WorldWideScience

Sample records for program assessing nuclear

  1. Arctic Nuclear Waste Assessment Program

    International Nuclear Information System (INIS)

    Edson, R.

    1995-01-01

    The Arctic Nuclear Waste Assessment Program (ANWAP) was initiated in 1993 as a result of US congressional concern over the disposal of nuclear materials by the former Soviet Union into the Arctic marine environment. The program is comprised of appr. 70 different projects. To date appr. ten percent of the funds has gone to Russian institutions for research and logistical support. The collaboration also include the IAEA International Arctic Seas Assessment Program. The major conclusion from the research to date is that the largest signals for region-wide radionuclide contamination in the Arctic marine environment appear to arise from the following: 1) atmospheric testing of nuclear weapons, a practice that has been discontinued; 2) nuclear fuel reprocessing wastes carried in the Arctic from reprocessing facilities in Western Europe, and 3) accidents such as Chernobyl and the 1957 explosion at Chelyabinsk-65

  2. Assessment of specialized educational programs for licensed nuclear reactor operators

    International Nuclear Information System (INIS)

    Melber, B.D.; Saari, L.M.; White, A.S.; Geisendorfer, C.L.; Huenefeld, J.C.

    1986-02-01

    This report assesses the job-relatedness of specialized educational programs for licensed nuclear reactor operators. The approach used involved systematically comparing the curriculum of specialized educational programs for college credit, to academic knowledge identified as necessary for carrying out the jobs of licenses reactor operators. A sample of eight programs, including A.S. degree, B.S. degree, and coursework programs were studied. Subject matter experts in the field of nuclear operations curriculum and training determined the extent to which individual program curricula covered the identified job-related academic knowledge. The major conclusions of the report are: There is a great deal of variation among individual programs, ranging from coverage of 15% to 65% of the job-related academic knowledge. Four schools cover at least half, and four schools cover less than one-third of this knowledge content; There is no systematic difference in the job-relatedness of the different types of specialized educational programs, A.S. degree, B.S. degree, and coursework; and Traditional B.S. degree programs in nuclear engineering cover as much job-related knowledge (about one-half of this knowledge content) as most of the specialized educational programs

  3. Program SYVAC, for stochastic assessment of nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Sherman, G.R.; Hoffman, K.J.; Donahue, D.C.

    1985-01-01

    In this paper, the computer program SYVAC, used to assess concepts for the disposal of nuclear fuel waste, is described with regard to the development approach, the basic program structure, and quality assurance. The interrelationships of these aspects are illustrated by detailed descriptions of two concepts of fundamental importance to the program: the method of selecting parameter values from input probability density functions, and the numerical evaluation of the convolution integral. Quality assurance procedures, including different types of comparisons and peer review, are presented

  4. A program to assess microbial impacts on nuclear waste containment

    International Nuclear Information System (INIS)

    Horn, J.; Meike, A.

    1996-01-01

    In this paper we discuss aspects of a comprehensive program to identify and bound potential effects of microorganisms on long-term nuclear waste containment, using as examples, studies conducted within the Yucca Mountain Project. A comprehensive program has been formulated which cuts across standard disciplinary lines to address the specific concerns of microbial activity in a radioactive waste repository. Collectively, this program provides bounding parameters of microbial activities that modify the ambient geochemistry and hydrology, modify corrosion rates, and transport and transform radionuclides under conditions expected to be encountered after geological waste emplacement. This program is intended to provide microbial reaction rates and bounding conditions in a form that can be integrated into existing chemical and hydrological models. The inclusion of microbial effects will allow those models to more accurately assess long term repository integrity

  5. 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.

  6. 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

  7. 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

  8. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume II. Proliferation resistance

    International Nuclear Information System (INIS)

    1980-06-01

    The purpose of this volume is limited to an assessment of the relative effects that particular choices of nuclear-power systems, for whatever reasons, may have on the possible spread of nuclear-weapons capabilities. This volume addresses the concern that non-nuclear-weapons states may be able to initiate efforts to acquire or to improve nuclear-weapons capabilities through civilian nuclear-power programs; it also addresses the concern that subnational groups may obtain and abuse the nuclear materials or facilities of such programs, whether in nuclear-weapons states (NWS's) or nonnuclear-weapons states (NNW's). Accordingly, this volume emphasizes one important factor in such decisions, the resistance of nuclear-power systems to the proliferation of nuclear-weapons capabilities

  9. Radwaste assessment program for nuclear station modifications by design engineering

    International Nuclear Information System (INIS)

    Eble, R.G.

    1988-01-01

    Radwaste burial for Duke Power Company's (DPC's) seven nuclear units has become a complicated and costly process. Burial costs are based on overall volume, surcharges for radioactivity content and weight of containers, truck and cask rental, driver fees, and state fees and taxes. Frequently, radwaste costs can be as high as $500 per drum. Additionally, DPC is limited on the total burial space allocated for each plant each year. The thrust of this program is to reduce radwaste volumes needing burial at either Barnwell, South Carolina, or Richland, Washington. A limited number of options are available at our sites: (a) minimization of radwaste volume production, (b) segregation of contamination and noncontaminated trash, (c) decontamination of small hardware, (d) volume reduction of compatible trash, (e) incineration of combustible trash (available at Oconee in near future), and (f) burial of below-regulatory-concern very low level waste on site. Frequently, costs can be reduced by contracting services outside the company, i.e., supercompaction, decontamination, etc. Information about radwaste volumes, activities, and weight, however, must be provided to the nuclear production department (NPD) radwaste group early in the nuclear station modification (NSM) process to determine the most cost-effective method of processing radwaste. In addition, NSM radwaste costs are needed for the NPD NSM project budget. Due to the advanced planning scope of this budget, NSM construction costs must be estimated during the design-phase proposal

  10. 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

  11. A Computer Program for Assessing Nuclear Safety Culture Impact

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kiyoon; Jae, Moosung [Hanyang Univ., Seoul (Korea, Republic of)

    2014-10-15

    Through several accidents of NPP including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, a lack of safety culture was pointed out as one of the root cause of these accidents. Due to its latent influences on safety performance, safety culture has become an important issue in safety researches. Most of the researches describe how to evaluate the state of the safety culture of the organization. However, they did not include a possibility that the accident occurs due to the lack of safety culture. Because of that, a methodology for evaluating the impact of the safety culture on NPP's safety is required. In this study, the methodology for assessing safety culture impact is suggested and a computer program is developed for its application. SCII model which is the new methodology for assessing safety culture impact quantitatively by using PSA model. The computer program is developed for its application. This program visualizes the SCIs and the SCIIs. It might contribute to comparing the level of the safety culture among NPPs as well as improving the management safety of NPP.

