews for Florida; and state SOLCAN meeting summaries and participants. (LEW)

  13. DOE-HUD Initiative on Energy Efficiency in Housing: A federal partnership. Program summary report

    Energy Technology Data Exchange (ETDEWEB)

    Brinch, J. [Energetics, Inc., Columbia, MD (United States)

    1996-06-01

    One of the primary goals of the US Department of Housing and urban Development (HUD) is the expansion of home ownership and affordable housing opportunities. Recognizing that energy efficiency is a key component in an affordable housing strategy, HUD and the US Department of Energy (DOE) created the DOE-HUD Initiative on Energy Efficiency in Housing. The DOE-HUD Initiative was designed to share the results of DOE research with housing providers throughout the nation, to reduce energy costs in federally-subsidized dwelling units and improve their affordability and comfort. This Program Summary Report provides an overview of the DOE-HUD Initiative and detailed project descriptions of the twenty-seven projects carried out with Initiative funding.

  14. Summary of the control-drive-mechanism design and performance for LWBR (LWBR Development Program)

    International Nuclear Information System (INIS)

    Yarnall, F.

    1983-01-01

    Control Drive Mechanisms (CDM) are used in the Light Water Breeder reactor to position Movable Fuel Assemblies weighing in excess of one ton each for purposes of reactivity control. These mechanisms are the first of a kind designed for loads of that magnitude. This report presents a summary of the design and performance of the CDM and includes discussions of the principles of operation, unique design features, and fabrication methods of this large, high load capacity CDM. The extensive design acceptance test program and the Shippingport plant periodic testing are summrized as are lessons learned during assembly of the CDM's to the reactor. These CDM's operated successfully to control the light water breeder core at the Shippingport Station from initial criticality in August 1977 to the final shutdown in October 1982. All test and operative data were within expected bands

  15. HAC and fission reactors

    International Nuclear Information System (INIS)

    Fujiwara, I.; Moriyama, H.; Tachikawa, E.

    1984-01-01

    In the fission process, newly formed fission products undergo hot atom reactions due to their energetic recoil and abnormal positive charge. The hot atom reactions of the fission products are usually accompanied by secondary effects such as radiation damage, especially in condensed phase. For reactor safety it is valuable to know the chemical behaviour and the release behaviour of these radioactive fission products. Here, the authors study the chemical behaviour and the release behaviour of the fission products from the viewpoint of hot atom chemistry (HAC). They analyze the experimental results concerning fission product behaviour with the help of the theories in HAC and other neighboring fields such as radiation chemistry. (Auth.)

  16. Office of Technology Development Program for Research, Development, Demonstration, Testing, and Evaluation. FY 1993 Program Summary

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    DOE has set a goal to clean up its complex and to bring all sites into compliance with applicable environmental regulations. This initiative is slated for completion by the year 2019. Four years ago there was no coordinated plan for identifying or cleaning these contaminated sites. Since 1989, DOE`s Office of Environmental Restoration and Waste Management has invested time, money, and manpower to establish a wide range of programs to meet this immense challenge. DOE is responsible for waste management and clean up of more than 100 contaminated installations in 36 states and territories. This includes 3,700 sites: over 26,000 acres, with hazardous or radioactive contaminated surface or groundwater, soil, or structures; over 26,000 acres requiring remediation, with the number growing as new sites are defined; 500 surplus facilities awaiting decontamination and decommissioning and approximately 5,000 peripheral properties (residences, businesses) that have soil contaminated with uranium tailings.

  17. Fiscal year 1995 well installation program summary Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1995-09-01

    This report summarizes the well installation activities conducted during the federal fiscal year (FY) 1995 drilling program at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee (including activities that were performed in late FY 1994, but not included in the FY 1994 Well Installation Program Summary Report). Synopses of monitoring well construction/well development data, well location rationale, geological/hydrological observations, quality assurance/quality control methods, and health and safety monitoring are included. Three groundwater monitoring wells and two gas monitoring probes were installed during the FY 1995 drilling program. One of the groundwater monitoring wells was installed at Landfill VI, the other two in the Boneyard/Burnyard area. All of the groundwater monitoring wells were constructed with stainless steel screens and casings. The two gas monitoring probes were installed at the Centralized Sanitary Landfill II and were of polyvinyl chloride (PVC) screened construction. Eleven well rehabilitation/redevelopment efforts were undertaken during FY 1995 at the Y-12 Plant. All new monitoring wells and wells targeted for redevelopment were developed by either a 2.0-in. diameter swab rig or by hand bailing until nonspecific parameters (pH and specific conductance) attained steady-state levels. Turbidity levels were lowered, if required, to the extent practicable by continued development beyond a steady-state level of pH and conductance

  18. MOD-5A wind turbine generator program design report: Volume 1: Executive Summary

    Science.gov (United States)

    1984-01-01

    The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator covering work performed between July 1980 and June 1984 is discussed. The report is divided into four volumes: Volume 1 summarizes the entire MOD-5A program, Volume 2 discusses the conceptual and preliminary design phases, Volume 3 describes the final design of the MOD-5A, and Volume 4 contains the drawings and specifications developed for the final design. Volume 1, the Executive Summary, summarizes all phases of the MOD-5A program. The performance and cost of energy generated by the MOD-5A are presented. Each subsystem - the rotor, drivetrain, nacelle, tower and foundation, power generation, and control and instrumentation subsystems - is described briefly. The early phases of the MOD-5A program, during which the design was analyzed and optimized, and new technologies and materials were developed, are discussed. Manufacturing, quality assurance, and safety plans are presented. The volume concludes with an index of volumes 2 and 3.

  19. Energy from nuclear fission an introduction

    CERN Document Server

    De Sanctis, Enzo; Ripani, Marco

    2016-01-01

    This book provides an overview on nuclear physics and energy production from nuclear fission. It serves as a readable and reliable source of information for anyone who wants to have a well-balanced opinion about exploitation of nuclear fission in power plants. The text is divided into two parts; the first covers the basics of nuclear forces and properties of nuclei, nuclear collisions, nuclear stability, radioactivity, and provides a detailed discussion of nuclear fission and relevant topics in its application to energy production. The second part covers the basic technical aspects of nuclear fission reactors, nuclear fuel cycle and resources, safety, safeguards, and radioactive waste management. The book also contains a discussion of the biological effects of nuclear radiation and of radiation protection, and a summary of the ten most relevant nuclear accidents. The book is suitable for undergraduates in physics, nuclear engineering and other science subjects. However, the mathematics is kept at a level that...

  20. The wastes of nuclear fission

    International Nuclear Information System (INIS)

    Doubre, H.

    2005-01-01

    In this paper the author presents the problems of the radioactive wastes generated by the nuclear fission. The first part devoted to the fission phenomenon explains the incident neutron energy and the target nuclei role. The second part devoted to the nuclear wastes sources presents the production of wastes upstream of the reactors, in the reactors and why these wastes are dangerous. The third part discusses the radioactive wastes management in France (classification, laws). The last part details the associated research programs: the radionuclides separation, the disposal, the underground storage, the transmutation and the thorium cycle. (A.L.B.)

  1. NASA's Upper Atmosphere Research Program (UARP) and Atmospheric Chemistry Modeling and Analysis Program (ACMAP): Research Summaries 1997-1999

    Science.gov (United States)

    Kurylo, M. J.; DeCola, P. L.; Kaye, J. A.

    2000-01-01

    Under the mandate contained in the FY 1976 NASA Authorization Act, the National Aeronautics and Space Administration (NASA) has developed and is implementing a comprehensive program of research, technology development, and monitoring of the Earth's upper atmosphere, with emphasis on the upper troposphere and stratosphere. This program aims at expanding our chemical and physical understanding to permit both the quantitative analysis of current perturbations as well as the assessment of possible future changes in this important region of our environment. It is carried out jointly by the Upper Atmosphere Research Program (UARP) and the Atmospheric Chemistry Modeling and Analysis Program (ACMAP), both managed within the Research Division in the Office of Earth Science at NASA. Significant contributions to this effort have also been provided by the Atmospheric Effects of Aviation Project (AEAP) of NASA's Office of Aero-Space Technology. The long-term objectives of the present program are to perform research to: understand the physics, chemistry, and transport processes of the upper troposphere and the stratosphere and their control on the distribution of atmospheric chemical species such as ozone; assess possible perturbations to the composition of the atmosphere caused by human activities and natural phenomena (with a specific emphasis on trace gas geographical distributions, sources, and sinks and the role of trace gases in defining the chemical composition of the upper atmosphere); understand the processes affecting the distributions of radiatively active species in the atmosphere, and the importance of chemical-radiative-dynamical feedbacks on the meteorology and climatology of the stratosphere and troposphere; and understand ozone production, loss, and recovery in an atmosphere with increasing abundances of greenhouse gases. The current report is composed of two parts. Part 1 summarizes the objectives, status, and accomplishments of the research tasks supported

  2. Status of fission yield data

    International Nuclear Information System (INIS)

    England, T.R.; Blachot, J.

    1988-01-01

    In this paper we summarize the current status of the recent US evaluation for 34 fissioning nuclides at one or more neutron incident energies and for spontaneous fission. Currently there are 50 yields sets, and for each we have independent and cumulative yields and uncertainties for approximately 1100 fission products. When finalized the recommended data will become part of Version VI of the US ENDF/B. Other major evaluations in progress that are included in a recently formed IAEA Coordinated Research Program are also summarized. In a second part we review two empirical models in use to estimate independent yields. Comparison of model estimates with measured data is presented, including a comparison with some recent data obtained from Lohengrin (Cf-249 T). 18 refs., 13 figs., 3 tabs

  3. Safety Test Program Summary SNAP 19 Pioneer Heat Source Safety Program

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1971-07-01

    Sixteen heat source assemblies have been tested in support of the SNAP 19 Pioneer Safety Test Program. Seven were subjected to simulated reentry heating in various plasma arc facilities followed by impact on earth or granite. Six assemblies were tested under abort accident conditions of overpressure, shrapnel impact, and solid and liquid propellant fires. Three capsules were hot impacted under Transit capsule impact conditions to verify comparability of test results between the two similar capsule designs, thus utilizing both Pioneer and Transit Safety Test results to support the Safety Analysis Report for Pioneer. The tests have shown the fuel is contained under all nominal accident environments with the exception of minor capsule cracks under severe impact and solid fire environments. No catastrophic capsule failures occurred in this test which would release large quantities of fuel. In no test was fuel visible to the eye following impact or fire. Breached capsules were defined as those which exhibit thoria contamination on its surface following a test, or one which exhibited visible cracks in the post test metallographic analyses.

  4. CINDER, Depletion and Decay Chain Calculation for Fission Products in Thermal Reactors

    International Nuclear Information System (INIS)

    England, T.R.; Gorrell, T.C.; Hightower, J.H.

    2001-01-01

    1 - Description of problem or function: CINDER is a four-group, one- point depletion and fission product program based on the evaluation of a general analytical solution of nuclides coupled in any linear sequence of radioactive decays and neutron absorptions in a specified neutron flux spectrum. The desired depletion and fission product chains and all physical data are specified by the problem originator. The program computes individual nuclide number densities, activities, nine energy-group disintegration rates, and macroscopic and barns/fission poisons at each time-step as well as selected summaries of these data. 2 - Method of solution: Time-dependent variations in nuclide cross sections and neutron fluxes are approximated by a user-specified sequential set of values which are considered constant during the duration of the user-specified associated time-increments. When a nuclide concentration is independent of the concentration of any of its progeny, it is possible to resolve the couplings so as to obtain nuclides fed by a single parent. These chains are referred to as linear. 3 - Restrictions on the complexity of the problem: The program is limited to 500 total nuclides formed in up to 240 chains of 20 or fewer nuclides each. Up to 10 nuclides may act as fission product sources, contributing to power, and as many as 99 time-steps of arbitrary length are permitted. All stable nuclides must have a cross section if zero power time-increments are anticipated

  5. Using modern imaging techniques to old HST data: a summary of the ALICE program.

    Science.gov (United States)

    Choquet, Elodie; Soummer, Remi; Perrin, Marshall; Pueyo, Laurent; Hagan, James Brendan; Zimmerman, Neil; Debes, John Henry; Schneider, Glenn; Ren, Bin; Milli, Julien; Wolff, Schuyler; Stark, Chris; Mawet, Dimitri; Golimowski, David A.; Hines, Dean C.; Roberge, Aki; Serabyn, Eugene

    2018-01-01

    Direct imaging of extrasolar systems is a powerful technique to study the physical properties of exoplanetary systems and understand their formation and evolution mechanisms. The detection and characterization of these objects are challenged by their high contrast with their host star. Several observing strategies and post-processing algorithms have been developed for ground-based high-contrast imaging instruments, enabling the discovery of directly-imaged and spectrally-characterized exoplanets. The Hubble Space Telescope (HST), pioneer in directly imaging extrasolar systems, has yet been often limited to the detection of bright debris disks systems, with sensitivity limited by the difficulty to implement an optimal PSF subtraction stategy, which is readily offered on ground-based telescopes in pupil tracking mode.The Archival Legacy Investigations of Circumstellar Environments (ALICE) program is a consistent re-analysis of the 10 year old coronagraphic archive of HST's NICMOS infrared imager. Using post-processing methods developed for ground-based observations, we used the whole archive to calibrate PSF temporal variations and improve NICMOS's detection limits. We have now delivered ALICE-reprocessed science products for the whole NICMOS archival data back to the community. These science products, as well as the ALICE pipeline, were used to prototype the JWST coronagraphic data and reduction pipeline. The ALICE program has enabled the detection of 10 faint debris disk systems never imaged before in the near-infrared and several substellar companion candidates, which we are all in the process of characterizing through follow-up observations with both ground-based facilities and HST-STIS coronagraphy. In this publication, we provide a summary of the results of the ALICE program, advertise its science products and discuss the prospects of the program.

  6. Summary report on fuel development and miniplate fabrication for the RERTR Program, 1978 to 1990

    International Nuclear Information System (INIS)

    Wiencek, T.C.

    1995-08-01

    This report summarizes the efforts of the Fabrication Technology Section at Argonne National Laboratory in the program of Reduced Enrichment Research and Test Reactors (RERTR). The main objective of this program was to reduce the amount of high enriched (∼93% 235 U) uranium (HEU) used in nonpower reactors. Conversion from low-density (0.8--1.6 g U/cm 3 ) HEU fuel elements to highly loaded (up to 7 g U/cm 3 ) low-enrichment ( 235 U) uranium (LEU) fuel elements allows the same reactor power levels, core designs and sizes to be retained while greatly reducing the possibility of illicit diversion of HEU nuclear fuel. This document is intended as an overview of the period 1978--1990, during which the Section supported this project by fabricating mainly powder metallurgy uranium-silicide dispersion fuel plates. Most of the subjects covered in detail are fabrication-related studies of uranium silicide fuels and fuel plate properties. Some data are included for out-of-pile experiments such as corrosion and compatibility tests. Also briefly covered are most other aspects of the RERTR program such as irradiation tests, full-core demonstrations, and technology transfer. References included are for further information on most aspects of the entire program. A significant portion of the report is devoted to data that were never published in their entirety. The appendices contain a list of previous RERTR reports, ANL fabrication procedures, calculations for phases present in two-phase fuels, chemical analysis of fuels, miniplate characteristics, and a summary of bonding runs made by hot isostatic pressing

  7. Summary report on fuel development and miniplate fabrication for the RERTR Program, 1978 to 1990

    Energy Technology Data Exchange (ETDEWEB)

    Wiencek, T.C. [Argonne National Lab., IL (United States). Energy Technology Div.

    1995-08-01

    This report summarizes the efforts of the Fabrication Technology Section at Argonne National Laboratory in the program of Reduced Enrichment Research and Test Reactors (RERTR). The main objective of this program was to reduce the amount of high enriched ({approx}93% {sup 235}U) uranium (HEU) used in nonpower reactors. Conversion from low-density (0.8--1.6 g U/cm{sup 3}) HEU fuel elements to highly loaded (up to 7 g U/cm{sup 3}) low-enrichment (<20% {sup 235}U) uranium (LEU) fuel elements allows the same reactor power levels, core designs and sizes to be retained while greatly reducing the possibility of illicit diversion of HEU nuclear fuel. This document is intended as an overview of the period 1978--1990, during which the Section supported this project by fabricating mainly powder metallurgy uranium-silicide dispersion fuel plates. Most of the subjects covered in detail are fabrication-related studies of uranium silicide fuels and fuel plate properties. Some data are included for out-of-pile experiments such as corrosion and compatibility tests. Also briefly covered are most other aspects of the RERTR program such as irradiation tests, full-core demonstrations, and technology transfer. References included are for further information on most aspects of the entire program. A significant portion of the report is devoted to data that were never published in their entirety. The appendices contain a list of previous RERTR reports, ANL fabrication procedures, calculations for phases present in two-phase fuels, chemical analysis of fuels, miniplate characteristics, and a summary of bonding runs made by hot isostatic pressing.

  8. Fissionable material

    International Nuclear Information System (INIS)

    Schuuring, C.; Tuininga, E.-J.; Turkenburg, W.

    1983-01-01

    This book is a presentation of controversies surrounding nuclear energy discussions in the Netherlands and aims to show that there are serious arguments against nuclear energy. Chapters on the following topics are included: the various dimensions of the energy discussion, the background to the existence of controversies in the nuclear energy discussion, the relation between nuclear energy and prosperity, different opinions concerning the cost of producing electricity from nuclear energy, radioactive waste, the consequences of a large scale accident, the relation between the peaceful use of nuclear energy and the proliferation of nuclear weapons, the effects of low radiation doses, the relation between nuclear energy and developments in the Third World, the effect of nuclear energy on democracy. The authors of these chapters, themselves critical of nuclear energy, have described the particular controversy and have given the viewpoints of both advocates and adversaries, followed by their own opinion. The conclusions from each chapter are recapitulated in a summary and the various components of the nuclear energy cycle are presented in an appendix. (C.F.)

  9. Fission Research at IRMM

    Directory of Open Access Journals (Sweden)

    Al-Adili A.

    2010-03-01

    Full Text Available Fission Research at JRC-IRMM has a longstanding tradition. The present paper is discussing recent investigations of fission fragment properties of 238 U(n,f, 234 U(n,f, prompt neutron emission in fission of 252 Cf(SF as well as the prompt fission neutron spectrum of 235 U(n,f and is presenting the most important results.

  10. Equilibrium fission model calculations

    International Nuclear Information System (INIS)

    Beckerman, M.; Blann, M.

    1976-01-01

    In order to aid in understanding the systematics of heavy ion fission and fission-like reactions in terms of the target-projectile system, bombarding energy and angular momentum, fission widths are calculated using an angular momentum dependent extension of the Bohr-Wheeler theory and particle emission widths using angular momentum coupling

  11. Magnetic Fusion Energy Program. Volume I. Introduction, technical summaries, list of publications, etc., Appendices A-K. Annual report

    International Nuclear Information System (INIS)

    Aamodt, R.E.; Byrne, R.N.; Catto, P.J.

    1979-12-01

    An abstract was prepared for the progress summary on transport theory for open and closed magnetic configurations. Seven abstracts were prepared for included appendices of more detailed work on individual devices. Also included is a list of publications, technical presentations, and DOE program contributions

  12. Systematics of Fission-Product Yields

    International Nuclear Information System (INIS)

    Wahl, A.C.

    2002-01-01

    Empirical equations representing systematics of fission-product yields have been derived from experimental data. The systematics give some insight into nuclear-structure effects on yields, and the equations allow estimation of yields from fission of any nuclide with atomic number Z F = 90 thru 98, mass number A F = 230 thru 252, and precursor excitation energy (projectile kinetic plus binding energies) PE = 0 thru ∼200 MeV--the ranges of these quantities for the fissioning nuclei investigated. Calculations can be made with the computer program CYFP. Estimates of uncertainties in the yield estimates are given by equations, also in CYFP, and range from ∼ 15% for the highest yield values to several orders of magnitude for very small yield values. A summation method is used to calculate weighted average parameter values for fast-neutron (∼ fission spectrum) induced fission reactions

  13. Systematics of Fission-Product Yields

    Energy Technology Data Exchange (ETDEWEB)

    A.C. Wahl

    2002-05-01

    Empirical equations representing systematics of fission-product yields have been derived from experimental data. The systematics give some insight into nuclear-structure effects on yields, and the equations allow estimation of yields from fission of any nuclide with atomic number Z{sub F} = 90 thru 98, mass number A{sub F} = 230 thru 252, and precursor excitation energy (projectile kinetic plus binding energies) PE = 0 thru {approx}200 MeV--the ranges of these quantities for the fissioning nuclei investigated. Calculations can be made with the computer program CYFP. Estimates of uncertainties in the yield estimates are given by equations, also in CYFP, and range from {approx} 15% for the highest yield values to several orders of magnitude for very small yield values. A summation method is used to calculate weighted average parameter values for fast-neutron ({approx} fission spectrum) induced fission reactions.

  14. Significant ELCAP analysis results: Summary report. [End-use Load and Consumer Assessment Program

    Energy Technology Data Exchange (ETDEWEB)

    Pratt, R.G.; Conner, C.C.; Drost, M.K.; Miller, N.E.; Cooke, B.A.; Halverson, M.A.; Lebaron, B.A.; Lucas, R.G.; Jo, J.; Richman, E.E.; Sandusky, W.F. (Pacific Northwest Lab., Richland, WA (USA)); Ritland, K.G. (Ritland Associates, Seattle, WA (USA)); Taylor, M.E. (USDOE Bonneville Power Administration, Portland, OR (USA)); Hauser, S.G. (Solar Energy Research Inst., Golden, CO (USA))

    1991-02-01

    The evolution of the End-Use Load and Consumer Assessment Program (ELCAP) since 1983 at Bonneville Power Administration (Bonneville) has been eventful and somewhat tortuous. The birth pangs of a data set so large and encompassing as this have been overwhelming at times. The early adolescent stage of data set development and use has now been reached and preliminary results of early analyses of the data are becoming well known. However, the full maturity of the data set and the corresponding wealth of analytic insights are not fully realized. This document is in some sense a milestone in the brief history of the program. It is a summary of the results of the first five years of the program, principally containing excerpts from a number of previous reports. It is meant to highlight significant accomplishments and analytical results, with a focus on the principal results. Many of the results have a broad application in the utility load research community in general, although the real breadth of the data set remains largely unexplored. The first section of the document introduces the data set: how the buildings were selected, how the metering equipment was installed, and how the data set has been prepared for analysis. Each of the sections that follow the introduction summarize a particular analytic result. A large majority of the analyses to date involve the residential samples, as these were installed first and had highest priority on the analytic agenda. Two exploratory analyses using commercial data are included as an introduction to the commercial analyses that are currently underway. Most of the sections reference more complete technical reports which the reader should refer to for details of the methodology and for more complete discussion of the results. Sections have been processed separately for inclusion on the data base.