  12. Self-imposed self-assessment program at a DOE Nuclear Facility

    International Nuclear Information System (INIS)

    Geoffrion, R.R.; Loud, J.J.; Walter, E.C.

    1996-01-01

    The Nuclear Materials and Technology (NMT) Division at Los Alamos National Laboratory (LANL) has implemented a performance-based self-assessment program at the TA-55 plutonium facility. The program was conceptualized and developed by LANL's internal assessment group, AA-2. The management walkaround program fosters continuous improvement in NMT products and performance of its activities. The program, based on experience from the Institute of Nuclear Power Operations, is endorsed at the site by the U.S. Department of Energy (DOE) Environment, Safety, and Health (ES ampersand H) personnel and by the Defense Nuclear Facility Safety Board. The self-assessment program focuses on how work is actually performed rather than on paperwork or process compliance. Managers critically and continually assess ES ampersand H, conduct of operations, and other functional area requirements

  13. DOE [Department of Energy]-Nuclear Energy Standards Program annual assessment, FY 1990

    International Nuclear Information System (INIS)

    Williams, D.L. Jr.

    1990-11-01

    To meet the objectives of the programs funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs, the Performance Assurance Project Office (PAPO) administers a nuclear standards program and related activities and fosters the development and application of standards. This standards program is carried out in accordance with the principles in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980. The purposes of this effort, as set forth in three subtasks, are to (1) manage the NE Standards Program, (2) manage the development and maintenance of NE standards, and (3) operate an NE Standards Information Program. This report assesses the Performance Assurance Project Office (PAPO) activities in terms of the objectives of the Department of Energy-Nuclear Energy (DOE-NE) funded programs. To meet these objectives, PAPO administers a nuclear standards program and related activities and fosters the development and application of standards. This task is carried out in accordance with the principles set forth in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980, and DOE memorandum, Implementation of DOE Orders on Quality Assurance, Standards, and Unusual Occurrence Reporting for Nuclear Energy Programs, March 3, 1982, and with guidance from the DOE-NE Technology Support Programs. 1 tab. (JF)

  14. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume V. Economics and systems analysis

    International Nuclear Information System (INIS)

    1979-12-01

    This assessment considers the economics of alternative nuclear reactor and fuel-cycle systems in the light of possible patterns of uranium supply and energy demand, as well as the economic implications of improving the proliferation resistance of the various systems. The assessment focuses on the costs of alternative nuclear technologies and the possible timing of their implementation, based on their economic attractiveness. The objectives of this assessment are to identify when economic incentives to deploy advanced nuclear power systems might exist, to estimate the costs of using technologies that would reduce the risk of proliferation, to assess the impact of major economic uncertainties on the transition to new technologies, and to compare the investments required for alternative systems. This information can then be used to assess the potential economic benefits of alternative research, development, and demonstration programs and the timing of those programs

  15. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume V. Economics and systems analysis

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-12-01

    This assessment considers the economics of alternative nuclear reactor and fuel-cycle systems in the light of possible patterns of uranium supply and energy demand, as well as the economic implications of improving the proliferation resistance of the various systems. The assessment focuses on the costs of alternative nuclear technologies and the possible timing of their implementation, based on their economic attractiveness. The objectives of this assessment are to identify when economic incentives to deploy advanced nuclear power systems might exist, to estimate the costs of using technologies that would reduce the risk of proliferation, to assess the impact of major economic uncertainties on the transition to new technologies, and to compare the investments required for alternative systems. This information can then be used to assess the potential economic benefits of alternative research, development, and demonstration programs and the timing of those programs.

  16. Handbook for nuclear power plant self-assessment programs. Final report, July 1991

    International Nuclear Information System (INIS)

    1991-07-01

    EPRI has prepared this handbook to help utilities with their Self-Assessment Programs at nuclear power plants. Self-assessments are independent reviews performed by nuclear plant utilities to identify trends in operational activities that are important to safety, and to assess the impact of these trends on plant safety. Activities performed as self-assessments include reviews and evaluations of plant performance and abnormal events, technical evaluations of plant activities to identify potential problem areas, and reviews of other sources of plant design and operating experience for applicability to safety. This handbook is based on information obtained from utilities and includes examples of activities and methods that have proven effective. The handbook includes a summary of NRC requirements, guidelines for self-assessment program planning, descriptions and examples of investigative techniques, and key references that can be consulted for additional information. It can serve as a training guide for plant staff members who are assigned to self-assessment activities. (author)

  17. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IV. Commercial potential

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    This volume of the Nonproliferation Alternative Systems Assessment Program (NASAP) report provides time and cost estimates for positioning new nuclear power systems for commercial deployment. The assessment also estimates the rates at which the new systems might penetrate the domestic market, assuming the continuing viability of the massive light-water reactor network that now exists worldwide. This assessment does not recommend specific, detailed program plans and budgets for individual systems; however, it is clear from this analysis that any of the systems investigated could be deployed if dictated by national interest.

  18. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IV. Commercial potential

    International Nuclear Information System (INIS)

    1980-06-01

    This volume of the Nonproliferation Alternative Systems Assessment Program (NASAP) report provides time and cost estimates for positioning new nuclear power systems for commercial deployment. The assessment also estimates the rates at which the new systems might penetrate the domestic market, assuming the continuing viability of the massive light-water reactor network that now exists worldwide. This assessment does not recommend specific, detailed program plans and budgets for individual systems; however, it is clear from this analysis that any of the systems investigated could be deployed if dictated by national interest

  19. Disposal facility for spent nuclear fuel. Environmental impact assessment program

    International Nuclear Information System (INIS)

    1998-01-01

    The report presents the Environmental Impact Assessment (EIA) of the high level radioactive waste disposal in Finland. In EIA different alternatives concerning site selection, construction, operation and sealing of the disposal facility as well as waste transportation and encapsulation of the waste are considered

  20. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume IV. Commercial potential

    International Nuclear Information System (INIS)

    1979-12-01

    Volume IV provides time and cost estimates for positioning new nuclear power systems for commercial deployment. The assessment also estimates the rates at which the new systems might penetrate the domestic market, assuming the continuing viability of the massive light-water reactor network that now exists worldwide. This assessment does not recommend specific, detailed program plans and budgets for individual systems; however, it is clear from this analysis that any of the systems investigated could be deployed if dictated by national interest

  1. Two economic, energetic, and environmental assessments of the French nuclear program

    International Nuclear Information System (INIS)

    Vielle, M.

    1996-01-01

    This paper presents two studies, which try to assess the economic, energy and environmental impact of the French nuclear program. First, the two models used are described briefly and then each study is discussed separately. The main results are summarized in the conclusion. (author). 4 refs., 5 tabs., 8 figs

  2. Assessment of the impacts of the French nuclear program on the environment

    International Nuclear Information System (INIS)

    Naudet, G.

    1994-01-01

    This paper is an assessment of the impact of the French nuclear program on investments, on electricity price, on electricity and energy demand and especially on environment. The impact on atmosphere pollution which is based on a macro economic long term model (called MELODY), particularly detailed for the energy sector, is outlined. (TEC). 10 figs., 1 tab., 4 refs

  3. Methodology for value/impact assessment of nuclear regulatory research programs

    International Nuclear Information System (INIS)

    Carlson, D.D.

    1978-12-01

    A methodology for conducting a value/impact assessment of research programs has been developed to provide the Nuclear Regulatory Commission (NRC) an improved capability for allocating resources for confirmatory research. This report presents a seven-step evaluation process and applies it to selected units of research. The methodology is intended to provide insight into the technical merits of the programs, one dimension of the complex problem of resource allocation for confirmatory research

  4. Assessment of the impacts of the french nuclear program on the environment

    International Nuclear Information System (INIS)

    Naudet, G.

    1991-01-01

    The assessment of the impacts of the French nuclear program on atmosphere pollution is based on a macroeconomic long term model MELODY particularly detailed for the energy sector. The French energy strategy, characterized by its nuclear program, is compared with an alternative coal strategy based on coal-fired power plants. The coal strategy would have entailed different economic performances, a different energy balance, and, consequently, a different quality of air. For instance, by 1990, carbon emissions would have been 60% higher with the coal strategy; actually, they are 27% lower today than their 1973 level. The French nuclear program resulted both in a carbon emission reduction similar to the Toronto Conference target, and in a significant improvement of economic performances. 4 refs.; 10 figs.; 1 tab

  5. Integrated Plant Safety Assessment, Systematic Evaluation Program: Yankee Nuclear Power Station (Docket No. 50-29)

    International Nuclear Information System (INIS)

    1987-10-01

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0825), under the scope of the Systematic Evaluation Program (SEP), for Yankee Atomic Electric Company's Yankee Nuclear Power Station located in Rowe, Massachusetts. The SEP was initiated by the NRC to review the design of older operating nuclear power plants to reconfirm and document their safety. This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Yankee plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when Yankee was licensed, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. 2 tabs

  6. An assessment of design control practices and design reconstitution programs in the nuclear power industry

    International Nuclear Information System (INIS)

    Imbro, E.V.

    1991-02-01

    The US Nuclear Regulatory Commission (NRC) and the utilities have identified shortcomings involving the maintenance of well-defined design bases and the availability of the necessary supporting design documentation. Many utilities have embarked on design-document reconstitution programs although there has been no clear consensus regarding what information should be included in design-bases documents, what is the minimum set of necessary design documents to support the design bases, or how missing or deficient design documentation should be handled. The NRC initiated a survey to ascertain the status of design control programs within the industry and the approaches to design-bases documentation used by some utilities. The survey scope included six utilities and one nuclear steam supply system vendor. Conclusions and observations resulting from the survey assessments are provided so that utilities and the NRC can consider actions to improve these programs. 12 refs

  7. Nuclear criticality safety assessment of the Consolidated Edison Uranium-Solidification Program Facility

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1984-01-01

    A nuclear criticality assessment of the Consolidated Edison Uranium-Solidification Program facility confirms that all operations involved in the process may be conducted with an acceptable margin of subcriticality. Normal operation presents no concern since subcriticality is maintained by design. Several recommendations are presented to prevent, or mitigate the consequences of, any abnormal events that might occur in the various portions of the process. These measures would also serve to reduce to a minimum the administrative controls required to prevent criticality

  8. Assessment of the human resources infrastructure for nuclear energy program in Macedonia

    International Nuclear Information System (INIS)

    Chaushevski, A.; Spasevska, H.; Nikolova-Poceva, S.; Popov, P.

    2015-01-01

    Macedonia is a country with no nuclear power and research reactors. The nuclear application is currently only in the medical industry, agriculture and food industry, accompanied by radiation measuring and protection activities in these sectors. On the other side the energy needs have been increasing in the last ten years, which resulted in electrical energy import of about 20–30% (around 3000 GWh). Nuclear power is one of the options for satisfying energy needs in the next 50 years. One of the crucial problems in nuclear energy implementation are human resources needs and educational infrastructure development in this field. No matter what will be the future energy scenario in the Republic of Macedonia, the nuclear educational program is the first step to have HR in the field of nuclear energy. This paper presents the proposed direction for having HR in nuclear energy program in a small country such as the Republic of Macedonia. Taking into account the existing national education program related to nuclear topics and in particular to nuclear power, and following the guidance and recommendations from the international nuclear educational programs at the IAEA, EHRO and others, the planning of the educational nuclear programs and human resources development in the Republic of Macedonia has been carried out. This includes the enhancing the capabilities of the national regulatory body in the Republic of Macedonia. (authors) Keywords: NEP (Nuclear Energy Program), HR (Human Resources), NEPIO (Nuclear Energy Program Implementation Organization), NRB (Nuclear Regulatory Body), NPP

  9. Assessing the need for a routine monitoring program in three Nuclear Medicine centers in Chile

    International Nuclear Information System (INIS)

    Astudillo, R.; Hermosilla, A.; Diaz-Londono, G.; Garcia, M.