  15. Summary and Analysis of the U.S. Government Bat Banding Program

    Science.gov (United States)

    Ellison, Laura E.

    2008-01-01

    This report summarizes the U.S. Government Bat Banding Program (BBP) from 1932 to 1972. More than 2 million bands were issued during the program, of which approximately 1.5 million bands were applied to 36 bat species by scientists in many locations in North America including the U.S., Canada, Mexico, and Central America. Throughout the BBP, banders noticed numerous and deleterious effects on bats, leading to a moratorium on bat banding by the U.S. Fish and Wildlife Service, and a resolution to cease banding by the American Society of Mammalogists in 1973. One of the main points of the memorandum written to justify the moratorium was to conduct a 'detailed evaluation of the files of the bat-banding program.' However, a critical and detailed evaluation of the BBP was never completed. In an effort to satisfy this need, I compiled a detailed history of the BBP by examining the files and conducting a literature review on bat banding activities during the program. I also provided a case study in managing data and applying current mark-recapture theory to estimate survival using the information from a series of bat bands issued to Clyde M. Senger during the BBP. The majority of bands applied by Senger were to Townsend's big-eared bat (Corynorhinus townsendii), a species of special concern for many states within its geographic range. I developed a database management system for the bat banding records and then analyzed and modeled survival of hibernating Townsend's big-eared bats at three main locations in Washington State using Cormack-Jolly-Seber (CJS) open models and the modeling capabilities of Program MARK. This analysis of a select dataset in the BBP files provided relatively precise estimates of survival for wintering Townsend's big-eared bats. However, this dataset is unique due to its well-maintained and complete state and because there were high recapture rates over the course of banding; it is doubtful that other unpublished datasets of the same quality exist

  16. NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  17. Theoretical descriptions of neutron emission in fission

    International Nuclear Information System (INIS)

    Madland, D.G.

    1991-01-01

    Brief descriptions are given of the observables in neutron emission in fission together with early theoretical representations of two of these observables, namely, the prompt fission neutron spectrum N(E) and the average prompt neutron multiplicity ν-bar p . This is followed by summaries, together with examples, of modern approaches to the calculation of these two quantities. Here, emphasis is placed upon the predictability and accuracy of the new approaches. In particular, the dependencies of N(E) and ν-bar p upon the fissioning nucleus and its excitation energy are discussed. Then, recent work in multiple-chance fission and other recent work involving new measurements are presented and discussed. Following this, some properties of fission fragments are mentioned that must be better known and better understood in order to calculate N(E) and ν-bar p with higher accuracy than is currently possible. In conclusion, some measurements are recommended for the purpose of benchmarking simultaneous calculations of neutron emission and gamma emission in fission. (author). 32 refs, 26 figs

  18. Summary of the Nevada Applied Ecology Group and correlative programs. Version 1

    Energy Technology Data Exchange (ETDEWEB)

    Friesen, H.N. [Raytheon Services Nevada, Las Vegas, NV (United States)

    1992-10-01

    This summary document presents results in a broad context; it is not limited to findings of the Nevada Applied Ecology Group. This book is organized to present the findings of the Nevada Applied Ecology Group and correlative programs in accordance with the originally stated objectives of the Nevada Applied Ecology Group. This plan, in essence, traces plutonium from its injection into the environment to movement in the ecosystem to development of cleanup techniques. Information on other radionuclides was also obtained and will be presented briefly. Chapter 1 presents a brief description of the ecological setting of the Test Range Complex. The results of investigations for plutonium distribution are presented in Chapter 2 for the area surrounding the Test Range Complex and in Chapter 3 for on-site locations. Chapters 4 and 5 present the results of investigations concerned with concentrations and movement, respectively, of plutonium in the ecosystem of the Test Range Complex, and Chapter 6 summarizes the potential hazard from this plutonium. Development of techniques for cleanup and treatment is presented in Chapter 7, and the inventory of radionuclides other than plutonium is presented briefly in Chapter 8.

  19. Summary of particle bed reactor designs for the Space Nuclear Thermal Propulsion Program

    Science.gov (United States)

    Powell, J. R.; Ludewig, H.; Todosow, M.

    1993-09-01

    A summary report of the Particle Bed Reactor (PBR) designs considered for the space nuclear thermal propulsion program has been prepared. The first chapters outline the methods of analysis, and their validation. Monte Carlo methods are used for the physics analysis, several new algorithms are used for the fluid dynamics heat transfer and engine system analysis, and commercially available codes are used for the stress analysis. A critical experiment, prototypic of the PBR was used for the physics validation, and blowdown experiments using fuel beds of prototypic dimensions were used to validate the power extraction capabilities from particle beds. In all four different PBR rocket reactor designs were studied to varying degrees of detail. They varied in power from 400 MW to 2000 MW. These designs were all characterized by a negative prompt coefficient, due to Doppler feedback, and the feedback due to moderator heat up varied from slightly negative to slightly positive. In all practical cases, the coolant worth was positive, although core configurations with negative coolant worth could be designed. In all practical cases the thrust/weight ratio was greater than 20.

  20. A summary of the Chalk River valve packing evaluation program 1985 - 1990

    International Nuclear Information System (INIS)

    Aikin, J.A.; Doubt, G.L.; Lade, C.R.

    1990-12-01

    The move away from asbestos-based valve packing products has generated concern among valve manufacturers, packing manufacturers and user groups about the reliability and safety of non-asbestos based products for long-term use. AECL Research, Chalk River, has been actively evaluating these new valve packing products since 1985. This report describes the work done at Chalk River from 1985 to 1990. The report includes both Electric Power Research Institute (EPRI) and CANDU Owners Group (COG) funded studies. A description of the test programs and a brief summary of the functional performance of the more successful materials (die-formed graphite, braided asbestos and braided non-asbestos) on friction, stem leakage and consolidation are provided. At this time, Chalk River and Ontario Hydro have approved the following packing arrangements: for non-live-loaded valves, the recommended replacements packing for braided asbestos is combination flexible graphite packing sets; and, for heavy water valves originally designed with JC187I, the recommended replacement packing is approved braided-asbestos products

  1. 14. International workshop on nuclear fission physics. Proceedings

    International Nuclear Information System (INIS)

    2000-01-01

    The meetings on nuclear fission took place 12-15 October 1998 and was organized by Institute of Physics and Power Engineering. The aim of the workshop was to present and discuss main new both theoretical and experimental results obtained in the area of nuclear fission, dynamical feature, properties of fission fragments and complementary radiation. As usual the program of the workshop was designed to cover a wide range of physical phenomena - from low energy and spontaneous fission to fission of hot rotating nuclei and multifragmentation at intermediate and high energies. Reaction induced by slow and fast neutron, light and heavy ions were discussed [ru

  2. The behavior of fission products during nuclear rocket reactor tests

    International Nuclear Information System (INIS)

    Bokor, P.C.; Kirk, W.L.; Bohl, R.J.

    1991-01-01

    Fission product release from nuclear rocket propulsion reactor fuel is an important consideration for nuclear rocket development and application. Fission product data from the last six reactors of the Rover program are collected in this paper to provide as basis for addressing development and testing issues. Fission product loss from the fuel will depend on fuel composition and reactor design and operating parameters. During ground testing, fission products can be contained downstream of the reactor. The last Rover reactor tested, the Nuclear Furnance, was mated to an effluent clean-up system that was effective in preventing the discharge of fission products into the atmosphere

  3. Fission level densities

    International Nuclear Information System (INIS)

    Maslov, V.M.

    1998-01-01

    Fission level densities (or fissioning nucleus level densities at fission saddle deformations) are required for statistical model calculations of actinide fission cross sections. Back-shifted Fermi-Gas Model, Constant Temperature Model and Generalized Superfluid Model (GSM) are widely used for the description of level densities at stable deformations. These models provide approximately identical level density description at excitations close to the neutron binding energy. It is at low excitation energies that they are discrepant, while this energy region is crucial for fission cross section calculations. A drawback of back-shifted Fermi gas model and traditional constant temperature model approaches is that it is difficult to include in a consistent way pair correlations, collective effects and shell effects. Pair, shell and collective properties of nucleus do not reduce just to the renormalization of level density parameter a, but influence the energy dependence of level densities. These effects turn out to be important because they seem to depend upon deformation of either equilibrium or saddle-point. These effects are easily introduced within GSM approach. Fission barriers are another key ingredients involved in the fission cross section calculations. Fission level density and barrier parameters are strongly interdependent. This is the reason for including fission barrier parameters along with the fission level densities in the Starter File. The recommended file is maslov.dat - fission barrier parameters. Recent version of actinide fission barrier data obtained in Obninsk (obninsk.dat) should only be considered as a guide for selection of initial parameters. These data are included in the Starter File, together with the fission barrier parameters recommended by CNDC (beijing.dat), for completeness. (author)

  4. Theoretical Description of the Fission Process

    International Nuclear Information System (INIS)

    Nazarewicz, Witold

    2009-01-01

    Advanced theoretical methods and high-performance computers may finally unlock the secrets of nuclear fission, a fundamental nuclear decay that is of great relevance to society. In this work, we studied the phenomenon of spontaneous fission using the symmetry-unrestricted nuclear density functional theory (DFT). Our results show that many observed properties of fissioning nuclei can be explained in terms of pathways in multidimensional collective space corresponding to different geometries of fission products. From the calculated collective potential and collective mass, we estimated spontaneous fission half-lives, and good agreement with experimental data was found. We also predicted a new phenomenon of trimodal spontaneous fission for some transfermium isotopes. Our calculations demonstrate that fission barriers of excited superheavy nuclei vary rapidly with particle number, pointing to the importance of shell effects even at large excitation energies. The results are consistent with recent experiments where superheavy elements were created by bombarding an actinide target with 48-calcium; yet even at high excitation energies, sizable fission barriers remained. Not only does this reveal clues about the conditions for creating new elements, it also provides a wider context for understanding other types of fission. Understanding of the fission process is crucial for many areas of science and technology. Fission governs existence of many transuranium elements, including the predicted long-lived superheavy species. In nuclear astrophysics, fission influences the formation of heavy elements on the final stages of the r-process in a very high neutron density environment. Fission applications are numerous. Improved understanding of the fission process will enable scientists to enhance the safety and reliability of the nation's nuclear stockpile and nuclear reactors. The deployment of a fleet of safe and efficient advanced reactors, which will also minimize radiotoxic

  5. Space Fission System Test Effectiveness

    International Nuclear Information System (INIS)

    Houts, Mike; Schmidt, Glen L.; Van Dyke, Melissa; Godfroy, Tom; Martin, James; Bragg-Sitton, Shannon; Dickens, Ricky; Salvail, Pat; Harper, Roger

    2004-01-01

    Space fission technology has the potential to enable rapid access to any point in the solar system. If fission propulsion systems are to be developed to their full potential, however, near-term customers need to be identified and initial fission systems successfully developed, launched, and utilized. One key to successful utilization is to develop reactor designs that are highly testable. Testable reactor designs have a much higher probability of being successfully converted from paper concepts to working space hardware than do designs which are difficult or impossible to realistically test. ''Test Effectiveness'' is one measure of the ability to realistically test a space reactor system. The objective of this paper is to discuss test effectiveness as applied to the design, development, flight qualification, and acceptance testing of space fission systems. The ability to perform highly effective testing would be particularly important to the success of any near-term mission, such as NASA's Jupiter Icy Moons Orbiter, the first mission under study within NASA's Project Prometheus, the Nuclear Systems Program

  6. Session summaries

    International Nuclear Information System (INIS)

    Sudo, Y.

    2002-01-01

    In the summary session, possible international activities in the field of basic studies on high-temperature engineering were discussed within the framework of the OECD/NEA Nuclear Science Committee (NSC). It was recommended to include topics relevant to fission-product behaviour and safety issues of HTGR in next meeting, in addition to the topics discussed in this meeting. The chairperson of the last session summarised the recommendations to be presented to the NSC into the following five topics as possible international activities: - Basic studies on behaviour of irradiated graphite/carbon and ceramic materials including their composites under both operation and storage conditions. - Development of in-core material characterisation and instrumentation methods. - Improvement in material properties through high-temperature irradiation. - Basic studies on HTGR fuel fabrication and performance including fission-product release. - Basic studies on safety issues of HTGR. It was also recommended that a further information exchange meeting focused on the organisation of the interactive collaboration activity with regard to the above topics be planned in 2003, tentatively in Oarai, Japan. (author)

  7. Fast fission phenomena

    International Nuclear Information System (INIS)

    Gregoire, Christian.

    1982-03-01

    Experimental studies of fast fission phenomena are presented. The paper is divided into three parts. In the first part, problems associated with fast fission processes are examined in terms of interaction potentials and a dynamic model is presented in which highly elastic collisions, the formation of compound nuclei and fast fission appear naturally. In the second part, a description is given of the experimental methods employed, the observations made and the preliminary interpretation of measurements suggesting the occurence of fast fission processes. In the third part, our dynamic model is incorporated in a general theory of the dissipative processes studied. This theory enables fluctuations associated with collective variables to be calculated. It is applied to highly inelastic collisions, to fast fission and to the fission dynamics of compound nuclei (for which a schematic representation is given). It is with these calculations that the main results of the second part can be interpreted [fr

  8. Storage of spent fuels: implementation of a research program on the risk of waste container rupture due to stress corrosion induced by fission products

    International Nuclear Information System (INIS)

    Parise, M.; Walle, E.; Foct, J.

    2001-01-01

    The following topics were dealt with: research programm on stress corrosion of spent fuel casks materials due to fission products, such as iodine, chemical interactions with zirconium, chemical aspects of stress corrosion, rupture risk assessment

  9. Fission product yields

    International Nuclear Information System (INIS)

    Valenta, V.; Hep, J.

    1978-01-01

    Data are summed up necessary for determining the yields of individual fission products from different fissionable nuclides. Fractional independent yields, cumulative and isobaric yields are presented here for the thermal fission of 235 U, 239 Pu, 241 Pu and for fast fission (approximately 1 MeV) of 235 U, 238 U, 239 Pu, 241 Pu; these values are included into the 5th version of the YIELDS library, supplementing the BIBFP library. A comparison is made of experimental data and possible improvements of calculational methods are suggested. (author)

  10. Fission neutron multiplicity calculations

    International Nuclear Information System (INIS)

    Maerten, H.; Ruben, A.; Seeliger, D.

    1991-01-01

    A model for calculating neutron multiplicities in nuclear fission is presented. It is based on the solution of the energy partition problem as function of mass asymmetry within a phenomenological approach including temperature-dependent microscopic energies. Nuclear structure effects on fragment de-excitation, which influence neutron multiplicities, are discussed. Temperature effects on microscopic energy play an important role in induced fission reactions. Calculated results are presented for various fission reactions induced by neutrons. Data cover the incident energy range 0-20 MeV, i.e. multiple chance fission is considered. (author). 28 refs, 13 figs

  11. Intermediate energy nuclear fission

    International Nuclear Information System (INIS)

    Hylten, G.

    1982-01-01

    Nuclear fission has been investigated with the double-kinetic-energy method using silicon surface barrier detectors. Fragment energy correlation measurements have been made for U, Th and Bi with bremsstrahlung of 600 MeV maximum energy. Distributions of kinetic energy as a function of fragment mass are presented. The results are compared with earlier photofission data and in the case of bismuth, with calculations based on the liquid drop model. The binary fission process in U, Yb, Tb, Ce, La, Sb, Ag and Y induced by 600 MeV protons has been investigated yielding fission cross sections, fragment kinetic energies, angular correlations and mass distributions. Fission-spallation competition calculations are used to deduce values of macroscopic fission barrier heights and nuclear level density parameter values at deformations corresponding to the saddle point shapes. We find macroscopic fission barriers lower than those predicted by macroscopic theories. No indication is found of the Businaro Gallone limit expected to occur somewhere in the mass range A = 100 to A = 140. For Ce and La asymmetric mass distributions similar to those in the actinide region are found. A method is described for the analysis of angular correlations between complementary fission products. The description is mainly concerned with fission induced by medium-energy protons but is applicable also to other projectiles and energies. It is shown that the momentum and excitation energy distributions of cascade residuals leading to fission can be extracted. (Author)

  12. Summaries of Idaho National Engineering Laboratory Radioecology and Ecology Program's waste management related studies

    International Nuclear Information System (INIS)

    Markham, O.D.

    1985-10-01

    The research summaries briefly describe studies concerning the activities of small mammals on and in waste disposal sites, revegetation of waste disposal sites, and contamination of wildlife by radionuclides and the spread of radionuclides by wildlife

  13. Acid deposition: State of science and technology. Summary report of the U.S. National Acid Precipitation Assessment Program

    International Nuclear Information System (INIS)

    Irving, P.M.; Smith, E.

    1991-09-01

    The twenty-seven State-of-Science and State-of-Technology (SOS/T) Reports, published in 1990 as the definitive scientific and technical synthesis of information obtained during the first decade of the U.S. national Acid Precipitation Assessment Program (NAPAP), are summarized in the document. In most cases, these summaries were the final chapter of the complete SOS/T Report

  14. FY 1994 annual summary report of the surveillance and maintenance activities for the Oak Ridge National Laboratory Environmental Restoration Program

    International Nuclear Information System (INIS)

    1994-11-01

    The Oak Ridge National Laboratory (ORNL) Environmental Restoration (ER) Surveillance and Maintenance (S and M) Program was initiated to manage former waste management and environmental research sites contaminated with radioactive materials and/or hazardous chemicals. The S and M Program is responsible for managing designated sites/facilities from the end of their operating lives until final disposition or site stabilization. To effectively manage and perform the various S and M Program responsibilities, five summary-level work breakdown structure (WBS) elements have been established: S and M Preliminary Investigations, Special Projects, Routine S and M, Inactive Groundwater Wells, and Project Management. Routine S and M activities were conducted as scheduled throughout fiscal years (FY) 1994 at applicable inactive waste management (WM) and other contaminated areas. Overall, the ER S and M Program maintains 47 facilities, performs vegetation maintenance on approximately 230 acres, maintains 54 inactive tanks, and provides overall site management on over 700 acres. In addition to the routine S and M activities, detailed site inspections were conducted at established frequencies on appropriate sites in the ER S and M Program. This document provides a summary of the FY 1994 ORNL ER S and M Program accomplishments

  15. NASA's Upper Atmosphere Research Program UARP and Atmospheric Chemistry Modeling and Analysis Program (ACMAP): Research Summaries 1994 - 1996. Report to Congress and the Environmental Protection Agency

    Science.gov (United States)

    Kendall, Rose (Compiler); Wolfe, Kathy (Compiler)

    1997-01-01

    Under the mandate contained in the FY 1976 NASA Authorization Act, the National Aeronautics and Space Administration (NASA) has developed and is implementing a comprehensive program of research, technology, and monitoring of the Earth's upper atmosphere, with emphasis on the stratosphere. This program aims at expanding our understanding to permit both the quantitative analysis of current perturbations as well as the assessment of possible future changes in this important region of our environment. It is carried out jointly by the Upper Atmosphere Research Program (UARP) and the Atmospheric Chemistry Modeling and Analysis Program (ACMAP), both managed within the Science Division in the Office of Mission to Planet Earth at NASA. Significant contributions to this effort are also provided by the Atmospheric Effects of Aviation Project (AEAP) of NASA's Office of Aeronautics. The long-term objectives of the present program are to perform research to: understand the physics, chemistry, and transport processes of the upper atmosphere and their effect on the distribution of chemical species in the stratosphere, such as ozone; understand the relationship of the trace constituent composition of the lower stratosphere and the lower troposphere to the radiative balance and temperature distribution of the Earth's atmosphere; and accurately assess possible perturbations of the upper atmosphere caused by human activities as well as by natural phenomena. In compliance with the Clean Air Act Amendments of 1990, Public Law 101-549, NASA has prepared a report on the state of our knowledge of the Earth's upper atmosphere, particularly the stratosphere, and on the progress of UARP and ACMAP. The report for the year 1996 is composed of two parts. Part 1 summarizes the objectives, status, and accomplishments of the research tasks supported under NASA UARP and ACMAP in a document entitled, Research Summary 1994-1996. Part 2 is entitled Present State of Knowledge of the Upper Atmosphere

  16. Directory of certificates of compliance for radioactive materials packages: Summary report of NRC approved quality assurance programs for radioactive material packages

    International Nuclear Information System (INIS)

    1987-11-01

    This directory contains a Summary Report of the US Nuclear Regulatory Commission's Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1987. This directory makes available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

  17. SEASAT economic assessment. Volume 1: Summary and conclusions. [management analysis of the economic benefits of the SEASAT program

    Science.gov (United States)

    1975-01-01

    A summary is presented of the economic benefits that can be derived from using the SEASAT Satellite System. A statement of the major findings of case studies of the practical applications of the SEASAT program to the following areas is given: (1) offshore oil and natural gas industry, (2) ocean mining, (3) coastal zones, (4) oil exploration in Arctic regions, (5) ocean fishing, and (6) ports and harbors. Also given is a description of the SEASAT System and its performance. A computer program, used to optimize SEASAT System's costs and operational requirements, is also considered.

  18. Conference summaries

    International Nuclear Information System (INIS)

    Phillips, G.J.

    1985-01-01

    The 113 papers presented at this conference covered the areas of 1) fuel design, development and production; 2) nuclear plant safety; 3) nuclear instrumentation; 4) public and regulatory matters; 5) developments and opportunities in fusion; 6) fuel behaviour under normal operating conditions; 7) nuclear plant design and operations; 8) materials science and technology; 9) nuclear power issues; 10) fusion technology; 11) fuel behaviour under accident conditions; 12) large scale fuel channel replacement programs; 13) thermalhydraulics experimental studies; 14) reactor physics and analysis; 15) applications of accelerators; 16) fission product release and severe fuel damage under accident conditions; 17) thermalhydraulics modeling and assessments; 18) waste management and the environment; and 20) new reactor concepts

  19. Fission neutron spectra measurements at LANSCE - Status and plans

    International Nuclear Information System (INIS)

    Haight, R. C.; Noda, S.; Nelson, R. O.; O'Donnell, J. M.; Devlin, M.; Chatillon, A.; Granier, T.; Taiebb, J.; Laurent, B.; Belier, G.; Becker, J. A.; Wu, C. Y.