    2015-01-01

    The workers performing different activities with radionuclides in nuclear medicine centers are at potential risk of external exposure and internal contamination. The IAEA Safety Guide No. RS-G-1.2 proposed criteria for determining the need for a routine monitoring program to assess internal contamination. For this purpose, an Excel template containing the IAEA criteria was applied in three nuclear medicine centers in Chile. The results show that it is necessary to carry out a routine monitoring program for five workers who handle 131 I and three for 99m Tc. We propose to implement this template at a national level in order to improve the conditions of radiation protection in the participating centers. (authors)

  10. Development of a seismic damage assessment program for nuclear power plant structures

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Hyun Moo; Cho, Yang Heui; Shin, Hyun Mok [Seoul National Univ., Seoul (Korea, Republic of)] (and others)

    2001-12-15

    The most part of the nuclear power plants operating currently in Korea are more than 20 years old and obviously we cannot pretend that their original performance is actually maintained. In addition, earthquake occurrences show an increasing trend all over the world, and Korea can no more be considered as a zone safe from earthquake. Therefore, need is to guarantee the safety of these power plant structures against seismic accident, to decide to maintain them operational and to obtain data relative to maintenance/repair. Such objectives can be reached by damage assessment using inelastic seismic analysis considering aging degradation. It appears to be more important particularly for the structure enclosing the nuclear reactor that must absolutely protect against any radioactive leakage. Actually, the tendency of the technical world, led by the OECD/NEA, BNL in the United States, CEA in France and IAEA, is to develop researches or programs to assess the seismic safety considering aging degradation of operating nuclear power plants. Regard to the above-mentioned international technical trend, a technology to establish inelastic seismic analysis considering aging degradation so as to assess damage level and seismic safety margin appears to be necessary. Damage assessment and prediction system to grasp in real-time the actual seismic resistance capacity and damage level by 3-dimensional graphic representations are also required.

  11. Development of a seismic damage assessment program for nuclear power plant structures

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Hyun Moo; Cho, Ho Hyun; Cho, Yang Hui [Seoul National Univ., Seoul (Korea, Republic of)] (and others)

    2000-12-15

    Some of nuclear power plants operating currently in Korea have been passed about 20 years after construction. Moreover, in the case of KORI I the service year is over 20 years, so their abilities are different from initial abilities. Also, earthquake outbreak increase, our country is not safe area for earthquake. Therefore, need is to guarantee the safety of these power plant structures against seismic accident, to decide to maintain them operational and to obtain data relative to maintenance/repair. Such objectives can be reached by damage assessment using inelastic seismic analysis considering aging degradation. It appears to be more important particularly for the structure enclosing the nuclear reactor that must absolutely protect against any radioactive leakage. Actually, the tendency of the technical world, led by the OECD/NEA, BNL in the United States, CEA in France and IAEA, is to develop researches or programs to assess the seismic safety considering aging degradation of operating nuclear power plants. Regard to the above-mentioned international technical trend, a technology to establish inelastic seismic analysis considering aging degradation so as to assess damage level and seismic safety margin appears to be necessary. Damage assessment and prediction system to grasp in real-time the actual seismic resistance capacity and damage level by 3-dimensional graphic representations are also required.

  12. Structural aging program to assess the adequacy of critical concrete components in nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.; Marchbanks, M.F.; Oland, C.B.; Arndt, E.G.

    1989-01-01

    The Structural Aging (SAG) Program is carried out by the Oak Ridge National Laboratory (ORNL) under sponsorship of the United States Nuclear Regulatory Commission (USNRC). The Program has evolved from preliminary studies conducted to evaluate the long-term environmental challenges to light-water reactor safety-related concrete civil structures. An important conclusion of these studies was that a damage methodology, which can provide a quantitative measure of a concrete structure's durability with respect to potential future requirements, needs to be developed. Under the SAG Program, this issue is being addressed through: establishment of a structural materials information center, evaluation of structural component assessment and repair technologies, and development of a quantitative methodology for structural aging determinations. Progress to date of each of these activities is presented as well as future plans. 7 refs., 5 figs

  13. Romanian nuclear fuel program

    International Nuclear Information System (INIS)

    Budan, O.

    1999-01-01

    The paper presents and comments the policy adopted in Romania for the production of CANDU-6 nuclear fuel before and after 1990. The CANDU-6 nuclear fuel manufacturing started in Romania in December 1983. Neither AECL nor any Canadian nuclear fuel manufacturer were involved in the Romanian industrial nuclear fuel production before 1990. After January 1990, the new created Romanian Electricity Authority (RENEL) assumed the responsibility for the Romanian Nuclear Power Program. It was RENEL's decision to stop, in June 1990, the nuclear fuel production at the Institute for Nuclear Power Reactors (IRNE) Pitesti. This decision was justified by the Canadian specialists team findings, revealed during a general, but well enough technically founded analysis performed at IRNE in the spring of 1990. All fuel manufactured before June 1990 was quarantined as it was considered of suspect quality. By that time more than 31,000 fuel bundles had already been manufactured. This fuel was stored for subsequent assessment. The paper explains the reasons which provoked this decision. The paper also presents the strategy adopted by RENEL after 1990 regarding the Romanian Nuclear Fuel Program. After a complex program done by Romanian and Canadian partners, in November 1994, AECL issued a temporary certification for the Romanian nuclear fuel plant. During the demonstration manufacturing run, as an essential milestone for the qualification of the Romanian fuel supplier for CANDU-6 reactors, 202 fuel bundles were produced. Of these fuel bundles, 66 were part of the Cernavoda NGS Unit 1 first fuel load (the balance was supplied by Zircatec Precision Industries Inc. ZPI). The industrial nuclear fuel fabrication re-started in Romania in January 1995 under AECL's periodical monitoring. In December 1995, AECL issued a permanent certificate, stating the Romanian nuclear fuel plant as a qualified and authorised CANDU-6 fuel supplier. The re-loading of the Cernavoda NGS Unit 1 started in the middle

  14. Assessment of infrastructure development requirements for embarking on nuclear power program in Macedonia

    International Nuclear Information System (INIS)

    Popov, N.; Ilijovski, I.; Popovski, V.

    2015-01-01

    Over the past decades nuclear energy has been proven as reliable and economical energy supply that is capable of meeting demanding energy market requirements. Many countries around the world consider entering into new nuclear energy programs and building new power reactors for satisfying their increasing electrical energy needs. A nuclear power program is a major undertaking requiring careful planning, preparation and investment, and human resources for building adequate nuclear infrastructure. Preparations for making a decision to enter into a new nuclear energy program requires a significant amount of financial and human resources, time, and assistance from already developed countries and international nuclear organizations. The International Atomic Energy Agency (IAEA) from Vienna provides technical help, financial assistance, and documented knowledge that are important for countries facing the challenge of entering nuclear programs for the first time. The IAEA organizes technical courses and information exchange meetings for new countries at which experiences and lessons learned are provided to new countries. This paper describes the key activities in the process for making a decision to enter a new nuclear energy program. It describes the efforts currently being conducted in the Republic of Macedonia in the direction of collecting information, performing various feasibility studies, and engaging in regional cooperation for utilizing experiences of the regional countries in performing such activities, and in developing their nuclear power programs. This paper also provides an overview of the IAEA documents and recommendations that are relevant for this topic

  15. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume V. Economics and systems analysis

    International Nuclear Information System (INIS)

    1980-06-01

    This NASAP assessment considers the economics of alternative nuclear reactor and fuel-cycle systems in the light of possible patterns of uranium supply and energy demand, as well as the economic implications of improvng the proliferation resistance of the various systems. The assessment focuses on the costs of alternative nuclear technologies and the possible timing of their implementation, based on their economic attractiveness

  16. Ready for nuclear energy?: An assessment of capacities and motivations for launching new national nuclear power programs

    International Nuclear Information System (INIS)

    Jewell, Jessica

    2011-01-01

    The International Atomic Energy Agency reports that as of July 2009 there were 52 countries interested in building their first nuclear power plant. This paper characterizes and evaluates these 'Newcomer Countries' in terms of their capacity and motivations to develop nuclear power. It quantifies factors historically associated with the development of nuclear energy programs and then benchmarks the Newcomers against these data. Countries with established nuclear power programs, particularly where nuclear facilities are privately owned, are typically larger, wealthier and politically stable economies with high government effectiveness. Nuclear power was historically launched during periods of high electricity consumption growth. Other indicators for the potential of nuclear power include: the size of the national grid, the presence of international grid connections and security of fuel supply for electricity production. We identify 10 Newcomers which most closely resemble the Established Nuclear Power Countries and thus are most likely to deploy nuclear energy, 10 countries where the development of nuclear energy is uncertain due to high political instability, 14 countries with lower capacities where pursuing nuclear energy may require especially strong international cooperation and 18 countries where the development of nuclear power is less likely due to their significantly lower capacities and motivations. - Research Highlights: →Historically, nuclear power was used in larger, wealthier, politically stable economies. →Nuclear power was typically launched in periods of high electricity demand growth. →Only 10 out of 52 'Newcomer' countries share similar characteristics. →10 other 'Newcomers' with high motivations and capacities are politically unstable. →Nuclear power would need international help in 14 countries and is unlikely in the rest (18).

  17. Ontario Hydro's nuclear program

    International Nuclear Information System (INIS)

    McCredie, J.

    1984-01-01

    This report briefly describes Ontario Hydro's nuclear program, examining the design and construction status, and the future from Ontario Hydro's perspective. Ontario Hydro relies heavily on nuclear power. Nuclear fuel was responsible for approximately 34% of Ontario Hydro's energy production in 1983. The nuclear proportion was supplied by twelve operating units located: NPD, Douglas Point, Pickering A and B. It is expected that by approximately 1992, 65% of the total energy needs will be generated through nuclear power

  18. Nuclear proliferation and civilian nuclear power: report of the nonproliferation alternative systems assessment program. Volume V. Economics and systems analysis

    International Nuclear Information System (INIS)

    1979-12-01

    This NASAP assessment considers the economics of alternative nuclear reactor and fuel-cycle systems in the light of possible patterns of uranium supply and energy demand, as well as the economic implications of improving the proliferation resistance of the various systems. The assessment focuses on the costs of alternative nuclear technologies and the possible timing of their implementation, based on their economic attractiveness. The objectives of this assessment are to identify when economic incentives to deploy advanced nuclear power systems might exist, to estimate the costs of using technologies that would reduce the risk of proliferation, to assess the impact of major economic uncertainties on the transition to new technologies, and to compare the investments required for alternative systems

  19. IAEA nuclear security program

    Energy Technology Data Exchange (ETDEWEB)

    Ek, D. [International Atomic Energy Agency, Vienna (Austria)

    2006-07-01

    Although nuclear security is a State responsibility, it is nevertheless an international concern, as the consequences of a nuclear security incident would have worldwide impact. These concerns have resulted in the development of numerous international instruments on nuclear security since the terrorist events in the USA on September 11, 2001. The IAEA Office of Nuclear Security has been charged to assist Member States to improvement their nuclear security and to meet the intent of these international obligations in order to ensure a cohesive thread of nuclear security protects the global community. The programs underway and planned by the Office of Nuclear Security will be discussed in this paper. (author)

  20. IAEA nuclear security program

    International Nuclear Information System (INIS)

    Ek, D.

    2006-01-01

    Although nuclear security is a State responsibility, it is nevertheless an international concern, as the consequences of a nuclear security incident would have worldwide impact. These concerns have resulted in the development of numerous international instruments on nuclear security since the terrorist events in the USA on September 11, 2001. The IAEA Office of Nuclear Security has been charged to assist Member States to improvement their nuclear security and to meet the intent of these international obligations in order to ensure a cohesive thread of nuclear security protects the global community. The programs underway and planned by the Office of Nuclear Security will be discussed in this paper. (author)

  1. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VII. International perspectives

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    The purpose of this volume is to assess the proliferation vulnerabilities of the present deployment of civilian nuclear-power systems within the current nonproliferation regime and, in light of their prospective deployment, to consider technical and institutional measures and alternatives which may contribute to an improved regime in which nuclear power could play a significant part. An assessment of these measures must include consideration of their nonproliferation effectiveness as well as their bearing upon energy security, and their operational, economic, and political implications. The nature of these considerations can provide some measure of their likely acceptability to various nations.

  2. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VII. International perspectives

    International Nuclear Information System (INIS)

    1980-06-01

    The purpose of this volume is to assess the proliferation vulnerabilities of the present deployment of civilian nuclear-power systems within the current nonproliferation regime and, in light of their prospective deployment, to consider technical and institutional measures and alternatives which may contribute to an improved regime in which nuclear power could play a significant part. An assessment of these measures must include consideration of their nonproliferation effectiveness as well as their bearing upon energy security, and their operational, economic, and political implications. The nature of these considerations can provide some measure of their likely acceptability to various nations

  3. Participation of ARN (Autoridad Regulatoria Nuclear) Argentina in the quality assessment program, EML-USDOE since 2002-2004

    International Nuclear Information System (INIS)

    Equillor, Hugo E.; Serdeiro, Nelida H.; Fernandez, Jorge A.; Gavini, Ricardo M.; Grinman, Ana. D. R.; Lewis, Esther C.; Palacios, Miguel A.