    2010-01-01

    A program to measure fission neutron spectra from neutron-induced fission of actinides is underway at the Los Alamos Neutron Science Center (LANSCE) in a collaboration among the CEA laboratory at Bruyeres-le-Chatel, Lawrence Livermore National Laboratory and Los Alamos National Laboratory. The spallation source of fast neutrons at LANSCE is used to provide incident neutron energies from less than 1 MeV to 100 MeV or higher. The fission events take place in a gas-ionization fission chamber, and the time of flight from the neutron source to that chamber gives the energy of the incident neutron. Outgoing neutrons are detected by an array of organic liquid scintillator neutron detectors, and their energies are deduced from the time of flight from the fission chamber to the neutron detector. Measurements have been made of the fission neutrons from fission of 235 U, 238 U, 237 Np and 239 Pu. The range of outgoing energies measured so far is from 0.7 MeV to approximately 8 MeV. These partial spectra and average fission neutron energies are compared with evaluated data and with models of fission neutron emission. Results to date are summarized in this presentation. Future plans are to make significant improvements in the fission chambers, neutron detectors, signal processing, data acquisition and the experimental environment to provide high fidelity data including measurements of fission neutrons below 0.7 MeV and improvements in the data above 8 MeV. (authors)

  20. Contracts, grants and funding summary of supersonic cruise research and variable-cycle engine technology programs, 1972 - 1982

    Science.gov (United States)

    Hoffman, S.; Varholic, M. C.

    1983-01-01

    NASA-SCAR (AST) program was initiated in 1972 at the direct request of the Executive Office of the White House and Congress following termination of the U.S. SST program. The purpose of SCR was to conduct a focused research and technology program on those technology programs which contributed to the SST termination and, also, to provide an expanded data base for future civil and military supersonic transport aircraft. Funding for the Supersonic Cruise Research (SCR) Program was initiated in fiscal year 1973 and terminated in fiscal year 1981. The program was implemented through contracts and grants with industry, universities, and by in-house investigations at the NASA/OAST centers. The studies included system studies and five disciplines: propulsion, stratospheric emissions impact, materials and structures, aerodynamic performance, and stability and control. The NASA/Lewis Variable-Cycle Engine (VCE) Component Program was initiated in 1976 to augment the SCR program in the area of propulsion. After about 2 years, the title was changed to VCE Technology program. The total number of contractors and grantees on record at the AST office in 1982 was 101 for SCR and 4 for VCE. This paper presents a compilation of all the contracts and grants as well as the funding summaries for both programs.

  1. Dual-fission chamber and neutron beam characterization for fission product yield measurements using monoenergetic neutrons

    Science.gov (United States)

    Bhatia, C.; Fallin, B.; Gooden, M. E.; Howell, C. R.; Kelley, J. H.; Tornow, W.; Arnold, C. W.; Bond, E. M.; Bredeweg, T. A.; Fowler, M. M.; Moody, W. A.; Rundberg, R. S.; Rusev, G.; Vieira, D. J.; Wilhelmy, J. B.; Becker, J. A.; Macri, R.; Ryan, C.; Sheets, S. A.; Stoyer, M. A.; Tonchev, A. P.

    2014-09-01

    A program has been initiated to measure the energy dependence of selected high-yield fission products used in the analysis of nuclear test data. We present out initial work of neutron activation using a dual-fission chamber with quasi-monoenergetic neutrons and gamma-counting method. Quasi-monoenergetic neutrons of energies from 0.5 to 15 MeV using the TUNL 10 MV FM tandem to provide high-precision and self-consistent measurements of fission product yields (FPY). The final FPY results will be coupled with theoretical analysis to provide a more fundamental understanding of the fission process. To accomplish this goal, we have developed and tested a set of dual-fission ionization chambers to provide an accurate determination of the number of fissions occurring in a thick target located in the middle plane of the chamber assembly. Details of the fission chamber and its performance are presented along with neutron beam production and characterization. Also presented are studies on the background issues associated with room-return and off-energy neutron production. We show that the off-energy neutron contribution can be significant, but correctable, while room-return neutron background levels contribute less than <1% to the fission signal.

  2. A Study of Minimum Competency Testing Programs. Final Summary and Analysis Report.

    Science.gov (United States)

    Gorth, William Phillip; Perkins, Marcy R.

    To portray the status of minimum competency testing programs nationwide; as of June 30, 1979, on-site visits were conducted with directors of all 31 state programs and 20 local district programs. Most programs were developed since 1976; 14 state and 13 local programs are fully implemented. The state board of education mandated 16 state programs;…

  3. The nuclear fission

    International Nuclear Information System (INIS)

    Fiorentino, J.

    1983-01-01

    The nuclear fission process considering initially the formation of compound nucleus and finishing with radioactive decay of fission products is studied. The process is divided in three parts which consist of the events associated to the nucleus of intermediate transitional state, the scission configuration, and the phenomenum of post scission. (M.C.K.) [pt

  4. Fission gas detection system

    International Nuclear Information System (INIS)

    Colburn, R.P.

    1984-01-01

    A device for collecting fission gas released by failed fuel rods which device uses a filter adapted to pass coolant but to block passage of fission gas bubbles due to the surface tension of the bubbles. The coolant may be liquid metal. (author)

  5. Muon-induced fission

    International Nuclear Information System (INIS)

    Polikanov, S.

    1980-01-01

    A review of recent experimental results on negative-muon-induced fission, both of 238 U and 232 Th, is given. Some conclusions drawn by the author are concerned with muonic atoms of fission fragments and muonic atoms of the shape isomer of 238 U. (author)

  6. Relativistic Coulomb Fission

    Science.gov (United States)

    Norbury, John W.

    1992-01-01

    Nuclear fission reactions induced by the electromagnetic field of relativistic nuclei are studied for energies relevant to present and future relativistic heavy ion accelerators. Cross sections are calculated for U-238 and Pu-239 fission induced by C-12, Si-28, Au-197, and U-238 projectiles. It is found that some of the cross sections can exceed 10 b.

  7. Feasibility study on fission moly target development

    International Nuclear Information System (INIS)

    Kim, Byung Ku; Kim, Seong Nyun; Shon, Dong Seong; Choi, Chang Beom; Lee, Jae Kuk; Park, Jin Ho; Jeong, Won Myung; Jeon, Kwan Sik; You, Jae Hyung; Kang, Kyung Chul; Ahn, Jong Hwan; Ju, Po Kuk

    1996-01-01

    A multi-purpose research reactor, HANARO has been operated on the beginning of 1995 and can be utilized for production of various radioisotopes. And a R and D program for fission Mo production was established, and the technical and economical feasibility study has been performed for fission Mo production in Korea. In this study the process for fission Mo production was recommended as follows; 1. Target : UO 2 of annulus type. 2. Separation and purification : Nitric acid dissolution → Alumina adsorption → Benzoin oxime precipitation → Alumina adsorption. And more desirable plan for steady supply of fission Mo were suggested in following viewpoints; 1. Technical collaboration with foreign company. 2. Backup supply system. 3. Marketing arrangement. (Author)

  8. Theory of neutron emission in fission

    International Nuclear Information System (INIS)

    Madland, D.G.

    1998-01-01

    A survey of theoretical representations of two of the observables in neutron emission in fission is given, namely, the prompt fission neutron spectrum N(E) and the average prompt neutron multiplicity bar ν p . Early representations of the two observables are presented and their deficiencies are discussed. This is followed by summaries and some examples of recent theoretical models for the calculation of these quantities. Emphasis is placed upon the predictability and accuracy of the recent models. In particular, the dependencies of N(E) and bar ν p upon the fissioning nucleus and its excitation energy are treated in detail for the Los Alamos model. Recent work in the calculation of the prompt fission neutron spectrum matrix N(E, E n ), where E n is the energy of the neutron inducing fission, is then discussed. Concluding remarks address the current status of the ability to calculate these observables with confidence, the direction of future theoretical efforts, and limitations to current (and future) approaches. This paper is an extension of a similar paper presented at the International Centre for Theoretical Physics in 1996

  9. Theoretical models of neutron emission in fission

    International Nuclear Information System (INIS)

    Madland, D.G.

    1992-01-01

    A brief survey of theoretical representations of two of the observables in neutron emission in fission is given, namely, the prompt fission neutron spectrum N(E) and the average prompt neutron multiplicity bar v p . Early representations of the two observables are presented and their deficiencies are discussed. This is followed by summaries and examples of recent theoretical models for the calculation of these quantities. Emphasis is placed upon the predictability and accuracy of the new models. In particular, the dependencies of N(E) and bar v p upon the fissioning nucleus and its excitation energy are treated. Recent work in the calculation of the prompt fission neutron spectrum matrix N(E,E n ), where E n is the energy of the neutron inducing fission, is then discussed. Concluding remarks address the current status of our ability to calculate these observables with confidence, the direction of future theoretical efforts, and limititations to current and future calculations. Finally, recommendations are presented as to which model should be used currently and which model should be pursued in future efforts

  10. Fission product and aerosol behaviour within the containment

    International Nuclear Information System (INIS)

    Beard, A.M.; Benson, C.G.; Bowsher, B.R.; Dickinson, S.; Nichols, A.L.

    1990-04-01

    Experimental studies have been undertaken to characterise the behaviour of fission products in the containment of a pressurised water reactor during a severe accident. The following aspects of fission product transport have been studied: (a) aerosol nucleation, (b) vapour transport processes, (c) chemical forms of high-temperature vapours, (d) interaction of fission product vapours with aerosols generated from within the reactor core, (e) resuspension processes, (f) chemistry in the containment. Chemical effects have been shown to be important in defining and quantifying fission product source terms in a wide range of accident sequences. Both the chemical forms of the fission product vapours and their interactions with reactor materials aerosols could have a major effect on the magnitude and physicochemical forms of the radioactive emission from a severe reactor accident. Only the main conclusions are presented in this summary document; detailed technical aspects of the work are described in separate reports listed in the annex

  11. Study of hypernuclei fission

    International Nuclear Information System (INIS)

    Malek, F.

    1990-01-01

    This work is about PS177 experience made on LEAR machine at CERN in 1988. The annihilation reaction of anti protons on a target of Bismuth or Uranium is studied. Lambda particles are produced by this reaction, in the nucleus in 2% of cases 7.1 10 -3 hypernuclei by stopped antiproton in the target are produced. The prompt hypernucleus fission probability of uranium is 75% and that of Bismuth 10%. The mass distribution of fission fragments is symmetrical ((≡ the excitation energy of the nucleus is very high). If the nucleus hasn't fissioned, the non-mesonic lambda decay, gives it an energy of 100 MeV, what allows to fission later. This fission is delayed because the hypernucleus lifetime is 1.3 +0.25 -0.21 10 -10 sec for Bismuth [fr

  12. Fission, fusion and the energy crisis

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, S E [Aston Univ., Birmingham (UK)

    1980-01-01

    The subject is covered in chapters, entitled: living on capital (energy reserves and consumption forecasts); the atom and its nucleus, mass and energy; fission and the bomb; the natural uranium reactor; enriched reactors; control and safety; long-term economics (the breeder reactions and nuclear fuel reserves); short-term economics (cost per kilowatt hour); national nuclear power programmes; nuclear power and the environment (including reprocessing, radioactive waste management, public relations); renewable energy sources; the fusion programme; summary and comment.

  13. The nuclear fission process

    International Nuclear Information System (INIS)

    Wagemans, C.

    1991-01-01

    Fifty years after its discovery, the nuclear fission phenomenon is of recurring interest. When its fundamental physics aspects are considered, fission is viewed in a very positive way, which is reflected in the great interest generated by the meetings and large conferences organized for the 50th anniversary of its discovery. From a purely scientific and practical point of view, a new book devoted to the (low energy) nuclear fission phenomenon was highly desirable considering the tremendous amount of new results obtained since the publication of the book Nuclear Fission by Vandenbosch and Huizenga in 1973 (Academic Press). These new results could be obtained thanks to the growth of technology, which enabled the construction of powerful new neutron sources, particle and heavy ion accelerators, and very performant data-acquisition and computer systems. The re-invention of the ionization chamber, the development of large fission fragment spectrometers and sophisticated multiparameter devices, and the production of exotic isotopes also contributed significantly to an improved understanding of nuclear fission. This book is written at a level to introduce graduate students to the exciting subject of nuclear fission. The very complete list of references following each chapter also makes the book very useful for scientists, especially nuclear physicists. The book has 12 chapters covering the fission barrier and the various processes leading to fission as well as the characteristics of the various fission reaction products. In order to guarantee adequate treatment of the very specialized research fields covered, several distinguished scientists actively involved in some of these fields were invited to contribute their expertise as authors or co-authors of the different chapters

  14. Program plan for the DOE Office of Fusion Energy First Wall/Blanket/Shield Engineering Technology Program. Volume I. Summary, objectives and management. Revision 2

    International Nuclear Information System (INIS)

    1982-08-01

    This document defines a plan for conducting selected aspects of the engineering testing required for magnetic fusion reactor FWBS components and systems. The ultimate product of this program is an established data base that contributes to a functional, reliable, maintainable, economically attractive, and environmentally acceptable commercial fusion reactor first wall, blanket, and shield system. This program plan updates the initial plan issued in November of 1980 by the DOE/Office of Fusion Energy (unnumbered report). The plan consists of two parts. Part I is a summary of activities, responsibilities and program management including reporting and interfaces with other programs. Part II is a compilation of the Detailed Technical Plans for Phase I (1982 to 1984) developed by the participants during Phase 0 of the program

  15. INTERNATIONAL PROGRAM: SUMMARY REPORT ON THE PROPERTIES OF CEMENTITIOUS WASTE FORMS

    International Nuclear Information System (INIS)

    Harbour, J

    2007-01-01

    This report provides a summary of the results on the properties of cementitious waste forms obtained as part of the International Program. In particular, this report focuses on the results of Task 4 of the Program that was initially entitled ''Improved Retention of Key Contaminants of Concern in Low Temperature Immobilized Waste Forms''. Task 4 was a joint program between Khlopin Radium Institute and the Savannah River National Laboratory. The task evolved during this period into a study of cementitious waste forms with an expanded scope that included heat of hydration and fate and transport modeling. This report provides the results for Task 4 of the International Program as of the end of FY06 at which time funding for Task 4 was discontinued due to the needs of higher priority tasks within the International Program. Consequently, some of the subtasks were only partially completed, but it was considered important to capture the results up to this point in time. Therefore, this report serves as the closeout report for Task 4. The degree of immobilization of Tc-99 within the Saltstone waste form was measured through monolithic and crushed grout leaching tests. An effective diffusion coefficient of 4.8 x 10 -12 (Leach Index of 11.4) was measured using the ANSI/ANS-16.1 protocol which is comparable with values obtained for tank closure grouts using a dilute salt solution. The leaching results show that, in the presence of concentrated salt solutions such as those that will be processed at the Saltstone Production Facility, blast furnace slag can effectively reduce pertechnetate to the immobile +4 oxidation state. Leaching tests were also initiated to determine the degree of immobilization of selenium in the Saltstone waste form. Results were obtained for the upper bound of projected selenium concentration (∼5 x 10 -3 M) in the salt solution that will be treated at Saltstone. The ANSI/ANS 16.1 leaching tests provided a value for the effective diffusivity of ∼5 x 10

  16. Nondestructive analysis of the RA fuel burnup, Calculation of the gamma activity ratio of fission products in the fuel - program QU0C1

    International Nuclear Information System (INIS)

    Bulovic, V.F.

    1973-01-01

    The γ radiation of RA reactor fuel element was measured under precisely defined measuring conditions. The spectrum was analysed by spectrometer with semiconductor Ge(Li) detector. The gamma counting rate in the fuel spectrum is defined as a function of fission product activity, gamma energy and yield, fuel thickness and additional absorbers, dimensions of the gamma collimator. Activity ratio of two fission products is defined as a function of counting rate peaks and part of the mentioned quantities. Four options for calculating the activities for fission products are discussed. Three of them are covered by the QU0C1 code written in FORTRAN for the CDC 3600 computer. The code is included in this report [sr

  17. Evaluation of nuclear power plant environmental impact prediction, based on monitoring programs. Summary and recommendations

    International Nuclear Information System (INIS)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

    1977-02-01

    An evaluation of the effectivenss of non-radiological environmental monitoring programs is presented. The monitoring programs for Monticello, Haddam Neck, and Millstone Nuclear Generating Plants are discussed. Recommendations for improvements in monitoring programs are presented

  18. Household Hazardous Waste Disposal Project. Summary Report. Metro Toxicant Program Report No. 1A.

    Science.gov (United States)

    Ridgley, Susan M.; Galvin, David V.

    The Household Hazardous Waste Disposal Project was established as an interagency effort to reduce the level of toxicants entering the environment by developing a control plan for the safe disposal of small quantities of household chemicals. This summary report provides an overview of the aspects of this problem that were examined, and the steps…

  19. Three Mile Island technical information and examination program instrumentation and electrical summary report

    International Nuclear Information System (INIS)

    Meininger, R.D.

    1985-07-01

    This report summarizes the investigations on instrumentation and electrical systems that were subjected to a loss-of-coolant accident environment during and following the accident at Three Mile Island Unit-2 (TMI-2) on March 28, 1979. The report is a summary of information previously published in GEND-INF reports, plus current knowledge of the investigators

  20. Material synergism fusion-fission

    International Nuclear Information System (INIS)

    Sankara Rao, K.B.; Raj, B.; Cook, I.; Kohyama, A.; Dudarev, S.

    2007-01-01

    In fission and fusion reactors the common features such as operating temperatures and neutron exposures will have the greatest impact on materials performance and component lifetimes. Developing fast neutron irradiation resisting materials is a common issue for both fission and fusion reactors. The high neutron flux levels in both these systems lead to unique materials problems like void swelling, irradiation creep and helium embitterment. Both fission and fusion rely on ferritic-martensitic steels based on 9%Cr compositions for achieving the highest swelling resistance but their creep strength sharply decreases above ∝ 823K. The use of oxide dispersion strengthened (ODS) alloys is envisaged to increase the operating temperature of blanket systems in the fusion reactors and fuel clad tubes in fast breeder reactors. In view of high operating temperatures, cyclic and steady load conditions and the long service life, properties like creep, low cycle fatigue,fracture toughness and creepfatigue interaction are major considerations in the selection of structural materials and design of components for fission and fusion reactors. Currently, materials selection for fusion systems has to be based upon incomplete experimental database on mechanical properties. The usage of fairly well developed databases, in fission programmes on similar materials, is of great help in the initial design of fusion reactor components. Significant opportunities exist for sharing information on technology of irradiation testing, specimen miniaturization, advanced methods of property measurement, safe windows for metal forming, and development of common materials property data base system. Both fusion and fission programs are being directed to development of clean steels with very low trace and tramp elements, characterization of microstructure and phase stability under irradiation, assessment of irradiation creep and swelling behaviour, studies on compatibility with helium and developing

  1. Status of fission power

    International Nuclear Information System (INIS)

    Levenson, M.

    1977-01-01

    Fission energy is reviewed from the viewpoints of technology, economics, politics, manufacturers, consumers, and foreign countries. Technically, the reactor program is operating and the light water reactor industry shows signs of maturing, although recent business has been disappointing. Marketing of gas-cooled reactors depends, not on technical, but economic and political issues. Liquid metal fast breeder reactors have been demonstrated worldwide, while the gas-cooled fast breeder remains an undemonstrated option. Nuclear plants, currently costing the same as coal plants with scrubbers, are the cheapest option for utilities because most of the cost is imbedded. The defeat of nuclear initiatives in seven states indicates that public feeling is not as anti-nuclear as opponents to nuclear power claim. The harshness of last winter demonstrated the advantages of a power source that is not so sensitive to the weather for reliable operation and transport, as well as low cost energy. Other nations are proceeding to build a nuclear capability, which the U.S. may jeopardize because of concerns about the fuel cycle, nuclear waste disposal, uranium reserves, and nuclear proliferation

  2. Draft program plan for TNS: the next step after the tokamak fusion test reactor. Part I. Summary

    International Nuclear Information System (INIS)

    Roberts, M.

    1977-10-01

    A draft program plan for TNS has been prepared which consists of two basic parts--an R and D Needs Assessment and a Project Plan with schedules and necessary implementation steps. In this brief but intensive effort, questions concerning (1) the present basis for the TNS program, (2) the principal gaps in the supporting program, and (3) the necessary actions to be taken to implement the TNS program were examined. The study supported the thesis that the physics and technology bases do exist from which to start the TNS design as a central fusion program goal. Specific recommendations are made to emphasize those physics, technology, and engineering areas in which there are program gaps. In the project engineering study, a basic schedule with close support from the R and D program is developed from which recommendations on administrative actions and areas for further elucidation are made. This document presents in summary form the findings of the study, the development of the principal theses, and the recommendation to ERDA-DMFE

  3. US Subseabed Disposal Program radioecological data base: summaries of available radionuclide concentration factors and biological half-lives

    International Nuclear Information System (INIS)

    Gomez, L.S.; Marietta, M.G.; Jackson, D.W.

    1984-01-01

    The US Subseabed Disposal Program has compiled an extensive objective concentration factor and biological half-life data base from the international marine radioecological literature. A microcomputer-based data management system has been implemented to provide statistical and graphical summaries of these data. The data base is constructed in a manner which allows subsets to be sorted using a number of inter-study variables such as organism category, tissue/organ category, geographic location (for in situ studies), and several laboratory-related conditions (e.g., exposure time and exposure concentration). We discuss concentration factor data summaries for many elements. We also discuss summary material for biological half-life data. We discuss the results of our review with the estimates of mean concentration factors provided by the IAEA. It is proposed that this presentation scheme will enable those concerned with predictive assessment of radiation dose in the marine environment to make a more judicious selection of data for a given application. 7 references

  4. HTGR Fuels and Core Development Program. Quarterly progress report for the period ending August 31, 1977. [Graphite and fuel irradiation; fission product release

    Energy Technology Data Exchange (ETDEWEB)

    1977-09-01

    The work reported includes studies of reactions between core materials and coolant impurities, basic fission product transport mechanisms, core graphite development and testing, the development and testing of recyclable fuel systems, and physics and fuel management studies. Materials studies include irradiation capsule tests of both fuel and graphite. Experimental procedures and results are discussed and data are presented.

  5. Fission in a Plasma

    Energy Technology Data Exchange (ETDEWEB)

    Younes, W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-10-26

    A three-year theory project was undertaken to study the fission process in extreme astrophysical environments, such as the crust of neutron stars. In the first part of the project, the effect of electron screening on the fission process was explored using a microscopic approach. For the first time, these calculations were carried out to the breaking point of the nucleus. In the second part of the project, the population of the fissioning nucleus was calculated within the same microscopic framework. These types of calculations are extremely computer-intensive and have seldom been applied to heavy deformed nuclei, such as fissioning actinides. The results, tools and methodologies produced in this work will be of interest to both the basic-science and nuclear-data communities.

  6. Fusion-fission dynamics

    International Nuclear Information System (INIS)

    Blocki, J.; Planeta, R.; Brzychczyk, J.; Grotowski, K.

    1992-01-01

    Classical dynamical calculations of the heavy ion induced fission processes have been performed for the reactions 40 Ar+ 141 Pr, 20 Ne+ 165 Ho and 12 C+ 175 Lu leading to the iridium like nucleus. As a result prescission lifetimes were obtained and compared with the experimental values. The comparison between the calculated and experimental lifetimes indicates that the one-body dissipation picture is much more relevant in describing the fusion-fission dynamics than the two-body one. (orig.)

  7. Florida maintenance rating program (MRP) assessment and enhancement : final report, May 28, 2008 [summary].

    Science.gov (United States)

    2008-01-01

    The Florida Department of Transportation : (FDOT) has used its maintenance rating : program (MRP) to evaluate the states : highway maintenance conditions and : determine asset maintenance needs since : 1985. Periodic evaluation of the program is :...

  8. FY 1987 program summary document: Office of Defense Waste and Transportation Management

    International Nuclear Information System (INIS)

    1987-04-01

    This document describes the Office of Defense Waste and Transportation Management (DWTM) Program as supported by the President's Fiscal Year (FY) 1987 Budget Request to Congress. It specifically addresses the program's organization, objectives, strategies, and plans for FY 1987

  9. Exploratory Technology Research Program for electrochemical energy storage: Executive summary report for 1993

    International Nuclear Information System (INIS)

    Kinoshita, K.

    1994-09-01

    The U.S. Department of Energy's Office of Propulsion Systems provides support for an Electrochemical Energy Storage Program, that includes research and development (R ampersand D) on advanced rechargeable batteries and fuel cells. A major goal of this program is to develop electrochemical power sources suitable for application in electric vehicles (EVs). The program centers on advanced systems that offer the potential for high performance and low life-cycle costs, both of which are necessary to permit significant penetration into commercial markets. The DOE Electrochemical Energy Storage Program is divided into two projects: the Electric Vehicle Advanced Battery Systems (EVABS) Development Program and the Exploratory Technology Research (ETR) Program. The EVABS Program management responsibility has been assigned to Sandia National Laboratories (SNL); Lawrence Berkeley Laboratory (LBL) is responsible for management of the FIR Program. The EVABS and ETR Programs include an integrated matrix of R ampersand D efforts designed to advance progress on selected candidate electrochemical systems. The United States Advanced Battery Consortium (USABC), a tripartite undertaking between DOE, the U.S. automobile manufacturers and the Electric Power Research Institute (EPRI), was formed in 1991 to accelerate the development of advanced batteries for consumer EVs. The role of the FIR Program is to perform supporting research on the advanced battery systems under development by the USABC and EVABS Program, and to evaluate new systems with potentially superior performance, durability and/or cost characteristics. The specific goal of the ETR Program is to identify the most promising electrochemical technologies and transfer them to the USABC, the battery industry and/or the EVABS Program for further development and scale-up. This report summarizes the research, financial and management activities relevant to the ETR Program in CY 1993

  10. Technical summary of groundwater quality protection program at Savannah River Plant. Volume 1. Site geohydrology, and solid and hazardous wastes

    International Nuclear Information System (INIS)

    Christensen, E.J.; Gordon, D.E.

    1983-12-01

    The program for protecting the quality of groundwater underlying the Savannah River Plant (SRP) is described in this technical summary report. The report is divided into two volumes. Volume I contains a discussion of the general site geohydrology and of both active and inactive sites used for disposal of solid and hazardous wastes. Volume II includes a discussion of radioactive waste disposal. Most information contained in these two volumes is current as of December 1983. The groundwater quality protection program has several elements which, taken collectively, are designed to achieve three major goals. These goals are to evaluate the impact on groundwater quality as a result of SRP operations, to restore or protect groundwater quality by taking corrective action as necessary, and to ensure disposal of waste materials in accordance with regulatory guidelines

  11. Southwest regional geothermal operations research program. Summary report. First project year, June 1977--August 1978

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, R.T.; Davidson, R.

    1978-12-01

    A summary report is given of the information, data, and results presented by New Mexico Energy Institute and the five State Teams in their separate draft reports. The objective is to develop scenarios for the development of each identified geothermal resource area in Arizona, Colorado, Nevada, New Mexico and Utah. Included are an overview; an economic analysis; institutitional procedures, contraints, and incentives; location of geothermal resources in the southwest; geothermal development postulations, state by state; and recommended actions for promoting and accelerating geothermal development. (MHR)

  12. Potentials of fissioning plasmas

    International Nuclear Information System (INIS)

    Karlheinz, Thom.

    1979-01-01

    Successful experiments with the nuclear pumping of lasers have demonstrated that in gaseous medium the kinetic energy of fission fragments can be converted directly into non-equilibrium optical radiation. This confirms the concept that the fissioning medium in a gas-phase nuclear reactor shows an internal structure such as a plasma in nearly thermal equilibrium varying up to a state of extreme-non-equilibrium. The accompanying variations of temperatures, pressure and radiative spectrum suggest wide ranges of applications. For example, in the gas-phase fission reactor concept enriched uranium hexafluoride or an uranium plasma replaces conventional fuel elements and permits operation above the melting point of solid materials. This potential has been motivation for the US National Aeronautics and Space Administration (NASA) to conduct relevant research for high specific impulse propulsion in space. The need to separate the high temperature gaseous fuel from the surfaces of a containing vessel and to protect them against thermal radiation has led to the concept of an externally moderated reactor in which the fissioning gaseous material is suspended by fluid dynamic means and the flow of opaque buffer gas removes the power. The gaseous nuclear fuel can slowly be circulated through the reactor for continuous on-site reprocessing including the annihilation of transuranium actinides at fission when being fed back into the reactor. An equilibrium of the generation and destruction of such actinides at fission when being fed back into the reactor. An equilibrium of the generation and destruction of such actinides can thus be achieved. These characteristics and the unique radiative properties led to the expectation that the gas-phase fission reactor could feature improved safety, safeguarding and economy, in addition to new technologies such as processing, photochemistry and the transmission of power over large distances in space

  13. A summary of the program and progress to 1984 December of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.

    1986-08-01

    The Canadian Nuclear Fuel Waste Management Program involves research into the storage and transportation of used nuclear fuel, immobilization of fuel waste, and deep geological disposal of the immobilized waste. The program is now in the fifth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the safety and environmental aspects of the deep underground disposal of immobilized fuel waste in plutonic rock. The objectives of the research for each component of the program and the progress made to the end of 1984 are described in this report. 74 refs

  14. Summary results of an assessment of research projects in the Nuclear Medicine Research program

    International Nuclear Information System (INIS)

    1988-01-01

    In May 1987, OHER management requested the Office of Program Analysis (OPA) to conduct a peer review of the projects of the DOE Nuclear Medicine Research program. This was done using procedures and a quantitative methodology OPA developed for assessing DOE research programs. Sixty-three individual nuclear medicine projects were reviewed by seven panels; one panel on isotopes and radioisotopes, three on radiopharmacology, two on clinical feasibility, and one on instrumentation. Each panel consisted of five to ten knowledgeable reviewers. 5 figs

  15. Historically Black Colleges and Universities Radioactive Waste Management Research Program: Summary of activities, 1985-1986

    International Nuclear Information System (INIS)

    1986-01-01

    This report summarizes the 1985 to 1986 activities of the Historically Black Colleges and Universities (HBCUs) Radioactive Waste Management Research Program sponsored by the Office of Civilian Radioactive Waste Management of the US Department of Energy (DOE). The first set of three awards was made in September,1984. In September, 1985, two of these projects were renewed and a new proposal was funded. The program has been enthusiastically received by the community of HBCUs and the program sponsor

  16. Correlated prompt fission data in transport simulations

    Science.gov (United States)

    Talou, P.; Vogt, R.; Randrup, J.; Rising, M. E.; Pozzi, S. A.; Verbeke, J.; Andrews, M. T.; Clarke, S. D.; Jaffke, P.; Jandel, M.; Kawano, T.; Marcath, M. J.; Meierbachtol, K.; Nakae, L.; Rusev, G.; Sood, A.; Stetcu, I.; Walker, C.

    2018-01-01

    nonproliferation, safeguards, nuclear energy, and defense programs. This review provides an overview of the topic, starting from theoretical considerations of the fission process, with a focus on correlated signatures. It then explores the status of experimental correlated fission data and current efforts to address some of the known shortcomings. Numerical simulations employing the FREYA and CGMF codes are compared to experimental data for a wide range of correlated fission quantities. The inclusion of those codes into the MCNP6.2 and MCNPX - PoliMi transport codes is described and discussed in the context of relevant applications. The accuracy of the model predictions and their sensitivity to model assumptions and input parameters are discussed. Finally, a series of important experimental and theoretical questions that remain unanswered are presented, suggesting a renewed effort to address these shortcomings.

  17. Correlated prompt fission data in transport simulations

    Energy Technology Data Exchange (ETDEWEB)

    Talou, P.; Jaffke, P.; Kawano, T.; Stetcu, I. [Los Alamos National Laboratory, Nuclear Physics Group, Theoretical Division, Los Alamos, NM (United States); Vogt, R. [Lawrence Livermore National Laboratory, Nuclear and Chemical Sciences Division, Livermore, CA (United States); University of California, Physics Department, Davis, CA (United States); Randrup, J. [Lawrence Berkeley National Laboratory, Nuclear Science Division, Berkeley, CA (United States); Rising, M.E.; Andrews, M.T.; Sood, A. [Los Alamos National Laboratory, Monte Carlo Methods, Codes, and Applications Group, Los Alamos, NM (United States); Pozzi, S.A.; Clarke, S.D.; Marcath, M.J. [University of Michigan, Department of Nuclear Engineering and Radiological Sciences, Ann Arbor, MI (United States); Verbeke, J.; Nakae, L. [Lawrence Livermore National Laboratory, Nuclear and Chemical Sciences Division, Livermore, CA (United States); Jandel, M. [Los Alamos National Laboratory, Nuclear and Radiochemistry Group, Los Alamos, NM (United States); University of Massachusetts, Department of Physics and Applied Physics, Lowell, MA (United States); Meierbachtol, K. [Los Alamos National Laboratory, Nuclear Engineering and Nonproliferation, Los Alamos, NM (United States); Rusev, G.; Walker, C. [Los Alamos National Laboratory, Nuclear and Radiochemistry Group, Los Alamos, NM (United States)

    2018-01-15

    , safeguards, nuclear energy, and defense programs. This review provides an overview of the topic, starting from theoretical considerations of the fission process, with a focus on correlated signatures. It then explores the status of experimental correlated fission data and current efforts to address some of the known shortcomings. Numerical simulations employing the FREYA and CGMF codes are compared to experimental data for a wide range of correlated fission quantities. The inclusion of those codes into the MCNP6.2 and MCNPX-PoliMi transport codes is described and discussed in the context of relevant applications. The accuracy of the model predictions and their sensitivity to model assumptions and input parameters are discussed. Finally, a series of important experimental and theoretical questions that remain unanswered are presented, suggesting a renewed effort to address these shortcomings. (orig.)

  18. Health-related Culinary Education: A Summary of Representative Emerging Programs for Health Professionals and Patients.

    Science.gov (United States)

    Polak, Rani; Phillips, Edward M; Nordgren, Julia; La Puma, John; La Barba, Julie; Cucuzzella, Mark; Graham, Robert; Harlan, Timothy S; Burg, Tracey; Eisenberg, David

    2016-01-01

    Beneficial correlations are suggested between food preparation and home food preparation of healthy choices. Therefore, there is an emergence of culinary medicine (CM) programs directed at both patients and medical professionals which deliver education emphasizing skills such as shopping, food storage, and meal preparation. The goal of this article is to provide a description of emerging CM programs and to imagine how this field can mature. During April 2015, 10 CM programs were identified by surveying CM and lifestyle medicine leaders. Program directors completed a narrative describing their program's structure, curricula, educational design, modes of delivery, funding, and cost. Interviews were conducted in an effort to optimize data collection. All 10 culinary programs deliver medical education curricula educating 2654 health professionals per year. Educational goals vary within the domains of (1) provider's self-behavior, (2) nutritional knowledge and (3) prescribing nutrition. Six programs deliver patients' curricula, educating 4225 individuals per year. These programs' content varies and focuses on either specific diets or various culinary behaviors. All the programs' directors are health professionals who are also either credentialed chefs or have a strong culinary background. Nine of these programs offer culinary training in either a hands-on or visual demonstration within a teaching kitchen setting, while one delivers remote culinary tele-education. Seven programs track outcomes using various questionnaires and biometric data. There is currently no consensus about learning objectives, curricular domains, staffing, and facility requirements associated with CM, and there has been little research to explore its impact. A shared strategy is needed to collectively overcome these challenges.

  19. Health-related Culinary Education: A Summary of Representative Emerging Programs for Health Professionals and Patients

    Science.gov (United States)

    Phillips, Edward M.; Nordgren, Julia; La Puma, John; La Barba, Julie; Cucuzzella, Mark; Graham, Robert; Harlan, Timothy S.; Burg, Tracey; Eisenberg, David

    2016-01-01

    Background: Beneficial correlations are suggested between food preparation and home food preparation of healthy choices. Therefore, there is an emergence of culinary medicine (CM) programs directed at both patients and medical professionals which deliver education emphasizing skills such as shopping, food storage, and meal preparation. Objective: The goal of this article is to provide a description of emerging CM programs and to imagine how this field can mature. Methods: During April 2015, 10 CM programs were identified by surveying CM and lifestyle medicine leaders. Program directors completed a narrative describing their program's structure, curricula, educational design, modes of delivery, funding, and cost. Interviews were conducted in an effort to optimize data collection. Results: All 10 culinary programs deliver medical education curricula educating 2654 health professionals per year. Educational goals vary within the domains of (1) provider's self-behavior, (2) nutritional knowledge and (3) prescribing nutrition. Six programs deliver patients' curricula, educating 4225 individuals per year. These programs' content varies and focuses on either specific diets or various culinary behaviors. All the programs' directors are health professionals who are also either credentialed chefs or have a strong culinary background. Nine of these programs offer culinary training in either a hands-on or visual demonstration within a teaching kitchen setting, while one delivers remote culinary tele-education. Seven programs track outcomes using various questionnaires and biometric data. Conclusions: There is currently no consensus about learning objectives, curricular domains, staffing, and facility requirements associated with CM, and there has been little research to explore its impact. A shared strategy is needed to collectively overcome these challenges. PMID:26937315

  20. Directory of certificates of compliance for radioactive materials packages. Volume 3, revision 1. Summary report of NRC approved quality assurance programs for radioactive material packages

    International Nuclear Information System (INIS)

    1981-12-01

    The directory contains a Summary Report of NRC approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packaging, and index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory

  1. Summary and accomplishments of the ORNL program for nuclear piping design criteria

    International Nuclear Information System (INIS)

    Greenstreet, W.L.

    1975-11-01

    The ORNL Piping Program was defined and established to develop basic information on the structure behavior of nuclear power plant piping components and to prepare this information in forms suitable for use in design codes and standards. Charts are presented showing the percentage completion of the various program tasks

  2. U.S. Department of Energy photovoltaic energy program contract summary, fiscal year 1999

    Energy Technology Data Exchange (ETDEWEB)

    Surek, T.; Hansen, A.

    2000-02-17

    This report summarizes the in-house and subcontracted research and development (R and D) activities under the National Center for Photovoltaics (NCPV) and US Department of Energy (DOE) National Photovoltaics Program from October 1, 1998, through September 30, 1999 (FY 1999). The mission of the DOE National Photovoltaics Program is to make PV a significant part of the domestic economy as an industry and an energy resource. The two primary goals of the national program are to (1) maintain the US industry's world leadership in research and technology development and (2) help the US industry remain a major, profitable force in the world market. The NCPV is part of the National PV Program and provides leadership and support to the national program toward achieving its mission and goals.

  3. The Canadian National Calibration Reference Center for Bioassay and in-vivo Monitoring: A program summary

    International Nuclear Information System (INIS)

    Kramer, G.H.; Zamora, M.L.

    1994-01-01

    The Canadian National Calibration Reference Center for Bioassay and in-vivo Monitoring is part of the Radiation Protection Bureau, Department of Health. The Reference Center operates a variety of different intercomparison programs that are designed to confirm that workplace monitoring results are accurate and provide the necessary external verification required by the Canadian regulators. The programs administered by the Reference Center currently include urinalysis intercomparisons for tritium, natural uranium, and 14 C, and in-vivo programs for whole-body, thorax, and thyroid monitoring. The benefits of the intercomparison programs to the participants are discussed by example. Future programs that are planned include dual spiked urine sample which contain both tritium and 14 C and the in-vivo measurement of 99m Tc. 18 refs., 1 fig., 2 tabs

  4. Summaries of FY 1986 research in the Applied Plasma Physics Fusion Theory Program

    International Nuclear Information System (INIS)

    1987-12-01

    The Theory Program is charged with supporting the development of theories and models of plasmas for the fusion research effort. This work ranges from first-principles analysis of elementary plasma processes to empirical simulation of specific experiments. The Theory Program supports research by industrial contractors, US government laboratories, and universities. The university support also helps to fulfill the DOE mission of training scientists for the fusion program. The Theory Program is funded through the Fusion Theory Branch, Division of Applied Plasma Physics in the Office of Fusion Energy. The work is divided among 31 institutions, of which 19 are universities, five are industrial contractors, and seven are US government laboratories; see Table 1 for a complete list. The FY 1986 Theory Program budget was divided among theory types: toroidal, mirror, alternate concept, generic, and atomic. Device modeling is included among the other funding categories, and is not budgeted separately

  5. Summary results of an assessment of research projects in the National Photovoltaics Program

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The Office of Energy Research (OER) undertook an assessment of 115 research projects (listed in Appendix A) sponsored by the National Photovoltaics Program. The Program is located within the Office of Energy Efficiency and Renewable Energy (EE). This report summarizes the results of that review. The Office of Solar Energy Conversion is responsible for the management of the National Photovoltaics Program. This program focuses on assisting US industry in development of fundamental technology to bring advanced photovoltaic energy systems to commercial use. The purpose of the assessment was to determine the following: (1) the quality of research of individual projects; (2) the impact of these individual projects on the mission of the program; and (3) the priority of future research opportunities.

  6. U.S. Department of Energy photovoltaic energy program contract summary, fiscal year 1999

    International Nuclear Information System (INIS)

    Surek, T.; Hansen, A.

    2000-01-01

    This report summarizes the in-house and subcontracted research and development (R and D) activities under the National Center for Photovoltaics (NCPV) and US Department of Energy (DOE) National Photovoltaics Program from October 1, 1998, through September 30, 1999 (FY 1999). The mission of the DOE National Photovoltaics Program is to make PV a significant part of the domestic economy as an industry and an energy resource. The two primary goals of the national program are to (1) maintain the US industry's world leadership in research and technology development and (2) help the US industry remain a major, profitable force in the world market. The NCPV is part of the National PV Program and provides leadership and support to the national program toward achieving its mission and goals

  7. Gulf Coast geopressured-geothermal program summary report compilation. Volume 2-A: Resource description, program history, wells tested, university and company based research, site restoration

    Energy Technology Data Exchange (ETDEWEB)

    John, C.J.; Maciasz, G.; Harder, B.J.

    1998-06-01

    The US Department of Energy established a geopressured-geothermal energy program in the mid 1970`s as one response to America`s need to develop alternate energy resources in view of the increasing dependence on imported fossil fuel energy. This program continued for 17 years and approximately two hundred million dollars were expended for various types of research and well testing to thoroughly investigate this alternative energy source. This volume describes the following studies: Geopressured-geothermal resource description; Resource origin and sediment type; Gulf Coast resource extent; Resource estimates; Project history; Authorizing legislation; Program objectives; Perceived constraints; Program activities and structure; Well testing; Program management; Program cost summary; Funding history; Resource characterization; Wells of opportunity; Edna Delcambre No. 1 well; Edna Delcambre well recompletion; Fairfax Foster Sutter No. 2 well; Beulah Simon No. 2 well; P.E. Girouard No. 1 well; Prairie Canal No. 1 well; Crown Zellerbach No. 2 well; Alice C. Plantation No. 2 well; Tenneco Fee N No. 1 well; Pauline Kraft No. 1 well; Saldana well No. 2; G.M. Koelemay well No. 1; Willis Hulin No. 1 well; Investigations of other wells of opportunity; Clovis A. Kennedy No. 1 well; Watkins-Miller No. 1 well; Lucien J. Richard et al No. 1 well; and the C and K-Frank A. Godchaux, III, well No. 1.

  8. Identification of Fissionable Materials Using the Tagged Neutron Technique

    International Nuclear Information System (INIS)

    Keegan, R.P.; Hurley, J.P.; Tinsley, J.R.; Trainham, R.

    2009-01-01

    This summary describes experiments to detect and identify fissionable materials using the tagged neutron technique. The objective of this work is to enhance homeland security capability to find fissionable material that may be smuggled inside shipping boxes, containers, or vehicles. The technique distinguishes depleted uranium from lead, steel, and tungsten. Future work involves optimizing the technique to increase the count rate by many orders of magnitude and to build in the additional capability to image hidden fissionable materials. The tagged neutron approach is very different to other techniques based on neutron die-away or photo-fission. This work builds on the development of the Associated Particle Imaging (API) technique at the Special Technologies Laboratory (STL). Similar investigations have been performed by teams at the Oak Ridge National Laboratory (ORNL), the Khlopin Radium Institute in Russia, and by the EURITRACK collaboration in the European Union

  9. Fission product release mechanisms and groupings

    International Nuclear Information System (INIS)

    Iglesia, F.C.; Brito, A.C.; Liu, Y.

    1995-01-01

    During CANDU postulated accidents the reactor fuel is estimated to be exposed to a variety of conditions. These conditions are dynamic and, during the course of an accident, the fuel may experience a wide range of temperatures and conditions from highly oxidizing to mildly reducing environments. The exposure of the reactor fuel to these environments and temperatures may affect its stoichiometry and release performance. In this paper a review of the important fission product release mechanisms is presented, the results of three out-of-pile experimental programs are summarized, and fission product release groups, for both oxidizing and reducing conditions are proposed. (author)

  10. Fission product release mechanisms and groupings

    Energy Technology Data Exchange (ETDEWEB)

    Iglesia, F C; Brito, A C; Liu, Y [Ontario Hydro, Toronto, ON (Canada); and others

    1996-12-31

    During CANDU postulated accidents the reactor fuel is estimated to be exposed to a variety of conditions. These conditions are dynamic and, during the course of an accident, the fuel may experience a wide range of temperatures and conditions from highly oxidizing to mildly reducing environments. The exposure of the reactor fuel to these environments and temperatures may affect its stoichiometry and release performance. In this paper a review of the important fission product release mechanisms is presented, the results of three out-of-pile experimental programs are summarized, and fission product release groups, for both oxidizing and reducing conditions are proposed. (author) 92 refs., 6 tabs.