    2004-01-01

    In this report, the results corresponding to five consecutive exercises (period 2002-2004) obtained by the Autoridad Regulatoria Nuclear (ARN) in alpha, beta and gamma measurements, on four different matrixes, within the framework of Environmental Measurements Laboratory (EML) Quality Assessment Program (QAP) of the United States, are presented. (author)

  4. Vinca nuclear decommissioning program

    International Nuclear Information System (INIS)

    Pesic, M.; Subotic, K.; Sotic, O.; Plecas, I.; Ljubenov, V.; Peric, A.

    2002-01-01

    In this paper a preliminary program for the nuclear decommissioning in The Vinca Institute of Nuclear Sciences is presented. Proposed Projects and Activities, planned to be done in the next 10 years within the frames of the Program, should improve nuclear and radiation safety and should solve the main problems that have arisen in the previous period. Project of removal of irradiated spent nuclear fuel from the RA reactor, as a first step in all possible decommissioning strategies and the main activity in the first two-three years of the Program realization, is considered in more details. (author)

  5. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

    International Nuclear Information System (INIS)

    1980-06-01

    This volume of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power - generating capability and one without

  6. Assessment of the facilities on Jackass Flats and other Nevada Test Site facilities for the new nuclear rocket program

    International Nuclear Information System (INIS)

    Chandler, G.; Collins, D.; Dye, K.; Eberhart, C.; Hynes, M.; Kovach, R.; Ortiz, R.; Perea, J.; Sherman, D.

    1992-01-01

    Recent NASA/DOE studies for the Space Exploration Initiative have demonstrated a critical need for the ground-based testing of nuclear rocket engines. Experience in the ROVER/NERVA Program, experience in the Nuclear Weapons Testing Program, and involvement in the new nuclear rocket program has motivated our detailed assessment of the facilities used for the ROVER/NERVA Program and other facilities located at the Nevada Test Site (NTS). The ROVER/NERVA facilities are located in the Nevada Research L, Development Area (NRDA) on Jackass Flats at NTS, approximately 85 miles northwest of Las Vegas. To guide our assessment of facilities for an engine testing program we have defined a program goal, scope, and process. To execute this program scope and process will require ten facilities. We considered the use of all relevant facilities at NTS including existing and new tunnels as well as the facilities at NRDA. Aside from the facilities located at remote sites and the inter-site transportation system, all of the required facilities are available at NRDA. In particular we have studied the refurbishment of E-MAD, ETS-1, R-MAD, and the interconnecting railroad. The total cost for such a refurbishment we estimate to be about $253M which includes additional contractor fees related to indirect, construction management, profit, contingency, and management reserves. This figure also includes the cost of the required NEPA, safety, and security documentation

  7. Comprehensive vibration assessment program for Yonggwang nuclear power plant unit 4

    International Nuclear Information System (INIS)

    Rhee, Hui Nam; Hwang, Jong Keun; Kim, Tae Hyung; Kim, Jung Kyu; Song, Heuy Gap; Kim, Beom Shig

    1995-01-01

    A Comprehensive Vibration Assessment Program (CVAP) has been performed for Yonggwang Nuclear Power Plant Unit 4 (YGN 4) in order to verify the structural integrity of the reactor internals for flow induced vibrations prior to commercial operation. The theoretical evidence for the structural integrity of the reactor internals and the basis for measurement and inspection are provided by the analysis. Flow induced hydraulic loads and reactor internals vibration response data were measured during pre-core hot functional testing in YGN 4 site. Also, the critical areas in the reactor internals were inspected visually to check any existence of structural abnormality before and after the pre-core hot functional testing. Then, the measured data have been analyzed and compared with the predicted data by analysis. The measured stresses are less than the predicted values and the allowable limits. It is concluded that the vibration response of the reactor internals due to the flow induced vibration under normal operation is acceptable for long term operation

  8. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume VII. International perspectives

    International Nuclear Information System (INIS)

    1979-12-01

    The purpose of this volume is to assess the proliferation vulnerabilities of the present deployment of civilian nuclear-power systems within the current nonproliferation regime and, in light of their prospective deployment, to consider technical and institutional measures and alternatives which may contribute to an improved regime in which nuclear power could play a significant part. An assessment of these measures must include consideration of their nonproliferation effectiveness as well as their bearing upon energy security, and their operational, economic, and political implications. The nature of these considerations can provide some measure of their likely acceptability to various nations. While any final assessment of such measures and alternatives would have to examine the circumstances particular to each nation, it is hoped that the more generic assessments conducted here will be useful in suggesting guidelines for developing an improved nonproliferation regime which also helps to meet nuclear-energy needs. One chapter outlines the existing nonproliferation regime, including the Treaty for the Non-Proliferation of Nuclear Weapons (NPT), International Atomic Energy Agency (IAEA) safeguards, bilateral and multilateral requirements for agreements of cooperation and transfers of technology, and existing provisons for sanctions for violation of nonproliferation commitments. The chapter then proceeds to an assessment of various alternatives for providing assurance of fuel supply in light of this current regime. Another chapter examines a set of technical and institutional measures and alternatives for various components of once-through and closed fuel cycles. The components of the once-through fuel cycle assessed are enrichment services and spent-fuel management; the components of closed fuel cycles assessed are reprocessing and plutonium management and fast-breeder reactor (FBR) deployment

  9. Argonne Nuclear Data Program

    Energy Technology Data Exchange (ETDEWEB)

    Kondev, F. [US Nuclear Data Program, U.S. DOE/SC (United States)

    2013-08-15

    Nuclear Data Compilations and Evaluations: - Nuclear structure and decay data compilations and evaluations for the International NSDD network (ENSDF and XUNDL); - AME12 and NuBase12 - in collaboration with G. Audi and M. MacCormick, CSNSM (Orsay), M. Wang, IMP (Lanzhou) and B. Pfeiffer, GSI (Darmstadt) - presentation by M. Wang; - DDEP coordinator - completed; - Horizontal nuclear data evaluation activities -IAEA CRP's, Isomers, Medical Isotopes; Complementary ND research Activities: - CARIBU, FRIB and other RIB facilities, Gretina, IAEA-CRP - emphasis on nuclear structure physics and astrophysics, and their intersection with applied nuclear physics programs.

  10. Argentine nuclear program

    International Nuclear Information System (INIS)

    Leibovich, H.; Takacs, E.A.

    1983-01-01

    The paper describes Argentina's nuclear program, detailing its objectives, the schedule of construction of nuclear plants and local production of required equipment. The technologies adopted so far, the local industrial and engineering participation, the preliminary study for the construction of the next power station and Argentina's nonproliferation nuclear policy are analyzed. Argentina's point of view on Canadian nonproliferation policy and CANDU reactor export is discussed

  11. National nuclear scientific program

    International Nuclear Information System (INIS)

    Plecas, I.; Matausek, M.V.; Neskovic, N.

    2001-01-01

    National scientific program of the Vinca Institute Nuclear Reactors And Radioactive Waste comprises research and development in the following fields: application of energy of nuclear fission, application of neutron beams, analyses of nuclear safety and radiation protection. In the first phase preparatory activities, conceptual design and design of certain processes and facilities should be accomplished. In the second phase realization of the projects is expected. (author)

  12. Nuclear Regulatory Commission probabilistic risk assessment implementation program: A status report

    International Nuclear Information System (INIS)

    Rubin, M.P.; Caruso, M.A.

    1996-01-01

    The US Nuclear Regulatory Commission (NRC) is undertaking a number of activities intended to increase the consideration of risk significance in its decision processes and the effective use of risk-based technologies in its regulatory activities. Although the NRC is moving toward risk-informed regulation throughout its areas of responsibilities, this paper focuses primarily on those issues associated with reactor regulation. As the NRC completed significant milestones in its development of probabilistic risk assessment (PRA) methodology and gained considerable experience in the limited application of risk assessment to selected regulatory activities, it became evident that a much broader use of risk informed approaches offered advantages to both the NRC and the US commercial nuclear industry. This desire to enhance the use of risk assessment is driven by the clear belief that application of PRA methods will result in direct improvements in nuclear power plant operational safety from the perspective of both the regulator and the plant operator. The NRC believed that an overall policy on the use of PRA methods in nuclear regulatory activities should be established so that the many potential applications of PRA could be implemented in a consistent and predictable manner that would promote regulatory stability and efficiency. This paper describes the key activities that the NRC has undertaken to implement the initial stages of an integrated risk-informed regulatory framework

  13. Nuclear physics program plan

    International Nuclear Information System (INIS)

    1985-11-01

    The nuclear physics program objectives, resources, applications and implications of scientific opportunities are presented. The scope of projected research is discussed in conjunction with accelerator facilities and manpower. 25 figs., 2 tabs

  14. Iran's Nuclear Program: Status

    National Research Council Canada - National Science Library

    Kerr, Paul K

    2008-01-01

    .... Indeed, the UN Security Council has responded to Iran's refusal to suspend work on its uranium enrichment and heavy-water nuclear reactor programs by adopting several resolutions, most recently...

  15. Iran's Nuclear Program: Status

    National Research Council Canada - National Science Library

    Kerr, Paul K

    2008-01-01

    .... Indeed, the UN Security Council has responded to Iran's refusal to suspend work on its uranium enrichment and heavy-water nuclear reactor programs by adopting several resolutions which imposed sanctions on Tehran...

  16. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

    International Nuclear Information System (INIS)

    1979-12-01

    Volume 6 of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power-generating capability and one without. This volume also provides estimates of the time required for development of large-scale commercial reactor systems to reach the construction permit application stage and for fuel-cycle facilities to reach the operating license application stage, which is a measure of the relative technical status of alternative nuclear systems

  17. Overview of the U.S. Nuclear Regulatory Commission collaborative research program to assess tsunami hazard for nuclear power plants on the Atlantic and Gulf Coasts

    Science.gov (United States)

    Kammerer, A.M.; ten Brink, Uri S.; Titov, V.V.

    2017-01-01

    In response to the 2004 Indian Ocean Tsunami, the United States Nuclear Regulatory Commission (US NRC) initiated a long-term research program to improve understanding of tsunami hazard levels for nuclear facilities in the United States. For this effort, the US NRC organized a collaborative research program with the United States Geological Survey (USGS) and the National Oceanic and Atmospheric Administration (NOAA) with a goal of assessing tsunami hazard on the Atlantic and Gulf Coasts of the United States. Necessarily, the US NRC research program includes both seismic- and landslide-based tsunamigenic sources in both the near and the far fields. The inclusion of tsunamigenic landslides, an important category of sources that impact tsunami hazard levels for the Atlantic and Gulf Coasts is a key difference between this program and most other tsunami hazard assessment programs. The initial phase of this work consisted of collection, interpretation, and analysis of available offshore data, with significant effort focused on characterizing offshore near-field landslides and analyzing their tsunamigenic potential and properties. In the next phase of research, additional field investigations will be conducted in key locations of interest and additional analysis will be undertaken. Simultaneously, the MOST tsunami generation and propagation model used by NOAA will first be enhanced to include landslide-based initiation mechanisms and then will be used to investigate the impact of the tsunamigenic sources identified and characterized by the USGS. The potential for probabilistic tsunami hazard assessment will also be explore in the final phases of the program.

  18. An alternative nuclear program

    International Nuclear Information System (INIS)

    Goldemberg, J.

    1981-01-01

    An analysis of the development of nuclear energy in Brazil is made since its beginning, showing the fundamental policy changes introduced in the end of the 60's with the purchase of the Angra dos Reis I reactor. This decision discouraged the existing efforts of an autonomous development in nuclear energy. The reaction to this policy led to the Nuclear Deal with Germany, which although incorporating some positive aspects is nor capable to lead to nuclear independence. The presently existing options are discussed, as well as the transformation of the Nuclear Program in a R and D Program based only in the reactors I, II and III, located in Angra dos Reis. (Author) [pt

  19. Alternative Nuclear Program

    International Nuclear Information System (INIS)

    Goldemberg, J.