  11. Transmutation of fission products through accelerator

    International Nuclear Information System (INIS)

    Nakamura, H.; Tani, S.; Takahashi, T.; Yamamura, O.

    1995-01-01

    The transmutation of fission products through particle accelerators has been studied under the OMEGA program. The photonuclear reaction has also been investigated to be applied to transmuting long-lived fission products, such as Cesium and Strontium, which have difficulties on reaction with neutrons due to its so small cross section. It is applicable for the transmutation if the energy balance can be improved with a monochromatic gamma rays in the range of the Giant Dipole Resonance generated through an excellent high current electron linear accelerator. The feasibility studies are being conducted on the transmutation system using it through an electron accelerator. (authors)

  12. Chemistry of actinides and fission products

    International Nuclear Information System (INIS)

    Pruett, D.J.; Sherrow, S.A.; Toth, L.M.

    1988-01-01

    This task is concerned primarily with the fundamental chemistry of the actinide and fission product elements. Special efforts are made to develop research programs in collaboration with researchers at universities and in industry who have need of national laboratory facilities. Specific areas currently under investigation include: (1) spectroscopy and photochemistry of actinides in low-temperature matrices; (2) small-angle scattering studies of hydrous actinide and fission product polymers in aqueous and nonaqueous solvents; (3) kinetic and thermodynamic studies of complexation reactions in aqueous and nonaqueous solutions; and (4) the development of inorganic ion exchange materials for actinide and lanthanide separations. Recent results from work in these areas are summarized here

  13. Pilot program: NRC severe reactor accident incident response training manual. Overview and summary of major points

    International Nuclear Information System (INIS)

    McKenna, T.J.; Martin, J.A. Jr.; Giitter, J.G.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Watkins

    1987-02-01

    Overview and Summary of Major Points is the first in a series of volumes that collectively summarize the U.S. Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assessment. Other volumes in the series are: Volume 2-Severe Reactor Accident Overview; Volume 3- Response of Licensee and State and Local Officials; Volume 4-Public Protective Actions-Predetermined Criteria and Initial Actions; Volume 5 - U.S. Nuclear Regulatory Commission. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. The volumes have been organized into these training modules to accommodate the scheduling and duty needs of participating NRC staff. Each volume is accompanied by an appendix of slides that can be used to present this material

  14. Summary of Recent Results from NASA's Space Solar Power (SSP) Programs and the Current Capabilities of Microwave WPT Technology

    Science.gov (United States)

    McSpadden, James; Mankins, John C.; Howell, Joe T. (Technical Monitor)

    2002-01-01

    The concept of placing enormous solar power satellite (SPS) systems in space represents one of a handful of new technological options that might provide large-scale, environmentally clean base load power into terrestrial markets. In the US, the SPS concept was examined extensively during the late 1970s by the U.S. Department of Energy (DOE) and the National Aeronautics and Space Administration (NASA). More recently, the subject of space solar power (SSP) was reexamined by NASA from 1995-1997 in the "fresh look" study, and during 1998 in an SSP "concept definition study". As a result of these efforts, in 1999-2000, NASA undertook the SSP Exploratory Research and Technology (SERT) program which pursued preliminary strategic technology research and development to enable large, multi-megawatt SSP systems and wireless power transmission (WPT) for government missions and commercial markets (in-space and terrestrial). During 2001-2002, NASA has been pursuing an SSP Concept and Technology Maturation (SCTM) program follow-on to the SERT, with special emphasis on identifying new, high-leverage technologies that might advanced the feasibility of future SSP systems. In addition, in 2001, the U.S. National Research Council (NRC) released a major report providing the results of a peer review of NASA's SSP strategic research and technology (R&T) road maps. One of the key technologies needed to enable the future feasibility of SSP/SPS is that of wireless power transmission. Advances in phased array antennas and rectennas have provided the building blocks for a realizable WPT system. These key components include the dc-RF converters in the transmitter, the retrodirective beam control system, and the receiving rectenna. Each subject is briefly covered, and results from the SERT program that studied a 5.8 GHz SPS system are presented. This paper presents a summary results from NASA's SSP efforts, along with a summary of the status of microwave WPT technology development.

  15. U.S. Department of Energy, Illness and Injury Surveillance Program, Worker Health Summary, 1995-2004

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, Office of Health, Safety and Security, Office of Illness and Injury Prevention Programs

    2007-10-01

    The Department of Energy’s (DOE) Illness and Injury Surveillance Program has created an opportunity to assess illness and injury rates and patterns among workers at participating sites for well over a decade. The Worker Health Summary introduces an additional perspective on worker health with the introduction of analyses comparing the experience of sites in different program offices and a focus on time trends covering a decade of worker illness and injury experience. These analyses by program office suggest that illness and injury patterns among National Nuclear Security Administration (NNSA) workers diverge in many ways from those seen among Environmental Management (EM) and Science workers for reasons not yet understood. These differences will receive further investigation in future special focus studies, as will other findings of interest. With the time depth now available in our data, the Worker Health Summary reveals an additional nuance in worker health trends: changing health patterns in a specialized and skilled but aging work force. Older workers are becoming an increasing percentage of the work force, and their absence rates for diseases such as diabetes and hypertension are increasing as well. The impact of these emerging health issues, if properly addressed, can be managed to maintain or even enhance worker health and productivity. Prevention strategies designed to reduce the toll of these health conditions appear warranted, and this report gives us an indication of where to focus them. The analyses that follow reflect the Illness and Injury Surveillance Program’s continued commitment to apply a public health perspective in protecting the health of DOE’s work force.

  16. Comprehensive Technical Report, General Electric Direct-Air-Cycle Aircraft Nuclear Propulsion Program, Program Summary and References

    Energy Technology Data Exchange (ETDEWEB)

    Thornton, G.; Rothstein, A.J.

    1962-06-28

    This is one of twenty-one volumes sumarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume discusses the background to the General Electric program, and summarizes the various direct-air-cycle nuclear test assemblies and power plants that were developed. Because of the requirements of high performance, low weight, and small size, vast improvements in existing technology were required to meet the flight objectives. The technological progress achieved during the program is also summarized. The last appendix contains a compilation of the abstracts, tables of contents, and reference lists of the other twenty volumes.

  17. The evaluation for reference fission yield of 238U fission

    International Nuclear Information System (INIS)

    Liang Qichang; Liu Tingjin

    1998-01-01

    In the fission yield data evaluation and measurement, the reference yield is very important, good or poor recommended or measurement values depend upon the reference data to a great extent. According to the CRP's requirement, the evaluation of reference fission yields have been and will be carried out in CNDC, as a part of the whole work (contract No.9504/R 0 /Regular Budget Fund), the evaluation for 29 reference fission yields of 15 product nuclides from 238 U fission have been completed

  18. Report on Activities and Programs for Countering Proliferation and NBC Terrorism. Volume 1. Executive Summary

    National Research Council Canada - National Science Library

    2006-01-01

    This Report on Activities and Programs for Countering Proliferation and NBC Terrorism is submitted to the United States Congress as required by the 1994 National Defense Authorization Act (NDAA) (as amended...

  19. Deployment summary: Fiscal years 1995-2000 [USDOE Office of International Programs

    International Nuclear Information System (INIS)

    2000-01-01

    This publication summarizes the progress made by the Office of International Programs (IP) in deploying innovative technologies for the environmental remediation of the DOE complex and for sites of its international collaborators for fiscal years 1995 through 2000

  20. Second jet workshop on pellet injection: pellet fueling program in the United States. Summary

    International Nuclear Information System (INIS)

    Milora, S.L.

    1983-01-01

    S. Milora described the US programme on pellet injection. It has four parts: (1) a confinement experimental program; (2) pellet injector development; (3) theoretical support; and (4) tritium pellet study for TFTR

  1. Urban Maglev Technology Development Program : Colorado Maglev Project : part 1 : executive summary of final report

    Science.gov (United States)

    2004-06-01

    The overall objective of the urban maglev transit technology development program is to develop magnetic levitation technology that is a cost effective, reliable, and environmentally sound transit option for urban mass transportation in the United Sta...

  2. Civilian Power Program. Part 1, Summary, Current status of reactor concepts

    Energy Technology Data Exchange (ETDEWEB)

    Author, Not Given

    1959-09-01

    This study group covered the following: delineation of the specific objectives of the overall US AEC civilian power reactor program, technical objectives of each reactor concept, preparation of a chronological development program for each reactor concept, evaluation of the economic potential of each reactor type, a program to encourage the the development, and yardsticks for measuring the development. Results were used for policy review by AEC, program direction, authorization and appropriation requests, etc. This evaluation encompassed civilian power reactors rated at 25 MW(e) or larger and related experimental facilities and R&D. This Part I summarizes the significant results of the comprehensive effort to determine the current technical and economic status for each reactor concept; it is based on the 8 individual technical status reports (Part III).

  3. Deployment summary: Fiscal years 1995-2000 [USDOE Office of International Programs

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-07-01

    This publication summarizes the progress made by the Office of International Programs (IP) in deploying innovative technologies for the environmental remediation of the DOE complex and for sites of its international collaborators for fiscal years 1995 through 2000.

  4. Systematic evaluation program status summary report: November 1-30, 1981

    International Nuclear Information System (INIS)

    1981-12-01

    The Systematic Evaluation Program is intended to examine many safety related aspects of eleven of the older light water reactors. This document provides the existing status of the review process including individual topic and overall completion status

  5. Fission fragment angular momentum

    International Nuclear Information System (INIS)

    Frenne, D. De

    1991-01-01

    Most of the energy released in fission is converted into translational kinetic energy of the fragments. The remaining excitation energy will be distributed among neutrons and gammas. An important parameter characterizing the scission configuration is the primary angular momentum of the nascent fragments. Neutron emission is not expected to decrease the spin of the fragments by more than one unit of angular momentum and is as such of less importance in the determination of the initial fragment spins. Gamma emission is a suitable tool in studying initial fragment spins because the emission time, number, energy, and multipolarity of the gammas strongly depend on the value of the primary angular momentum. The main conclusions of experiments on gamma emission were that the initial angular momentum of the fragments is large compared to the ground state spin and oriented perpendicular to the fission axis. Most of the recent information concerning initial fragment spin distributions comes from the measurement of isomeric ratios for isomeric pairs produced in fission. Although in nearly every mass chain isomers are known, only a small number are suitable for initial fission fragment spin studies. Yield and half-life considerations strongly limit the number of candidates. This has the advantage that the behavior of a specific isomeric pair can be investigated for a number of fissioning systems at different excitation energies of the fragments and fissioning nuclei. Because most of the recent information on primary angular momenta comes from measurements of isomeric ratios, the global deexcitation process of the fragments and the calculation of the initial fragment spin distribution from measured isomeric ratios are discussed here. The most important results on primary angular momentum determinations are reviewed and some theoretical approaches are given. 45 refs., 7 figs., 2 tabs

  6. Program summary for the Office of Remedial Action and Waste Technology

    International Nuclear Information System (INIS)

    1989-10-01

    The US Department of Energy is the lead Federal agency responsible for planning and implementing the programs that ensure safe and efficient management of nuclear wastes from both civilian and defense activities. Within the Department, three offices share this responsibility: the Office of Remedial Action and Waste Technology, the Office of Civilian Radioactive Waste Management, and the Office of Defense Waste and Transportation Management. This document summarizes the programs managed by the Office of Remedial Action and Waste Technology

  7. Advanced Industrial Materials (AIM) Program: Compilation of project summaries and significant accomplishments, FY 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    In many ways, the Advanced Industrial Materials (AIM) Program underwent a major transformation in Fiscal Year 1995 and these changes have continued to the present. When the Program was established in 1990 as the Advanced Industrial Concepts (AIC) Materials Program, the mission was to conduct applied research and development to bring materials and processing technologies from the knowledge derived from basic research to the maturity required for the end use sectors for commercialization. In 1995, the Office of Industrial Technologies (OIT) made radical changes in structure and procedures. All technology development was directed toward the seven ``Vision Industries`` that use about 80% of industrial energy and generated about 90% of industrial wastes. The mission of AIM has, therefore, changed to ``Support development and commercialization of new or improved materials to improve productivity, product quality, and energy efficiency in the major process industries.`` Though AIM remains essentially a National Laboratory Program, it is essential that each project have industrial partners, including suppliers to, and customers of, the seven industries. Now, well into FY 1996, the transition is nearly complete and the AIM Program remains reasonably healthy and productive, thanks to the superb investigators and Laboratory Program Managers. This report contains the technical details of some very remarkable work by the best materials scientists and engineers in the world. Subject areas covered are: advanced metals and composites; advanced ceramics and composites; polymers and biobased materials; and new materials and processes.

  8. Summary of entire research achievements of creative engineering research program on nuclear fuel cycle

    International Nuclear Information System (INIS)

    Takenaka, Shingo; Ikegami, Tetsuo

    2008-03-01

    Creative Engineering Research Program on Nuclear Fuel Cycle (former In-house Innovative Research Encouraging Program) was implemented from FY 2001 to FY 2007 in order to support such in-house researches that create innovative new concepts and aim technical break-through. Totally 37 applications have been received and 14 research themes have been accepted and been performed in this program. As for the research achievements of the 14 research themes, first author papers accepted by scientific journals and by science councils were 47 and 32, respectively, and oral presentations at scientific societies were 99. Furthermore, interpretive articles for scientific journals, requested lectures, patents, and prize winnings were 13, 30, 8, and 3, respectively. Consequently, it can be evaluated that the research achievements resulted from this program are generally in high level and that the expectations, at the starting point of this program, to activate the innovative research activities have been accomplished. In this report, the final reports of the 14 research themes together with the outline of this program are included. (author)

  9. Fission product detection

    International Nuclear Information System (INIS)

    Liatard, E.; Akrouf, S.; Bruandet, J.F

    1987-01-01

    The response of photovoltaic cells to heavy ions and fission products have been tested on beam. Their main advantages are their extremely low price, their low sensitivity to energetic light ions with respect to fission products, and the possibility to cut and fit them together to any shape without dead zone. The time output signals of a charge sensitive preamplifier connected to these cells allows fast coincidences. A resolution of 12ns (F.W.H.M.) have been measured between two cells [fr

  10. Low energy nuclear fission

    International Nuclear Information System (INIS)

    Nifenecker, H.

    1982-02-01

    In these lectures we present the liquid drop model of fission and compare some of its prediction with experiment. The liquid drop analogy allows to define in a rather simple and intuitive way a number of useful concepts and possible observables. We then discuss, using the example of the oscillator model, the generality of shell effects. We show how a synthesis of the liquid drop model and of the shell model can be made using the Strutinsky shell averaging procedure. Some experimental data related to the existence of shape isomers are presented and discussed. We conclude by discussing some aspects, both experimental and theoretical, of fission dynamics

  11. Fission of heavy hypernuclei

    International Nuclear Information System (INIS)

    Nifenecker, H.

    1993-01-01

    The results on delayed and prompt fission of heavy hypernuclei obtained by the LEAR PS177 collaboration are recalled and discussed. It is shown that the hypernuclei life-times can be explained in term of a weak strangeness violating lambda-nucleon interaction with a cross section close to 6.0 10 -15 barns. The lambda attachment function is shown to be sensitive to the scission configuration, just before fission, and to the neck dynamics. This function provides a new way to study the nuclear scission process. (author)

  12. Fission gas measuring technology

    International Nuclear Information System (INIS)

    Lee, Hyung Kwon; Kim, Eun Ka; Hwang, Yong Hwa; Lee, Eun Pyo; Chun, Yong Bum; Seo, Ki Seog; Park, Dea Gyu; Chu, Yong Sun; Ahn, Sang Bok.

    1998-02-01

    Safety and economy of nuclear plant are greatly affected by the integrity of nuclear fuels during irradiation reactor core. A series of post-irradiation examination (PIE) including non-destructive and destructive test is to be conducted to evaluate and characterize the nuclear performance. In this report, a principle of the examination equipment to measure and analyse fission gases existing nuclear fuels were described and features of the component and device consisting the fission gas measuring equipment are investigated. (author). 4 refs., 2 tabs., 6 figs

  13. Fission gas measuring technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyung Kwon; Kim, Eun Ka; Hwang, Yong Hwa; Lee, Eun Pyo; Chun, Yong Bum; Seo, Ki Seog; Park, Dea Gyu; Chu, Yong Sun; Ahn, Sang Bok

    1998-02-01

    Safety and economy of nuclear plant are greatly affected by the integrity of nuclear fuels during irradiation reactor core. A series of post-irradiation examination (PIE) including non-destructive and destructive test is to be conducted to evaluate and characterize the nuclear performance. In this report, a principle of the examination equipment to measure and analyse fission gases existing nuclear fuels were described and features of the component and device consisting the fission gas measuring equipment are investigated. (author). 4 refs., 2 tabs., 6 figs.

  14. Fission modelling with FIFRELIN

    International Nuclear Information System (INIS)

    Litaize, Olivier; Serot, Olivier; Berge, Leonie

    2015-01-01

    The nuclear fission process gives rise to the formation of fission fragments and emission of particles (n,γ, e - ). The particle emission from fragments can be prompt and delayed. We present here the methods used in the FIFRELIN code, which simulates the prompt component of the de-excitation process. The methods are based on phenomenological models associated with macroscopic and/or microscopic ingredients. Input data can be provided by experiment as well as by theory. The fission fragment de-excitation can be performed within Weisskopf (uncoupled neutron and gamma emission) or a Hauser-Feshbach (coupled neutron/gamma emission) statistical theory. We usually consider five free parameters that cannot be provided by theory or experiments in order to describe the initial distributions required by the code. In a first step this set of parameters is chosen to reproduce a very limited set of target observables. In a second step we can increase the statistics to predict all other fission observables such as prompt neutron, gamma and conversion electron spectra but also their distributions as a function of any kind of parameters such as, for instance, the neutron, gamma and electron number distributions, the average prompt neutron multiplicity as a function of fission fragment mass, charge or kinetic energy, and so on. Several results related to different fissioning systems are presented in this work. The goal in the next decade will be i) to replace some macroscopic ingredients or phenomenological models by microscopic calculations when available and reliable, ii) to be a support for experimentalists in the design of detection systems or in the prediction of necessary beam time or count rates with associated statistics when measuring fragments and emitted particle in coincidence iii) extend the model to be able to run a calculation when no experimental input data are available, iv) account for multiple chance fission and gamma emission before fission, v) account for the

  15. Low energy nuclear fission

    International Nuclear Information System (INIS)

    Nifenecker, H.

    1980-08-01

    In these lectures the liquid drop model of fission is presented and some of its predictions compared with experiment. The liquid drop analogy allows to define in a rather simple and intuitive way a number of useful concepts and possible observables. It is shown how a synthesis of the liquid drop model and of the shell model can be made using the Strutinsky shell averaging procedure. Some experimental data related to the existence of shape isomers are presented and discussed. We conclude by discussing some aspects, both experimental and theoretical, of fission dynamics

  16. Directory of Certificates of Compliance for Radioactive-Materials Packages. Summary report of NRC approved quality assurance programs for radioactive material packages

    International Nuclear Information System (INIS)

    1983-01-01

    This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective December 31, 1982. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

  17. Fission Product Library and Resource

    Energy Technology Data Exchange (ETDEWEB)

    Burke, J. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Padgett, S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-09-29

    Fission product yields can be extracted from an irradiated sample by performing gamma ray spectroscopy on the whole sample post irradiation. There are several pitfalls to avoid when trying to determine a specific isotope's fission product yield.

  18. Spontaneous fission of superheavy nuclei

    Indian Academy of Sciences (India)

    The fission-like configurations are used for the total deformation energy calculations. A ... oscillator potential for the two fission fragment regions reads as ... Beyond this limit, the contribution of more remote levels is negligible. Once the density ...

  19. NASA Ames summary high school apprenticeship research program, 1983 research papers

    Science.gov (United States)

    Powell, P.

    1984-01-01

    Engineering enrollments are rising in universities; however, the graduate engineer shortage continues. Particularly, women and minorities will be underrepresented for years to come. As one means of solving this shortage, Federal agencies facing future scientific and technological challenges were asked to participate in the Summer High School Apprenticeship Research Program (SHARP). This program was created 4 years ago to provide an engineering experience for gifted female and minority high school students at an age when they could still make career and education decisions. The SHARP Program is designed for high school juniors (women and minorities) who are U.S. citizens, are 16 years old, and who have unusually high promise in mathematics and science through outstanding academic performance in high school. Students who are accepted into this summer program will earn as they learn by working 8 hours a day in a 5-day work week. This work-study program features weekly field trips, lectures and written reports, and job experience related to the student's career interests.

  20. Battelle integrity of nuclear piping program. Summary of results and implications for codes/standards

    International Nuclear Information System (INIS)

    Miura, Naoki

    2005-01-01

    The BINP(Battelle Integrity of Nuclear Piping) program was proposed by Battelle to elaborate pipe fracture evaluation methods and to improve LBB and in-service flaw evaluation criteria. The program has been conducted from October 1998 to September 2003. In Japan, CRIEPI participated in the program on behalf of electric utilities and fabricators to catch up the technical backgrounds for possible future revision of LBB and in-service flaw evaluation standards and to investigate the issues needed to be reflected to current domestic standards. A series of the results obtained from the program has been well utilized for the new LBB Regulatory Guide Program by USNRC and for proposal of revised in-service flaw evaluation criteria to the ASME Code Committee. The results were assessed whether they had implications for the existing or future domestic standards. As a result, the impact of many of these issues, which were concerned to be adversely affected to LBB approval or allowable flaw sizes in flaw evaluation criteria, was found to be relatively minor under actual plant conditions. At the same time, some issues that needed to be resolved to address advanced and rational standards in the future were specified. (author)

  1. Summary reports of activities under visiting research program in Research Reactor Institute, Kyoto University, in first half of 1984

    International Nuclear Information System (INIS)

    1984-01-01

    The technical reports of KURRI are published at any time summarizing in the form of interim report the data required for research and experiment, such as the results of various functional tests of experimental devices, the test results of the things made for trial, the state of radiation control and waste treatment and the reports of study meetings, or the remarkable results obtained during research, new techniques, the discussion on other papers and reports and so on. In this report, the summaries of 90 researches carried out under the visiting research program in the first half of 1984 are collected. The subject number, title, reporters and the gist of each research are reported. (Kako, I.)

  2. Process for treating fission waste

    International Nuclear Information System (INIS)

    Rohrmann, C.A.; Wick, O.J.

    1983-01-01

    A method is described for the treatment of fission waste. A glass forming agent, a metal oxide, and a reducing agent are mixed with the fission waste and the mixture is heated. After melting, the mixture separates into a glass phase and a metal phase. The glass phase may be used to safely store the fission waste, while the metal phase contains noble metals recovered from the fission waste

  3. Summary of non-US national and international radioactive waste management programs 1981

    International Nuclear Information System (INIS)

    Harmon, K.M.; Kelman, J.A.

    1981-06-01

    Many nations and international agencies are working to develop improved technology and industrial capability for neuclear fuel cycle and waste management operations. The effort in some countries is limited to research in university laboratories on treating low-level waste from reactor plant operations. In other countries, national nuclear research institutes are engaged in major programs in all phases of the fuel cycle and waste management, and there is a national effort to commercialize fuel cycle operations. Since late 1976, staff members of Pacific Northwest Laboratory have been working under US Department of Energy sponsorship to assemble and consolidate openly available information on foreign and international nuclear waste management programs and technology. This report summarizes the information collected on the status of fuel cycle and waste management programs in selected countries making major efforts in these fields as of the end of May 1981

  4. Summary of non-US national and international radioactive waste management programs 1980

    International Nuclear Information System (INIS)

    Harmon, K.M.; Kelman, J.A.; Stout, L.A.; Hsieh, K.A.

    1980-03-01

    Many nations and international agencies are working to develop improved technology and industrial capability for nuclear fuel cycle and waste management operations. The effort in some countries is limited to research in university laboratories on treating low-level waste from reactor plant operations. In other countries, national nuclear research institutes are engaged in major programs in all phases of the fuel cycle and waste management, and there is a national effort to commercialize fuel cycle operations. Since late 1976, staff members of Pacific Northwest Laboratory have been working under US Department of Energy sponsorship to assemble and consolidate openly available information on foreign and international nuclear waste management programs and technology. This report summarizes the information collected on the status of fuel cycle and waste management programs in selected countries making major efforts in these fields as of the end of January 1980

  5. Summary of the Mol electrolysis cell test program in the CRL tritium laboratory

    International Nuclear Information System (INIS)

    Miller, J.M.; Keyes, R.J.

    1996-01-01

    The development of electrolysis technology for highly tritiated water at the Studiecentrum voor Kernenergie/Centre d'Etude de l'Energie Nucleaire (SCK/CEN), Mol, Belgium, focused on A Low Inventory Capillary Electrolyser (ALICE). The key characteristic of ALICE is its low liquid inventory, a key feature for the radio-toxicity of tritiated water. A program to test this electrolytic cell design with highly tritiated water in the Chalk River Tritium Laboratory was initiated in 1988 and extended through to early 1995. The activities conducted at CRL and associated with the experimental program-design, installation, licensing and commissioning activities- are described in this report along with the results of the test program conducted on the experimental system with non-tritiated heavy water. The installation in the CRL Tritium Laboratory consisted of three main sections: the electrolysis section, the tritium storage and supply section, and the recombination section. 16 figs., 2 tabs., 10 refs

  6. 2D/3D Program work summary report, [January 1988--December 1992

    International Nuclear Information System (INIS)

    Damerell, P.S.; Simons, J.W.

    1993-06-01

    The 2D/3D Program was carried out by Germany, Japan and the United States to investigate the thermal-hydraulics of a PWR large-break LOCA. A contributory approach was utilized in which each country contributed significant effort to the program and all three countries shared the research results. Germany constructed and operated the Upper Plenum Test Facility (UPTF), and Japan constructed and operated the Cylindrical Core Test Facility (CCTF) and the Slab Core Test Facility (SCTF). The US contribution consisted of provision of advanced instrumentation to each of the three test facilities, and assessment of the TRAC computer code against the test results. Evaluations of the test results were carried out in all three countries. This report summarizes the 2D/3D Program in terms of the contributing efforts of the participants

  7. Waste Treatment Plant Support Program: Summaries of Reports Produced During Fiscal Years 1999-2010

    Energy Technology Data Exchange (ETDEWEB)

    Beeman, Gordon H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2010-08-01

    The Waste Treatment Plant (WTP) being built on the U.S. Department of Energy (DOE) Hanford Site will be the largest chemical processing plant in the United States. Bechtel National Inc. (BNI) is the designer and constructor for the WTP. The Pacific Northwest National Laboratory (PNNL) has provided significant research and testing support to the WTP. This report provides a summary of reports developed initially under PNNL’s “1831” use agreement and later PNNL’s “1830” prime contract with DOE in support of the WTP. In March 2001, PNNL under its “1831” use agreement entered into a contract with BNI to support their research and testing activities. However, PNNL support to the WTP predates BNI involvement. Prior to March 2001, PNNL supported British Nuclear Fuels Ltd. in its role as overall designer and constructor. In February 2007, execution of PNNL’s support to the WTP was moved under its “1830” prime contract with DOE.

  8. Fiscal year 1996 well installation program summary, Y-12 Plant Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-04-01

    This report summarizes the well installation activities conducted during the federal fiscal year (FY) 1996 drilling program at the Oak Ridge Y-12 Plant, Oak Ridge Tennessee. Synopses of monitoring well construction/well development data, well location rationale, geological/hydrological observations, quality assurance/quality control methods, and health and safety monitoring are included. Two groundwater monitoring wells were installed during the FY 1996 drilling program. One of the groundwater monitoring wells was installed in the Lake Reality area and was of polyvinyl chloride screened construction. The other well, installed near the Ash Disposal Basin, was of stainless steel construction

  9. Summary of the performance of strand produced for the 1990 SSC dipole program

    International Nuclear Information System (INIS)

    Christopherson, D.; Capone, D. II; Seuntjens, J.; Pollock, D.; Hannaford, C.R.

    1991-01-01

    In 1990 and at the beginning of 1991, more than 4 million feet of wire was delivered to support the SSC Dipole Program. This wire was fabricated to meet specification SSC-MAG-M-4141, and test results and various statistics are compiled here. Certain strengths and weaknesses in the performance of the delivered strand are discussed, including analysis of strand breakage in certain billets. Test results of cable manufactured for 40 mm dipole magnets and 50 mm dipole magnets are reported, and a brief overview of the 1991-1992 Conductor Program is included

  10. Summary of the performance of strand produced for the 1990 SSC Dipole Program

    International Nuclear Information System (INIS)

    Christopherson, D.; Capone, D.; Seuntjens, J.; Pollock, D.; Hannaford, C.R.

    1991-03-01

    In 1990 and at the beginning of 1991, more than 4 million feet of wire was delivered to support the SSC Dipole Program. This wire was fabricated to meet specification SSC-MAG-M-4141, and test results and various statistics are compiled here. Certain strengths and weaknesses in the performance of the delivered strand are discussed, including analysis of strand breakage in certain billets. Test results of cable manufactured for 40 mm dipole magnets and 50 mm dipole magnets are reported, and a brief overview of the 1991--1992 Conductor Program is included. 4 refs., 5 figs., 4 tabs

  11. Summary report of the state surveillance program on the transportation of radioactive materials

    International Nuclear Information System (INIS)

    1977-11-01

    From 1973 to 1976, a surveillance program was conducted in New Jersey, Oregon, Missouri, New York, Illinois, Texas, Louisiana, South Carolina, Minnesota, and New York City to provide training support for State radiation personnel and to determine actual radiation exposure conditions and radioactive material package handling practices through the terminals of air carriers and freight forwarders. NRC and DOT along with the participating States, developed the surveillance program. In general, the results did not indicate a public health or safety problem due to the transportation of radioactive materials. Some employees of several freight forwarders, are, however, receiving annual exposures in excess of 500 mrem. Recommendations are given

  12. The Teachers Academy for Mathematics and Science. Executive summary and program activities update

    Energy Technology Data Exchange (ETDEWEB)

    1992-09-01

    In his State of the Union address on January 31, 1990, President Bush set a goal for US students to be number one in the world in mathematics and science achievement by the year 2000. The Teachers Academy for Mathematics and Science in Chicago is an experiment of unprecedented boldness and scale that can provide a means to the President`s goal, both for the Chicago area and as a national model. This document covers organization and governance, program activities, future training goals, and evaluation programs.

  13. The U.S. Department of Energy Office of Indian Energy Policy and Programs Las Vegas, Nevada, Roundtable Summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    2011-03-16

    LAS VEGAS EXECUTIVE SUMMARY The Las Vegas, Nevada DOE Tribal Roundtable convened on March 16th, at the Las Vegas Hilton. The meeting was hosted by the Department of Energy (DOE) Office of Indian Policy and Programs (DOE Office of Indian Energy) and facilitated by JR Bluehouse, Program Manager, Udall Foundation’s U.S. Institute for Environmental Conflict Resolution (U.S. Institute). Mr. Bluehouse was assisted by Tamara, Underwood, Program Assistant, U.S. Institute.  Tribal leaders and representatives from multiple tribal governments and communities attended the roundtable. Tracey LeBeau, newly appointed Director of the Office of Indian Energy attended.    LaMont Jackson from DOE’s Office of Electricity attended. Also attending from the administration and federal agencies were Kim Teehee, Senior Policy Advisor for Native American Affairs, The White House; Charlie Galbraith, Associate Director of the Office of Public Engagement and Deputy Associate Director of the Office of Intergovernmental Affairs, The White House; Jodi Gillette, Deputy Assistant Secretary for Policy and Economic Development, the Bureau of Indian Affairs.

  14. 50 years of nuclear fission

    International Nuclear Information System (INIS)

    Hilscher, D.

    1989-01-01

    The article tells the story of the discovery of nuclear fission in Berlin 50 years ago by Otto Hahn and Fritz Strassmann in cooperation with Lise Meitner. 50 years later nuclear fission is still a subject of research. Some question remain unanswered. Selected new research results are used to discuss the dynamics of the collective movement of the elementary nuclear fission process. (orig.) [de

  15. Fission dynamics of hot nuclei

    Indian Academy of Sciences (India)

    2014-04-05

    Apr 5, 2014 ... across the fission barrier is very small or in other words, the fission barrier is much ... of this shape evolution, the gross features of the fissioning nucleus can be described ..... [7] Y Abe, C Gregoire and H Delagrange, J. Phys.

  16. National Waste Terminal Storage Program Information Management Plan. Volume I. Management summary

    International Nuclear Information System (INIS)

    1977-05-01

    A comprehensive information management plan is needed for the processing of the large amount of documentation that will accumulate in the National Waste Terminal Storage program over the next decade. The plan will apply to all documentation from OWI contractors, subcontractors, and suppliers, and to external documentation from OWI organizations

  17. 1976 Inter-university symposium on renewable resource assessment and programming: executive summary

    Science.gov (United States)

    Billy G. Pemberton

    1977-01-01

    The Forest and Rangeland Renewable Resources Planning Act of 1974 directs the Secretary of Agriculture to prepare an assessment of the nation's renewable resources and a program that will assure an adequate future supply of these resources. Responsibility for this work is assigned to the Forest Service. An inter-university symposium was held in 1976 to evaluate...

  18. Gender Differences in Major Federal External Grant Programs. Technical Report Summary

    Science.gov (United States)

    Hosek, Susan D.; Cox, Amy G.; Ghosh-Dastidar, Bonnie; Kofner, Aaron; Rampal, Nishal; Scott, Jon; Berry, Sandra H.

    2005-01-01

    The Wyden amendment to the National Science Foundation (NSF) Authorization Act of 2002 sought to determine whether federally funded educational programs other than sports comply with Title IX, which prohibits gender discrimination. At the request of NSF, this report analyzes administrative data from fiscal years 2001 through 2003 describing the…

  19. Summary Report on NRL Participation in the Microwave Landing System Program.

    Science.gov (United States)

    1980-08-19

    shifters were measured and statistically analyzed. Several research contracts for promising phased array techniques were awarded to industrial contractors...program was written for compiling statistical data on the measurements, which reads out inser- sertion phase characteristics and standard deviation...GLOSSARY OF TERMS ALPA Airline Pilots’ Association ATA Air Transport Association AWA Australiasian Wireless Amalgamated AWOP All-weather Operations

  20. Professional Preparation in School Psychology: A Summary of Information from Programs in Seven Countries

    Science.gov (United States)

    Oakland, Thomas; Hatzichristou, Chryse

    2014-01-01

    This article summarizes prominent themes found in descriptions of school psychology programs in Estonia (Kikas, 2014), Greece (Hatzichristou & Polychroni, 2014), Hong Kong (Lam, 2014), Romania (Negovan & Dinca, 2014), Sweden (Schad, 2014), United Kingdom (Wood, 2014), and United States (Joyce & Rossen, 2014). This paper summarizes…

  1. National waste terminal storage program: configuration management plan. Volume I. Management summary

    International Nuclear Information System (INIS)

    1977-05-01

    Objective of the Configuration Management Plan is to describe the Office of Waste Isolation's approach for the systematic identification, change control, status accounting, and auditing of: documents defining the NWTS Program and the plans for attaining the defined objectives; physical and functional characteristics of each storage site, facility, systems and equipment; and associated costs and schedules

  2. An Implementation Study of the "Art in Action Program". Executive Summary

    Science.gov (United States)

    Biag, Manuelito; Raab, Erin; Hofstedt, Mary

    2015-01-01

    Targeting students in grades K-8, Art in Action's program consists of 12 age-appropriate lessons per year led by parent and teacher volunteers. The curriculum is based on historically significant artists and their works of art. Through semi-structured discussions, students examine a variety of masterpieces, learning about the artist as well as…

  3. Manufacturing Educational Change: Impact Evaluation of the Lansing Area Manufacturing Partnership Pilot Program. Executive Summary.

    Science.gov (United States)

    MacAllum, Keith; Taylor, Susan Hubbard; Johnson, Amy Bell

    The Lansing Area Manufacturing Partnership (LAMP) is an academically rigorous, business/labor-driven school-to-career program in Lansing, Michigan, that includes business, union, school, and parent partners and provides participating students with work-based learning experiences for 2.5 hours every day throughout their senior year. LAMP's…

  4. The discovery of fission

    International Nuclear Information System (INIS)

    McKay, H.A.C.

    1978-01-01

    In this article by the retired head of the Separation Processes Group of the Chemistry Division, Atomic Energy Research Establishment, Harwell, U.K., the author recalls what he terms 'an exciting drama, the unravelling of the nature of the atomic nucleus' in the years before the Second World War, including the discovery of fission. 12 references. (author)

  5. Summary and abstracts: Applied Research Units and Projects 1996 UCETF Program

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-21

    The Urban Consortium (UC), created by PTI, is a network of jurisdictions with populations of over 250,000. The UC provides a platform for research and enterprise through its Energy, Environmental, Transportation, and Telecommunications and Information Task Forces. The UC provides a unique creative forum where elected and appointed officials and technical managers identify, test, and validate practical ways to improve the provision of public services and, where possible, generate new revenue opportunities. Public Technology, Inc., is the non-profit technology organization of the National League of Cities, the National Association of Counties, and the International City/County Management Association. PTI creates and advances technology-based products, services, and enterprises in cities and counties nationwide. Staffed by PTI, the UC addresses the critical needs of local governments through its Task Forces. The Urban Consortium Energy Task Force (UCETF) program has, since its inception, acted as a laboratory to develop, test solutions and share the resulting products or management approaches with the wider audience of local governments. It has addressed the overlap between energy and environment and economic development policy issues, and, is the nation's most extensive cooperative local government program to improve energy management and decision-making through applied research and technology cooperation. Proposals to meet the specific objectives of the UCETF annual R and D program are solicited from major urban jurisdictions. Projects based on these proposals are then selected by the UCETF for direct conduct and management by staff of city and county governments. Projects selected for each year's program are organized in thematic units to assure effective management and ongoing peer-to-peer experience exchange, with results documented at the end of each program year.

  6. Summary of Ontario Hydro's 1990-91 zebra mussel research program

    International Nuclear Information System (INIS)

    Claudi, R.; Wiancko, P.M.

    1992-01-01

    Ontario Hydro is the principal supplier of electricity to the Province of Ontario. It serves 3.6 million customers, with an inservice capacity of 28,200 MW. Ontario Hydro has seven fossil, five nuclear, and four hydraulic stations in the Great Lakes Basin and surrounding watershed. In addition, there are another 60 inland hydraulic stations and numerous dams. As the largest single user of raw water from the Great Lakes Basin, Ontario Hydro recognized the need to control zebra mussels early in 1989. At that time, very little was known in North America about the zebra mussel life cycle and potential impact. European utilities were consulted, but as we now know, zebra mussels are not perceived to be a problem in Europe at this time. To satisfy the immediate need for control, chlorination was identified as the most effective interim measure to prevent the fouling of systems which draw water from the aquatic environment. Due to the current regulatory environment, this solution is considered short term and Ontario Hydro was compelled to initiate a comprehensive research effort aimed at providing alternative methods of control. Most of the research effort during 1990, was methods of control. Most of the research effort during 1990, was directed towards this goal. Many alternative control measures, both chemical and nonchemical were considered. Also considered were the potential effects of the control measures and zebra mussels on station operations. A multidisciplinary team involving aquatic biologists, chemists, corrosion specialists, and civil and mechanical engineers from the various departments of Ontario Hydro was asked to address the problem. Some of the research also involved collaborative studies with universities, US utilities, American Water Works Association, and Canadian industries. Following is a summary of the research effort in 1990, and a preview of the research underway in 1991

  7. Waste Treatment Plant Support Program: Summaries of Reports Produced During Fiscal Years 1999-2010

    International Nuclear Information System (INIS)

    Beeman, Gordon H.

    2010-01-01

    The Waste Treatment Plant (WTP) being built on the U.S. Department of Energy (DOE) Hanford Site will be the largest chemical processing plant in the United States. Bechtel National Inc. (BNI) is the designer and constructor for the WTP. The Pacific Northwest National Laboratory (PNNL) has provided significant research and testing support to the WTP. This report provides a summary of reports developed initially under PNNL's '1831' use agreement and later PNNL's '1830' prime contract with DOE in support of the WTP. In March 2001, PNNL under its '1831' use agreement entered into a contract with BNI to support their research and testing activities. However, PNNL support to the WTP predates BNI involvement. Prior to March 2001, PNNL supported British Nuclear Fuels Ltd. in its role as overall designer and constructor. In February 2007, execution of PNNL's support to the WTP was moved under its '1830' prime contract with DOE. Documents numbered 'PNWD-XXXX' were issued under PNNL's '1831' use agreement. Documents numbered 'PNNL-XXXX' were issued under PNNL's '1830' prime contract with DOE. The documents are sorted by fiscal year and categorized as follows: (1) Characterization; (2) HLW (High Level Waste); (3) Material Characterization; (4) Pretreatment; (5) Simulant Development; (6) Vitrification; and (7) Waste Form Qualification. This report is intended to provide a compendium of reports issued by PNWD/PNNL in support of the Waste Treatment Plant. Copies of all reports can be obtained by clicking on http://www.pnl.gov/rpp-wtp/ and downloading the .pdf file(s) to your computer.

  8. Fission neutron spectra measurements at LANSCE - status and plans

    International Nuclear Information System (INIS)

    Haight, Robert C.; Noda, Shusaku; Nelson, Ronald O.; O' Donnell, John M.; Devlin, Matt; Chatillon, Audrey; Granier, Thierry; Taieb, Julien; Laurent, Benoit; Belier, Gilbert; Becker, John A.; Wu, Ching-Yen

    2009-01-01

    A program to measure fission neutron spectra from neutron-induced fission of actinides is underway at the Los Alamos Neutron Science Center (LANSCE) in a collaboration among the CEA laboratory at Bruyeres-le-Chatel, Lawrence Livermore National Laboratory and Los Alamos National Laboratory. The spallation source of fast neutrons at LANSCE is used to provide incident neutron energies from less than 1 MeV to 100 MeV or higher. The fission events take place in a gas-ionization fission chamber, and the time of flight from the neutron source to that chamber gives the energy of the incident neutron. Outgoing neutrons are detected by an array of organic liquid scintillator neutron detectors, and their energies are deduced from the time of flight from the fission chamber to the neutron detector. Measurements have been made of the fission neutrons from fission of 235 U, 238 U, 237 Np and 239 Pu. The range of outgoing energies measured so far is from 1 MeV to approximately 8 MeV. These partial spectra and average fission neutron energies are compared with evaluated data and with models of fission neutron emission. Results to date will be presented and a discussion of uncertainties will be given in this presentation. Future plans are to make significant improvements in the fission chambers, neutron detectors, signal processing, data acquisition and the experimental environment to provide high fidelity data including mea urements of fission neutrons below 1 MeV and improvements in the data above 8 MeV.

  9. Louisiana Barrier Island Comprehensive Monitoring (BICM) Program Summary Report: Data and Analyses 2006 through 2010

    Science.gov (United States)

    Kindinger, Jack G.; Buster, Noreen A.; Flocks, James G.; Bernier, Julie C.; Kulp, Mark A.

    2013-01-01

    The Barrier Island Comprehensive Monitoring (BICM) program was implemented under the Louisiana Coastal Area Science and Technology (LCA S&T) office as a component of the System Wide Assessment and Monitoring (SWAMP) program. The BICM project was developed by the State of Louisiana (Coastal Protection Restoration Authority [CPRA], formerly Department of Natural Resources [DNR]) to complement other Louisiana coastal monitoring programs such as the Coastwide Reference Monitoring System-Wetlands (CRMS-Wetlands) and was a collaborative research effort by CPRA, University of New Orleans (UNO), and the U.S. Geological Survey (USGS). The goal of the BICM program was to provide long-term data on the barrier islands of Louisiana that could be used to plan, design, evaluate, and maintain current and future barrier-island restoration projects. The BICM program used both historical and newly acquired (2006 to 2010) data to assess and monitor changes in the aerial and subaqueous extent of islands, habitat types, sediment texture and geotechnical properties, environmental processes, and vegetation composition. BICM datasets included aerial still and video photography (multiple time series) for shoreline positions, habitat mapping, and land loss; light detection and ranging (lidar) surveys for topographic elevations; single-beam and swath bathymetry; and sediment grab samples. Products produced using BICM data and analyses included (but were not limited to) storm-impact assessments, rate of shoreline and bathymetric change, shoreline-erosion and accretion maps, high-resolution elevation maps, coastal-shoreline and barrier-island habitat-classification maps, and coastal surficial-sediment characterization maps. Discussions in this report summarize the extensive data-collection efforts and present brief interpretive analyses for four coastal Louisiana geographic regions. In addition, several coastal-wide and topical themes were selected that integrate the data and analyses within a

  10. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume 1. Program summary

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. This introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings and recommendations. Each of Volumes II-VII reports on an individual assessment (Volume II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP.

  11. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume 1. Program summary

    International Nuclear Information System (INIS)

    1979-12-01

    This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. This introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings and recommendations. Each of Volumes II-VII reports on an individual assessment (Volume II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP

  12. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume I. Program summary

    International Nuclear Information System (INIS)

    1980-06-01

    This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. The introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings, and recommendations. Each of Volumes II-VII reports on an individual assessment (Volumn II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP

  13. Summary of inspection findings of licensee inservice testing programs at United States commercial nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Dunlop, A.; Colaccino, J.

    1996-12-01

    Periodic inspections of pump and valve inservice testing (IST) programs in United States commercial nuclear power plants are performed by Nuclear Regulatory Commission (NRC) Regional Inspectors to verify licensee regulatory compliance and licensee commitments. IST inspections are conducted using NRC Inspection Procedure 73756, {open_quotes}Inservice Testing of Pumps and Valves{close_quotes} (IP 73756), which was updated on July 27, 1995. A large number of IST inspections have also been conducted using Temporary Instruction 2515/114, {open_quotes}Inspection Requirements for Generic Letter 89-04, Acceptable Inservice Testing Programs{close_quotes} (TI-2515/114), which was issued January 15, 1992. A majority of U.S. commercial nuclear power plants have had an IST inspection to either IP 73756 or TI 2515/114. This paper is intended to summarize the significant and recurring findings from a number of these inspections since January of 1990.

  14. A technology development summary for the AGT101 Advanced Gas Turbine Program

    Energy Technology Data Exchange (ETDEWEB)

    Boyd, G.L.; Kidwell, J.R.; Kreiner, D.M.

    1987-01-01

    Since the program initiation in October 1979, the Garrett/Ford Advanced Gas Turbine Program, designated AGT101, has made significant progress in developing ceramic technology for gas turbine applications. Successful component development has resulted in engine tests with an all ceramic hot section to temperatures up to 2200F (1204C) and full speed operation to 100,000 rpm (turbine rotor tip speed of 2300 ft/sec (701 m/s)). An 85-hour test was performed on an all ceramic engine at 2200F (1204C) turbine inlet temperature. These engine tests represent important first steps in the development of ceramic materials and technology. Engine evaluation was preceded by important component development. Activities included aerodynamic component evaluation and development of a high temperature foil bearing to support the ceramic turbine rotor. Development of low leakage regenerator seals and static ceramic seals in this high temperature environment were critical to engine performance.

  15. Emeritus Scientists, Mathematicians and Engineers (ESME) program. Summary of activities for school year 1991--1992

    Energy Technology Data Exchange (ETDEWEB)

    Sharlin, H.I.

    1992-09-01

    The Emeritus Scientists, Mathematicians and Engineers (ESME) program matches retired scientists and engineers with wide experience with elementary school children in order to fuel the children`s natural curiosity about the world in which they live. The long-range goal is to encourage students to maintain the high level of mathematical and science capability that they exhibit at an early age by introducing them to the fun and excitement of the world of scientific investigation and engineering problem solving. Components of the ESME program are the emeriti, established teacher-emeriti teams that work to produce a unit of 6 class hours of demonstration or hands-on experiments, and the encounter by students with the world of science/engineering through the classroom sessions and a field trip to a nearby plant or laboratory.

  16. The summary of the fundamental power development program for fiscal 1981

    International Nuclear Information System (INIS)

    Murakami, Masami

    1982-01-01

    The Power Source Development Coordination Council put tentatively the target of starting construction in fiscal 1981 at hydraulic 1,000 MW, thermal 5,000 MW and nuclear 5,000 MW, totaling 11,000 MW. Subsequently, after the coordination among the ministries and agencies concerned, the following development program was formally decided for fiscal 1981: hydraulic power 290 MW at 22 sites, thermal power 5,480 MW at 9 sites and nuclear power 1,980 MW at two sites, totaling 7,750 MW at 33 sites. This is 70 % of the tentative target. Nuclear power generation thus put in the fundamental power development program was: one BWR unit of 825 MW in Maki, Niigata Prefecture (Tohoku Electric), and two PWR units of 579 MW each in Kyowa-Tomari in Hokkaido (Hokkaido Electric). (J.P.N.)

  17. Status summary of chemical processing development in plutonium-238 supply program

    Energy Technology Data Exchange (ETDEWEB)

    Collins, Emory D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Benker, Dennis [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wham, Robert M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); DePaoli, David W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Delmau, Laetitia Helene [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sherman, Steven R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-10-01

    This document summarizes the status of development of chemical processing in the Plutonium-238 Supply Program (PSP) near the end of Demonstration 1. The objective of the PSP is “to develop, demonstrate, and document a production process that meets program objectives and to prepare for its operation” (Frazier et al. 2016). Success in the effort includes establishing capability using the current infrastructure to produce Np targets for irradiation in Department of Energy research reactors, chemically processing the irradiated targets to separate and purify the produced Pu and transferring the PuO2 product to Los Alamos National Laboratory (LANL) at an average rate of 1.5 kg/y.

  18. Summary of national and international fuel cycle and radioactive waste management programs, 1984

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

    1984-07-01

    Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories.

  19. Summary of non-US national and international fuel cycle and radioactive waste management programs 1982

    International Nuclear Information System (INIS)

    Harmon, K.M.; Kelman, J.A.

    1982-08-01

    Brief program overviews of fuel cycle, spent fuel, and waste management activities in the following countries are provided: Argentina, Australia, Austria, Belgium, Brazil, Canada, China, Denmark, Finland, France, German Federal Republic, India, Italy, Japan, Republic of Korea, Mexico, Netherlands, Pakistan, South Africa, Spain, Sweden, Switzerland, Taiwan, USSR, and the United Kingdom. International nonproliferation activities, multilateral agreements and projects, and the international agencies specifically involved in the nuclear fuel cycle are also described

  20. Fiscal year 1994 well installation program summary report, Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1994-09-01

    This report summarizes the well installation activities conducted during the federal fiscal year (FY) 1994 drilling program at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Synopses of monitoring well construction/well development data, well location rationale, geological/hydrological observations, quality assurance/quality control methods, and health and safety monitoring are included. Two monitoring wells were installed and one piezometer installation was attempted, but not completed, during the FY 1994 drilling program. In addition, SAIC provided health and safety and geotechnical oversight for two soil borings in support of the Y-12 Underground Storage Tank (UST) Program. All new monitoring wells were developed by either a 2.0-in. diameter swab rig or by hand bailing until nonspecific indicator parameters (pH and specific conductance) attained steady-state levels. Turbidity levels were lowered, if required, to the extent practicable by continued development beyond a steady-state level of pH and conductance. All well installation was conducted following industry-standard methods and approved procedures in the Environment Surveillance Procedures Quality Control Program (Energy Systems 1988), the Resource Conservation and Recovery Act (RCRA) Groundwater Monitoring Technical Enforcement Guidance Document (EPA 1986), and Guidelines for Installation of Monitor Wells at the Y-12 Plant (Geraghty and Miller 1985). Health and safety monitoring and field screening of drilling returns and development waters were conducted in accordance with approved Martin Marietta Energy Systems, Inc. (Energy Systems) guidelines. All of the monitoring wells installed during FY 1994 at the Y-12 Plant were of screened construction

  1. Summary of non-US national and international fuel cycle and radioactive waste management programs 1982

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, K.M.; Kelman, J.A.

    1982-08-01

    Brief program overviews of fuel cycle, spent fuel, and waste management activities in the following countries are provided: Argentina, Australia, Austria, Belgium, Brazil, Canada, China, Denmark, Finland, France, German Federal Republic, India, Italy, Japan, Republic of Korea, Mexico, Netherlands, Pakistan, South Africa, Spain, Sweden, Switzerland, Taiwan, USSR, and the United Kingdom. International nonproliferation activities, multilateral agreements and projects, and the international agencies specifically involved in the nuclear fuel cycle are also described.

  2. Summary of national and international fuel cycle and radioactive waste management programs, 1984

    International Nuclear Information System (INIS)

    Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

    1984-07-01

    Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories

  3. Extremely Low Frequency (ELF) Communications System Ecological Monitoring Program: Plan and Summary of 1982 Progress.

    Science.gov (United States)

    1983-08-01

    Scientific studies were funded through a peer-reviewed, competitive bidding process in mid-1982, and studies were initiated at the Wisconsin and Michigan ELF...Naval Electronic Systems Command (NESC) during and subsequent to the ELF Comunications Program environmental impact evaluation process, includ- ing the... scientific review of ELF electromagnetic field effects made by the National Academy of Sciences in 1977. This document generally describes the

  4. Fiscal Year 1993 Well Plugging and Abandonment Program Summary Report Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    This report is a synopsis of the progress of the well plugging and abandonment program at the Y-12 Plant, Oak Ridge, Tennessee, from October 1993 through August 1994. A total of 57 wells and borings were plugged and abandoned during the period of time covered in this report. All wells and borings were plugged and abandoned in accordance with the Monitoring Well Plugging and Abandonment Plan for the U.S. Department of Energy, Y-12 Plant, Oak Ridge, Tennessee.

  5. Integrating Gender into World Bank Financed Transport Programs : Component 1. Case Study Summary and Final Report

    OpenAIRE

    IC Net

    2004-01-01

    The World Bank in November 2001 commissioned IC Net Limited of Japan to carry out a study titled 'Integrating Gender into World Bank Financed Transport Programs' in accord with the terms of reference (TOR) issued in June 2001. The study was financed by a grant from the Japanese Large Studies Trust Fund. The contract came into effect on 15 December 2001 and covers the period to 15 June 2004...

  6. Hazardous Waste Development, Demonstration, and Disposal (HAZWDDD) program plan: Executive summary

    International Nuclear Information System (INIS)

    McGinnis, C.P.; Eisenhower, B.M.; Reeves, M.E.; DePaoli, S.M.; Stinton, L.H.; Harrington, E.H.

    1989-02-01

    The Hazardous Waste Development, Demonstration, and Disposal (HAZWDDD) Program Plan provides a strategy for management of hazardous and mixed wastes generated by the five Department of Energy (DOE) installations managed by Martin Marietta Energy Systems, Inc. (Energy Systems). This integrated corporate plan is based on the individual installation plans, which identify waste streams, facility capabilities, problem wastes, future needs, and funding needs. Using this information, the corporate plan identifies common concerns and technology/facility needs over the next 10 years. The overall objective of this corporate plan is to ensure that treatment, storage, and disposal (TSD) needs for all hazardous and mixed wastes generated by Energy Systems installations have been identified and planned for. Specific objectives of the program plan are to (1) identify all hazardous and mixed waste streams; (2) identify hazardous and mixed waste TSD requirements; (3) identify any unresolved technical issues preventing implementation of the strategy; (4) develop schedules for studies, demonstrations, and facilities to resolve the issues; and (5) define the interfaces with the Low-Level Waste Disposal Development and Demonstration (LLWDDD) Program. 10 refs., 7 figs

  7. 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.

  8. Japan's Sunshine Project. Summary of solar energy research and development program (1983 edition)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1983-07-01

    The Sunshine Program is managed by the promotion center established by the Agency of Industrial Science and Technology of the Ministry of International Trade and Ministry, and is allocated for fiscal 1983 a budget of 8.9 times 1-billion yen. The program is to come to a conclusion in 2000. The program covers not only photovoltaic power generation but also many other fields in which research and development efforts bear fruits of success in practical application one after the other. At the current stage, the target is the test run of a crystalline solar cell mass production line (500kW/year). Basic studies and development will also proceed for the practicalization of amorphous solar cells. For photovoltaic power generation, four demonstration systems and two central power plants will be constructed and operated. Two solar thermal power generation systems each capable of 1000kWe will be tested and operated. Solar systems will be constructed and operated for industrial process heating. Articles on photovoltaic power generation in this book cover the basic study of solar cells, development of crystalline/amorphous solar cells, development of mass production technology, and development of system technology. Reference is also made to the state of development of solar thermal power generation and solar thermal heating/cooling. (NEDO)

  9. Summary Report, Southwest Regional Geothermal Operations Research Program: First project year, June 1977-August 1978

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Richard T.; Davidson, Ray

    1978-12-01

    The overall objectives of the first year project were as follows: (1) to develop realistic but aggressive scenarios with certainty factors for the development of each identified geothermal resource area in Arizona, Colorado, Nevada, New Mexico, and Utah; (2) to delineate the public actions, together with their schedules, required for the scenarios to materialize; and (3) to develop a computer-based data storage and retrieval system (i.e. a Regional Program Progress Monitor) of the level of a preliminary working model, which is capable of displaying program approach but is not loaded with all available data. In addition, each sponsor had supplementary objectives aligned to its own programmatic goals. DOE sought to develop expertise and programs within the appropriate state agencies upon which future DOE development and commercialization activities could be structured. FCRC sought to promote the utilization of geothermal energy throughout the five-state region for purposes of expanded economic development, increased employment, and higher citizen incomes. The goals of the five states varied from state to state, but generally included the following: development of alternative energy sources to replace dwindling supplies of oil and natural gas; economic and industrial development in rural areas; encouragement of industry and utility development of geothermal energy for electrical power generation; demonstration of the practical applications of energy research and development; and close interaction with business and industry for the commercialization of both electric and direct thermal applications.

  10. Elastocapillary Instability in Mitochondrial Fission

    Science.gov (United States)

    Gonzalez-Rodriguez, David; Sart, Sébastien; Babataheri, Avin; Tareste, David; Barakat, Abdul I.; Clanet, Christophe; Husson, Julien

    2015-08-01

    Mitochondria are dynamic cell organelles that constantly undergo fission and fusion events. These dynamical processes, which tightly regulate mitochondrial morphology, are essential for cell physiology. Here we propose an elastocapillary mechanical instability as a mechanism for mitochondrial fission. We experimentally induce mitochondrial fission by rupturing the cell's plasma membrane. We present a stability analysis that successfully explains the observed fission wavelength and the role of mitochondrial morphology in the occurrence of fission events. Our results show that the laws of fluid mechanics can describe mitochondrial morphology and dynamics.

  11. A threshold for dissipative fission

    International Nuclear Information System (INIS)

    Thoennessen, M.; Bertsch, G.F.

    1993-01-01

    The empirical domain of validity of statistical theory is examined as applied to fission data on pre-fission data on pre-fission neutron, charged particle, and γ-ray multiplicities. Systematics are found of the threshold excitation energy for the appearance of nonstatistical fission. From the data on systems with not too high fissility, the relevant phenomenological parameter is the ratio of the threshold temperature T thresh to the (temperature-dependent) fission barrier height E Bar (T). The statistical model reproduces the data for T thresh /E Bar (T) thresh /E Bar (T) independent of mass and fissility of the systems

  12. SUMMARY OF 2010 DOE EM INTERNATIONAL PROGRAM STUDIES OF WASTE GLASS STRUCTURE AND PROPERTIES

    Energy Technology Data Exchange (ETDEWEB)

    Fox, K.; Choi, A.; Marra, J.; Billings, A.

    2011-02-07

    Collaborative work between the Savannah River National Laboratory (SRNL) and SIA Radon in Russia was divided among three tasks for calendar year 2010. The first task focused on the study of simplified high level waste glass compositions with the objective of identifying the compositional drivers that lead to crystallization and poor chemical durability. The second task focused on detailed characterization of more complex waste glass compositions with unexpectedly poor chemical durabilities. The third task focused on determining the structure of select high level waste glasses made with varying frit compositions in order to improve models under development for predicting the melt rate of the Defense Waste Processing Facility (DWPF) glasses. The majority of these tasks were carried out at SIA Radon. Selection and fabrication of the glass compositions, along with chemical composition measurements and evaluations of durability were carried out at SRNL and are described in this report. SIA Radon provided three summary reports based on the outcome of the three tasks. These reports are included as appendices to this document. Briefly, the result of characterization of the Task 1 glasses may indicate that glass compositions where iron is predominantly tetrahedrally coordinated have more of a tendency to crystallize nepheline or nepheline-like phases. For the Task 2 glasses, the results suggested that the relatively low fraction of tetrahedrally coordinated boron and the relatively low concentrations of Al{sub 2}O{sub 3} available to form [BO{sub 4/2}]{sup -}Me{sup +} and [AlO{sub 4/2}]{sup -}Me{sup +} tetrahedral units are not sufficient to consume all of the alkali ions, and thus these alkali ions are easily leached from the glasses. All of the twelve Task 3 glass compositions were determined to be mainly amorphous, with some minor spinel phases. Several key structural units such as metasilicate chains and rings were identified, which confirms the current modeling

  13. Summary of ROSA-4 LSTF first phase test program and station blackout (TMLB) test results

    International Nuclear Information System (INIS)

    Tasaka, K.; Kukita, Y.; Anoda, Y.

    1990-01-01

    This paper summarizes major test results obtained at the ROSA-4 Large Scale Test Facility (LSTF) during the first phase of the test program. The results from a station blackout (TMLB) test conducted at the end of the first-phase program are described in some detail. The LSTF is an integral test facility being operated by the Japan Atomic Energy Research Institute for simulation of pressurized water reactor (PWR) thermal-hydraulic responses during small-break loss-of-coolant accidents (SBLOCAs) and operational/abnormal transients. It is a 1/48 volumetrically scaled, full-height, full-pressure simulator of a Westinghouse-type 4-loop PWR. The facility includes two symmetric primary loops each one containing an active inverted-U tube steam generator and an active reactor coolant pump. The loop horizontal legs are sized to conserve the scaled (1/24) volumes as well as the length to the square root of the diameter ratio in order to simulate the two-phase flow regime transitions. The primary objective of the LSTF first-phase program was to define the fundamental PWR thermal-hydraulic responses during SBLOCAs and transients. Most of the tests were conducted with simulated component/operator failures, including unavailability of the high pressure injection system and auxiliary feedwater system, as well as operator failure to take corrective actions. The forty-two first phase tests included twenty-nine SBLOCA tests conducted mainly for cold leg breaks, three abnormal transient tests and ten natural circulation tests. Attempts were made in several of the SBLOCA tests to simulate the plant recovery procedures as well as candidate accident management measures for prevention of high-pressure core melt situation. The natural circulation tests simulated the single-phase and two-phase natural circulation as well as reflux condensation behavior in the primary loops in steady or quasi-steady states

  14. Summary and recommendations of the NRC/INEL Activated Carbon Testing Program

    International Nuclear Information System (INIS)

    Scarpellino, C.D.; Sill, C.W.

    1986-01-01

    The Committee on Nuclear Air and Gas Treatment (CONAGT) of the American Society of Mechanical Engineers (ASME) sponsored an interlaboratory testing program, round-robin, of nuclear-grade activated carbon. The results of this round-robin revealed gross differences in penetration of radio-labeled methyl iodide as measured by the various laboratories when using Method A of the ASTM D-3803-79 Standard. These differences prompted the Nuclear Regulatory Commission (NRC) to establish the NRC/INEL Activated Carbon Testing Program to determine the causes of these discrepancies and to provide recommendations that could lead to an accurate and reliable testing procedure that would ensure an adequate method for assessing the capability of activated carbon to remove radioiodine from gas streams within commercial nuclear power plants. The NRC/INEL Activated Carbon Testing Program has conducted formal and informal interlaboratory comparisons to identify problems with the test method and its application and to assess the effectiveness of changes to procedures and equipment voluntarily implemented by commercial laboratories to mitigate the disparity of test results. The results of the first formal NRC/INEL Interlaboratory Comparison (IC) essentially verified the CONAGT round-robin results despite the use of a detailed test protocol. This data indicated that many of the participating laboratories probably had been operating outside the ASTM specifications for relative humidity (RH) and flow. In addition, this process provided information which was used to modify the testing protocol employed for the second NRC/INEL Interlaboratory Comparison (IC-2) to make it more rugged and reliable. These changes to the protocol together with the results of INEL sensitivity testing are the basis for the recommendations presented

  15. Electromagnetic pulse research on electric power systems: Program summary and recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Barnes, P.R.; McConnell, B.W.; Van Dyke, J.W. (Oak Ridge National Lab., TN (United States)); Tesche, F.M. (Tesche (F.M.), Dallas, TX (United States)); Vance, E.F. (Vance (E.F.), Fort Worth, TX (United States))

    1993-01-01

    A single nuclear detonation several hundred kilometers above the central United States will subject much of the nation to a high-altitude electromagnetic pulse (BENT). This pulse consists of an intense steep-front, short-duration transient electromagnetic field, followed by a geomagnetic disturbance with tens of seconds duration. This latter environment is referred to as the magnetohydrodynamic electromagnetic pulse (NMENT). Both the early-time transient and the geomagnetic disturbance could impact the operation of the nation's power systems. Since 1983, the US Department of Energy has been actively pursuing a research program to assess the potential impacts of one or more BENT events on the nation's electric energy supply. This report summarizes the results of that program and provides recommendations for enhancing power system reliability under HENT conditions. A nominal HENP environment suitable for assessing geographically large systems was developed during the program and is briefly described in this report. This environment was used to provide a realistic indication of BEMP impacts on electric power systems. It was found that a single high-altitude burst, which could significantly disturb the geomagnetic field, may cause the interconnected power network to break up into utility islands with massive power failures in some areas. However, permanent damage would be isolated, and restoration should be possible within a few hours. Multiple bursts would likely increase the blackout areas, component failures, and restoration time. However, a long-term blackout of many months is unlikely because major power system components, such as transformers, are not likely to be damaged by the nominal HEND environment. Moreover, power system reliability, under both HENT and normal operating conditions, can be enhanced by simple, and often low cost, modifications to current utility practices.

  16. Barium 139 as Fission Indicator

    Energy Technology Data Exchange (ETDEWEB)

    Broda, E.

    1943-07-01

    This report is based on a measurement performed at the Cavendish Laboratory (Cambridge) by E. Broda in December 1943 where a technique has been worked out for measuring the fission density in a uranium containing medium in relative units by determining the amount of a suitable fission product formed. Generally a given fission product will be formed in natural uranium by slow neutron fission of U235 or by fast neutron fission of either U235 or U238. It is intended to translate the relative units into absolute units by comparison of the Ba yield with the indication of UF6 fission chamber in the same medium. This has to be done separately for fast and slow neutron fission as the yields may be different. Another application of the technique developed is the measurement of thermal neutron density in an uraniferous medium without using a detector subject to variations of sensitivity according to the properties of the medium. (nowak)

  17. Nerva Fuel Element Development Program Summary Report - July 1966 through June 1972 Extrusion Studies

    Energy Technology Data Exchange (ETDEWEB)

    Napier, J. M.

    1973-09-21

    This part of the completion report pertaining to the NERVA graphite fuel element program covers data collected during the extrusion studies. The physical properties of the fuel element reached the following values: coefficient of thermal expansion (CTE) - 7.0 x 10-6/o C (25 - l,OOOo C); modulus of elasticity - 1.5 x lo6 psi; flexural strength - - 8,000 psi; ultimate strain to failure - 5,500 pidin; good thermal stress resistance. Matrices were produced which could be vapor coated with crack-free films of zirconium carbide. The CTE of the matrix was almost equal to the CTE of the zirconium carbide coating.

  18. Geothermal Technologies Program Geoscience and Supporting Technologies 2001 University Research Summaries

    International Nuclear Information System (INIS)

    Creed, R.J.; Laney, P.T.

    2002-01-01

    The U.S. Department of Energy Office of Wind and Geothermal Technologies (DOE) is funding advanced geothermal research through University Geothermal Research solicitations. These solicitations are intended to generate research proposals in the areas of fracture permeability location and characterization, reservoir management and geochemistry. The work funded through these solicitations should stimulate the development of new geothermal electrical generating capacity through increasing scientific knowledge of high-temperature geothermal systems. In order to meet this objective researchers are encouraged to collaborate with the geothermal industry. These objectives and strategies are consistent with DOE Geothermal Energy Program strategic objectives

  19. National Center for Analysis of Energy Systems: program summaries for 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    This Center, founded in January 1976, is one of four areas comprising the Department of Energy and Environment at Brookhaven National Laboratory. The major ongoing activities of the Center concern integrated, quantitative analyses of technological, economic, and environmental aspects of energy at the regional, national, and international levels. The objectives, activities, and sources of support of each of the programs are described and the major accomplishments during the year are outlined. Some of the planned future activities of the Center are indicated, and recent publications are listed.

  20. Geothermal Technologies Program Geoscience and Supporting Technologies 2001 University Research Summaries

    Energy Technology Data Exchange (ETDEWEB)

    Creed, R.J.; Laney, P.T.

    2002-05-14

    The U.S. Department of Energy Office of Wind and Geothermal Technologies (DOE) is funding advanced geothermal research through University Geothermal Research solicitations. These solicitations are intended to generate research proposals in the areas of fracture permeability location and characterization, reservoir management and geochemistry. The work funded through these solicitations should stimulate the development of new geothermal electrical generating capacity through increasing scientific knowledge of high-temperature geothermal systems. In order to meet this objective researchers are encouraged to collaborate with the geothermal industry. These objectives and strategies are consistent with DOE Geothermal Energy Program strategic objectives.

  1. Geothermal Technologies Program Geoscience and Supporting Technologies 2001 University Research Summaries

    Energy Technology Data Exchange (ETDEWEB)

    Creed, Robert John; Laney, Patrick Thomas

    2002-06-01

    The U.S. Department of Energy Office of Wind and Geothermal Technologies (DOE) is funding advanced geothermal research through University Geothermal Research solicitations. These solicitations are intended to generate research proposals in the areas of fracture permeability location and characterization, reservoir management and geochemistry. The work funded through these solicitations should stimulate the development of new geothermal electrical generating capacity through increasing scientific knowledge of high-temperature geothermal systems. In order to meet this objective researchers are encouraged to collaborate with the geothermal industry. These objectives and strategies are consistent with DOE Geothermal Energy Program strategic objectives.

  2. JSPS-CAS Core University Program seminar on summary of 10-year collaborations in plasma and nuclear fusion research area

    International Nuclear Information System (INIS)

    Toi, Kazuo; Wang Kongjia

    2011-07-01

    The JSPS-CAS Core University Program (CUP) seminar on “Summary of 10-year Collaborations in Plasma and Nuclear Fusion Research Area” was held from March 9 to March 11, 2011 in the Okinawa Prefectural Art Museum, Naha city, Okinawa, Japan. The collaboration program on plasma and nuclear fusion started from 2001 under the auspices of Japanese Society of Promotion of Science (JSPS) and Chinese Academy of Sciences (CAS). This year is the last year of the CUP. This seminar was organized in the framework of the CUP. In the seminar, 29 oral talks were presented, having 14 Chinese and 30 Japanese participants. These presentations covered key topics related to the collaboration categories: (1) improvement of core plasma properties, (2) basic research on fusion reactor technologies, and (3) theory and numerical simulation. This seminar aims at summarizing the results obtained through the collaborations for 10 years, and discussing future prospects of China-Japan collaboration in plasma and nuclear fusion research areas. (author)

  3. Nye County nuclear waste repository project office independent scientific investigations program. Summary annual report, May 1996--April 1997

    International Nuclear Information System (INIS)

    1997-05-01

    This annual summary report, prepared by Multimedia Environmental Technology, Inc. (MET) on behalf of Nye County Nuclear Waste Project Office, summarizes the activities that were performed during the period from May 1, 1996 to April 30, 1997. These activities were conducted in support of the Independent Scientific Investigation Program (ISIP) of Nye County at the Yucca Mountain Site (YMS). The Nye County NWRPO is responsible for protecting the health and safety of the Nye County residents. NWRPO's on-site representative is responsible for designing and implementing the Independent Scientific Investigation Program (ISIP). Major objectives of the ISIP include: (1) Investigating key issues related to conceptual design and performance of the repository that can have major impact on human health, safety, and the environment. (2) Identifying areas not being addressed adequately by DOE Nye County has identified several key scientific issues of concern that may affect repository design and performance which were not being adequately addressed by DOE. Nye County has been conducting its own independent study to evaluate the significance of these issues

  4. Analysis of AEC-ERDA-DOE and USGS uranium program data: disipline reviews and summary reports. Final report

    International Nuclear Information System (INIS)

    1980-03-01

    Most of the literature dealing with the econmic geology and exploitation of uranium deposits in the United States has been published since 1950, primarily by the Department of Energy (DOE) and its predecessor agencies. The limited availability of much of these data, combined with the inexperience of many electric power utilities and, to some extent, mining companies with regard to uranium exploration, frequently resulted in the inauguration of ill-conceived and duplicative efforts. To assess the value of this literature in light of present knowledge, a systematic review of those publications dealing with uranium exploration, and the economic geology, evaluation, and exploitation of uranium deposits was undertaken. Matrix reports (summaries) have been prepared for each of the nearly 2500 documents reviewed. This material is available through the computerized literature search services of the Oak Ridge National Laboratory. In addition, thirteen discipline reviews and summary reports were compiled within the broad fields of uraium geology and mining engineering frm which any advances in knowledge would have the greatest impact on the future discovery and exploitation of uranium deposits. A final chapter presents a critique of the DOE National Uranium Resource Evaluation Program, as judged by members of the uranium industry. A two-part report summarizes and analyzes the results of this investigation. Part 1 is primarily an introduction to the various types of uranium deposits, the geologic and structural environments in which they occur, and the mechanisms for their emplacement. Part 2 considers the various techniques used to explore, evaluate, and exploit uranium deposits. The report is intended to serve as a major source of basic information concerning previous uranium-related studies for all those involved with the search for and utilization of uranium

  5. Summary and conclusions of a program addressing aging of nuclear power plant concrete structures

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Hookham, C.J.; Graves, H.L. III

    1999-01-01

    Research has been conducted by the Oak Ridge National Laboratory to address aging management of nuclear power plant concrete structures. The purpose was to identify potential structural safety issues and acceptance criteria for use in continued service assessments. The focus of this program was on structural integrity rather than on leaktightness or pressure retention of concrete structures. Primary program accomplishments include formulation of a Structural Materials Information Center that contains data and information on the time variation of material properties under the influence of pertinent environmental stressors and aging factors for 144 materials, an aging assessment methodology to identify critical structures and degradation factors that can potentially impact their performance, guidelines and evaluation criteria for use in condition assessments of reinforced concrete structures, and a reliability-based methodology for current condition assessments and estimations of future performance of reinforced concrete nuclear power plant structures. In addition, in-depth evaluations were conducted of several nondestructive evaluation and repair-related technologies to develop guidance on their applicability. (orig.)

  6. The Coastal Ocean Prediction Systems program: Understanding and managing our coastal ocean. Volume 1: Strategic summary

    Energy Technology Data Exchange (ETDEWEB)

    1990-05-15

    The proposed COPS (Coastal Ocean Prediction Systems) program is concerned with combining numerical models with observations (through data assimilation) to improve our predictive knowledge of the coastal ocean. It is oriented toward applied research and development and depends upon the continued pursuit of basic research in programs like COOP (Coastal Ocean Processes); i.e., to a significant degree it is involved with ``technology transfer`` from basic knowledge to operational and management applications. This predictive knowledge is intended to address a variety of societal problems: (1) ship routing, (2) trajectories for search and rescue operations, (3) oil spill trajectory simulations, (4) pollution assessments, (5) fisheries management guidance, (6) simulation of the coastal ocean`s response to climate variability, (7) calculation of sediment transport, (8) calculation of forces on structures, and so forth. The initial concern is with physical models and observations in order to provide a capability for the estimation of physical forces and transports in the coastal ocean. For all these applications, there are common needs for physical field estimates: waves, tides, currents, temperature, and salinity, including mixed layers, thermoclines, fronts, jets, etc. However, the intent is to work with biologists, chemists, and geologists in developing integrated multidisciplinary prediction systems as it becomes feasible to do so. From another perspective, by combining observations with models through data assimilation, a modern approach to monitoring is provided through whole-field estimation.

  7. ORNL long-range environmental and waste management plan: Program overview and summary

    International Nuclear Information System (INIS)

    Bates, L.D.; Berry, J.B.; Butterworth, G.E.

    1988-04-01

    The primary purpose of this report is to provide a thorough and systematic planning document to reflect the continuing process of site assessment, strategy development, and planning for the current and long-term control of environmental issues, waste management practices, and remedial action requirements. The docuemnt also provides an estimate of the resources required to implement the current plan. This document is not intended to be a budget document: it is, however, intended to provide guidance to both Martin Marietta Energy Systems, Inc., and the US Department of Energy (DOE) Management as to the near order of magnitude of the resources (primarily funding requirements) and the time frame required to execute the strategy in the present revision of the plan. The near-term (one to three years) part of the plan is a realistic assessment of the current program and ongoing capital projects and reflects the efforts preceived to be necessary to comply with all current state and federal regulations and DOE orders. It also should be in general agreement with current budget (funding) requests and obligations for these immediate years. Beyond the immediate time frame, the document reflects the strategy and the project and funding estimates as a snapshot at the time of publication. Annual revision will reflect the continuing evoltuion and development of environmental and waste management processes, characterizations, remedial actions, regulations, an strategies for the establishment and conduct of a comprehensive environmental and waste management program. 15 figs., 10 tabs

  8. FY 2008 Next Generation Safeguards Initiative International Safeguards Education and Training Pilot Programs Summary Report

    International Nuclear Information System (INIS)

    Dreicer, M.; Anzelon, G.; Essner, J.; Dougan, A.; Doyle, J.; Boyer, B.; Hypes, P.; Sokova, E.; Wehling, F.

    2008-01-01

    Key component of the Next Generation Safeguards Initiative (NGSI) launched by the National Nuclear Security Administration is the development of human capital to meet present and future challenges to the safeguards regime. An effective university-level education in safeguards and related disciplines is an essential element in a layered strategy to rebuild the safeguards human resource capacity. Two pilot programs at university level, involving 44 students, were initiated and implemented in spring-summer 2008 and linked to hands-on internships at LANL or LLNL. During the internships, students worked on specific safeguards-related projects with a designated Laboratory Mentor to provide broader exposure to nuclear materials management and information analytical techniques. The Safeguards and Nuclear Material Management pilot program was a collaboration between the Texas A and M University (TAMU), Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). It included a 16-lecture course held during a summer internship program. The instructors for the course were from LANL together with TAMU faculty and LLNL experts. The LANL-based course was shared with the students spending their internship at LLNL via video conference. A week-long table-top (or hands-on) exercise on was also conducted at LANL. The student population was a mix of 28 students from a 12 universities participating in a variety of summer internship programs held at LANL and LLNL. A large portion of the students were TAMU students participating in the NGSI pilot. The International Nuclear Safeguards Policy and Information Analysis pilot program was implemented at the Monterey Institute for International Studies (MIIS) in cooperation with LLNL. It included a two-week intensive course consisting of 20 lectures and two exercises. MIIS, LLNL, and speakers from other U.S. national laboratories (LANL, BNL) delivered lectures for the audience of 16 students. The majority of students

  9. Findings from the Evaluation of the National Library Power Program. Executive Summary. An Initiative of the DeWitt Wallace-Reader's Digest Fund.

    Science.gov (United States)

    Zweizig, Douglas; Hopkins, Dianne McAfee

    This document presents the executive summary of an evaluation of Library Power, a program of the DeWitt Wallace-Reader's Digest Fund to enhance and elevate the role of libraries in public schools. The report begins with an examination of Library Power's core components (collection development, facilities refurbishing, flexible scheduling,…

  10. Core degradation and fission product release

    International Nuclear Information System (INIS)

    Wright, R.W.; Hagen, S.J.L.

    1992-01-01

    Experiments on core degradation and melt progression in severe LWR accidents have provided reasonable understanding of the principal processes involved in the early phase of melt progression that extends through core degradation and metallic material melting and relocation. A general but not a quantitative understanding of late phase melt progression that involves ceramic material melting and relocation has also been obtained, primarily from the TMI-2 core examination. A summary is given of the current state of knowledge on core degradation and melt progression obtained from these integral experiments and of the principal remaining significant uncertainties. A summary is also given of the principal results on in-vessel fission product release obtained from these experiments. (author). 8 refs, 5 figs, 3 tabs

  11. ORNL Long-Range Environmental and Waste Management Plan: Program overview and summary

    International Nuclear Information System (INIS)

    Bates, L.D.; Berry, J.B.; Butterworth, G.E.

    1987-12-01

    The primary purpose is to provide a thorough and systematic planning document to reflect the continuing process of site assessment, strategy development, and planning for the current and long-term control of environmental issues, waste management practices, and remedial action requirments. The document also provides an estimate of the resources required to implenent the current plan. As with any document of this nature, the near-term (one to three years) part of the plan is a realistic assessment of the current program and ongoing capital projects and relects the efforts preceived to be necesary to comply with all current state and federal regulations and DOE orders. It also should be in general agreement with current budget (funding) requests and obligations for these immediate years. Beyond the immediate time frame, the document reflects the strategy and the project and funding estimates as a snapshot at the time of publication. 15 figs., 10 tabs

  12. Greenbelt Homes Pilot Energy Efficiency Program Phase 1 Summary. Existing Conditions and Baseline Energy Use

    Energy Technology Data Exchange (ETDEWEB)

    Wiehagen, J. [NAHB Research Center, Upper Marlboro, MD (United States); Del Bianco, M. [NAHB Research Center, Upper Marlboro, MD (United States); Wood, A. [NAHB Research Center, Upper Marlboro, MD (United States)

    2013-02-01

    A multi-year pilot energy efficiency retrofit project has been undertaken by Greenbelt Homes, Inc, (GHI) a 1,566 co-operative of circa 1930 and '40 homes. The three predominate construction methods of the townhomes in the community are materials common to the area and climate zone including 8” CMU block, wood frame with brick veneer and wood frame with vinyl siding. GHI has established a pilot project that will serve as a basis for decision making for the roll out of a decade-long community upgrade program that will incorporate energy efficiency to the building envelope and equipment with the modernization of other systems like plumbing, mechanical equipment, and cladding.

  13. Greenbelt Homes Pilot Energy Efficiency Program Phase 1 Summary: Existing Conditions and Baseline Energy Use

    Energy Technology Data Exchange (ETDEWEB)

    Wiehagen, J.; Del Bianco, M.; Wood, A.

    2013-02-01

    A multi-year pilot energy efficiency retrofit project has been undertaken by Greenbelt Homes, Inc, (GHI) a 1,566 co-operative of circa 1930 and '40 homes. The three predominate construction methods of the townhomes in the community are materials common to the area and climate zone including 8" CMU block, wood frame with brick veneer and wood frame with vinyl siding. GHI has established a pilot project that will serve as a basis for decision making for the roll out of a decade-long community upgrade program that will incorporate energy efficiency to the building envelope and equipment with the modernization of other systems like plumbing, mechanical equipment, and cladding.

  14. Grande Ronde Basin Spring Chinook Salmon Captive Broodstock Program, 1995-2002 Summary Report.

    Energy Technology Data Exchange (ETDEWEB)

    Hoffnagle, Timothy; Carmichael, Richard; Noll, William

    2003-12-01

    survey areas in 1995 from as high as 1,205 redds in the same area in 1969 (Table 1). All streams reached low points (0-6 redds in the index areas) in the 1990's, except those in which no redds were found for several years and surveys were discontinued, such as Spring, Sheep and Indian creeks which had a total of 109 redds in 1969. The Minam and Wenaha rivers are tributaries of the Grande Ronde River located primarily in wilderness areas. Chinook salmon numbers in these two streams (based on redd counts) also decreased dramatically beginning in the early 1970's (Table 1). Since then there have been a few years of increasing numbers of redds but counts have generally been 25-40% of the number seen in the 1960's. No hatchery fish have been released into either of these streams and we monitor them during spawning ground surveys for the presence of hatchery strays. These populations will be used as a type of control for evaluating our supplementation efforts in Catherine Creek, upper Grande Ronde River and Lostine River. In this way, we can attempt to filter out the effects of downstream variables, over which we have no control, when we interpret the results of the captive broodstock program as the F1 and F2 generations spawn and complete their life cycles in the wild. The Grande Ronde Basin Captive Broodstock Program was initiated because these chinook salmon populations had reached critical levels where dramatic and unprecedented efforts were needed to prevent extinction and preserve any future options for use of endemic fish for artificial propagation programs for recovery and mitigation. This program was designed to quickly increase numbers of returning adults, while maintaining the genetic integrity of each endemic population.

  15. Proceedings of the Second Fusion-Fission Energy Systems Review Meeting

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-11-02

    The agenda of the meeting was developed to address, in turn, the following major areas: specific problem areas in nuclear energy systems for application of fusion-fission concepts; current and proposed fusion-fission programs in response to the identified problem areas; target costs and projected benefits associated with fusion-fission energy systems; and technical problems associated with the development of fusion-fission concepts. The greatest emphasis was placed on the characteristics of and problems, associated with fuel producing fusion-fission hybrid reactors.

  16. Fusion-fission dynamics

    International Nuclear Information System (INIS)

    Blocki, J.; Planeta, R.; Brzychczyk, J.; Grotowski, K.

    1991-04-01

    Classical dynamical calculations of the heavy ion induced fission process for the reactions 40 Ar+ 141 Pr, 20 Ne+ 165 Ho and 12 C+ 175 Lu leading to the iridium like nucleus have been performed. As a result prescission lifetimes were obtained and compared with the experimental values. The agreement between the calculated and experimental lifetimes indicates that the one-body dissipation picture is much more relevant in describing the fusion-fission dynamics than the two-body one. Somewhat bigger calculated times than the experimental ones in case of the C+Lu reaction at 16 MeV/nucleon may be a signal on the energy range applicability of the one-body dissipation model. (author)

  17. Chromosomal mutation by fission neutrons and X-rays in higher plants. A review on results of the joint research program utilizing Kinki University reactor

    International Nuclear Information System (INIS)

    Yonezawa, Yoshihiko

    2010-01-01

    We have studied the efficiency of fission neutrons from the nuclear reactor of Kinki University (UTR-KINKI) and X-rays to chromosomes of higher plants for over 20 years. In this review, we described the development of bio-dosimeter using hyper-sensibility of germinating onion roots for irradiation, the analysis of chromosome structure in Haplopappus gracilis (Asteraceae), with the special reference of latent centromeres and survived telomeres throughout chromosomal evolution, the experimental studies on the induction of chromosomal rearrangement in Zebrina pendula (Commelinaceae), the behavior of chromosome fragments with non-localized centromeres in Carex and Eleocharis (Cyperaceae), and the possibility as a bio-dosimeter of pollen mother cells of Tradescantia paludosa (Commelinaceae) for the detection of low-dose radiation. (author)

  18. The fission track method

    International Nuclear Information System (INIS)

    Hansen, K.

    1990-01-01

    During the last decade fission track (FT) analysis has evolved as an important tool in exploration for hydrocarbon resources. Most important is this method's ability to yield information about temperatures at different times (history), and thus relate oil generation and time independently of other maturity parameters. The purpose of this paper is to introduce the basics of the method and give an example from the author's studies. (AB) (14 refs.)

  19. Nonenergy Benefits from the Weatherization Assistance Program: A Summary of Findings from the Recent Literature

    Energy Technology Data Exchange (ETDEWEB)

    Schweitzer, M.

    2002-04-25

    The purpose of this project is to summarize findings reported in the recent literature on nonenergy benefits attributable to the weatherizing of low income homes. This study is a follow-up to the seminal research conducted on the nonenergy benefits attributable to the Department of Energy's national Weatherization Assistance Program by Brown et al. (1993). For this review, nonenergy benefits were broken into three major categories: (1) ratepayer benefits; (2) household benefits; and (3) societal benefits. The ratepayer benefits can be divided into two main subcategories: payment-related benefits and service provision benefits. Similarly, there are two key types of household benefits: those associated with affordable housing and those related to safety, health, and comfort. Societal benefits can be classified as either environmental, social, or economic. Fig. E.S. 1 presents point estimates of the average lifetime monetary value per weatherized home resulting from low income weatherization programs for the key benefit types listed above. These benefits represent net present value estimates (i.e., estimates of the current worth of all benefits expected over the lifetime of the weatherization measures), assuming a 20-year lifetime for installed energy efficiency measures and a 3.2% discount rate. Overall, societal benefits are estimated to be substantially larger than ratepayer and household benefits. Ranges for the societal benefits are also much greater than for the other two categories of nonenergy benefits. The total monetized value for all nonenergy benefit categories associated with weatherizing a home is estimated to be $3346, in 2001 dollars. This represents a national average which, like any point estimate, has considerable uncertainty associated with it. This figure is substantially higher than the total value of nonenergy benefits presented a decade ago in the national weatherization evaluation (Brown et al. 1993) because the current study quantified a

  20. [Fission product yields of 60 fissioning reactions]. Final report

    International Nuclear Information System (INIS)

    Rider, B.F.

    1995-01-01

    In keeping with the statement of work, I have examined the fission product yields of 60 fissioning reactions. In co-authorship with the UTR (University Technical Representative) Talmadge R. England ''Evaluation and Compilation of Fission Product Yields 1993,'' LA-UR-94-3106(ENDF-349) October, (1994) was published. This is an evaluated set of fission product Yields for use in calculation of decay heat curves with improved accuracy has been prepared. These evaluated yields are based on all known experimental data through 1992. Unmeasured fission product yields are calculated from charge distribution, pairing effects, and isomeric state models developed at Los Alamos National Laboratory. The current evaluation has been distributed as the ENDF/B-VI fission product yield data set