    1982-01-01

    An analysis of the development of nuclear energy in Brazil is made since its beginning, showing the fundamental policy changes introduced in the end of the 60's with the purchase of the Angra dos Reis I reactor. This decision discouraged the existing efforts of an autonomous development in nuclear energy. The reaction to this policy led to the Nuclear Deal with Germany, which although incorporating some positive aspects is not capable to lead to nuclear independence. The presently existing options are discussed, as well as the transformation of the Nuclear Program in a R and D Program based only in the reactors I, II and III, located in Angra dos Reis. (Author) [pt

  20. India's nuclear program

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    India made an early commitment to being as self-sufficient as possible in nuclear energy and has largely achieved that goal. The country operates eight nuclear reactors with a total capacity of 1,304 MWe, and it remains committed to an aggressive growth plan for its nuclear industry, with six reactors currently under construction, and as many as twelve more planned. India also operates several heavy water production facilities, fabrication facilities, reprocessing works, and uranium mines and mills. Due to India's decision not to sign the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), the country has had to develop nearly all of its nuclear industry and infrastructure domestically. Overall, India's nuclear power program is self-contained and well integrated, with plans to expand to provide up to ten percent of the country's electrical generating capacity

  1. LISA. A code for safety assessment in nuclear waste disposals program description and user guide

    International Nuclear Information System (INIS)

    Saltelli, A.; Bertozzi, G.; Stanners, D.A.

    1984-01-01

    The code LISA (Long term Isolation Safety Assessment), developed at the Joint Research Centre, Ispra is a useful tool in the analysis of the hazard due to the disposal of nuclear waste in geological formations. The risk linked to preestablished release scenarios is assessed by the code in terms of dose rate to a maximum exposed individual. The various submodels in the code simulate the system of barriers -both natural and man made- which are interposed between the contaminants and man. After a description of the code features a guide for the user is supplied and then a test case is presented

  2. Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

    International Nuclear Information System (INIS)

    1987-04-01

    The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

  3. Program to develop analytical tools for environmental and safety assessment of nuclear material shipping container systems

    International Nuclear Information System (INIS)

    Butler, T.A.

    1978-11-01

    This paper describes a program for developing analytical techniques to evaluate the response of nuclear material shipping containers to severe accidents. Both lumped-mass and finite element techniques are employed to predict shipping container and shipping container-carrier response to impact. The general impact problem is computationally expensive because of its nonlinear, three-dimensional nature. This expense is minimized by using approximate models to parametrically identify critical cases before more exact analyses are performed. The computer codes developed for solving the problem are being experimentally substantiated with test data from full-scale and scale-model container drop tests. 6 figures, 1 table

  4. Integrated-plant-safety assessment Systematic Evaluation program. Millstone Nuclear Power Station, Unit 1, Northeast Nuclear Energy Company, Docket No. 50-245

    International Nuclear Information System (INIS)

    1982-11-01

    The Systematic Evaluation Program was initiated in February 1977 to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Millstone Nuclear Power Station, Unit 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit 1, is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  5. The Chinese nuclear program

    International Nuclear Information System (INIS)

    Prenez, J.C.; Bettoun, G.

    2009-01-01

    This series of slides presents the organization of the Chinese nuclear industry and its perspectives for the 2 next decades. The presentation is divided into 5 parts. Part one: the energy sector in China. Due to the economic development of the country this sector is flourishing and reaches an average growth rate of 9% per year. More than fifty per cent of the power plants being built in the world, are located in China. The electricity production stems by far from fossil energies (>80%) but this part is expected to decrease to reach 70% in 2020. Part 2: the Chinese nuclear program. This program is dual: the massive deployment of chinese improved reactors of second generation (the construction of 6 CPR1000 reactors will be launched each year) and the import and assimilation of reactors of the third generation: 4 AP1000 and 2 EPR are being built. Part 3: the organization of the Chinese nuclear sector. The main actors are CNNC (China National Nuclear Corporation), CGNPC (China Guangdong Nuclear Power Corporation), CPI (China Power Investment Corporation), SNPTC (State Nuclear Power Technology Corporation). The main 5 Chinese suppliers are also presented. Part 4: The role of EDF. Today's EDF role is multiple: to be active in the Chinese nuclear program, to go beyond technical assistance to reach partnership, to invest in Chinese power plants, to promote cooperation between French and Chinese actors of the nuclear industry. A lot of joint ventures have been created. Part 5: the Taishan project. Taishan is a coastal site near Macao in the Guangdong province in which 2 EPR are being built, the first concrete was cast in october 2009, 52 months of construction are scheduled and the first unit will be commissioned in end 2013 while the second commissioning is planned for end 2014. (A.C.)

  6. Nuclear program review

    International Nuclear Information System (INIS)

    Brito, S.; Rosa, L.P.; Carvalho, Joaquim de; Simon, D.N.

    1985-01-01

    A review of the Brazilian Nuclear Program based in Brazilian energy perspectives, in world-wide technology evolution and in international and national economic context is done. The objetive is look for subsidies for new decisions related to the future of program, taking in account the acquired experience and new data created by evolution of internal and external political and technological conjuncture. (M.C.K.) [pt

  7. Nuclear energy research initiative, an overview of the cooperative program for the risk-informed assessment of regulatory and design requirements for future nuclear power plants

    International Nuclear Information System (INIS)

    Ritterbusch, Stanley E.

    2000-01-01

    EPRI sstudies have shown that nuclear plant capital costs will have to decrease by about 35% to 40% to be competitive with fossil-generated electricity in the Unite States. Also, the ''first concrete'' to fuel load construction schedule will have to be decreased to less than 40 months. Therefore, the U. S. Department of Energy (DOE) initiate the Nuclear Energy Research Initiative (NERI) and ABB CENP proposed a cooperative program with Sandia National Laboratory (SNL) and Duke Engineering and Services (DE and S) to begin an innovative research effort to drastically cut the cost of new nuclear power plant construction for the U. S. de-regulated market place. This program was approved by the DOE through three separate but coordinated ''cooperative agreements.'' They are the ''Risk-Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants'' (Risk-Informed NPP), the ''Smart Nuclear Power Plant Program'' (Smart-NPP), and ''Design, Procure, Construct, Install and Test'' (DPCIT) Program. DOE funded the three cooperative agreements at a level of $2.6 million for the first year of the program. Funding for the complete program is durrently at a level $6.9 million, however, ABB CENP and all partners anticipate that the scope of the NERI program will be increased as a result of the overall importance of NERI to the U. S. Government. The Risk-Informed NPP program, which is aimed at revising costly regularory and design requirements without reducing overall plant safety, has two basic tasks: ''development of Risk-Informed Methods'' and ''strengthening the Reliability Database.'' The overall objective of the first task is to develop a scientific, risk-informed approach for identifying and simplifying deterministic industry standards, regulatory requirements, and safety systems that do not significantly contribute to nuclear power plant reliability and safety. The second basic task is to develop a means for strengthening the reliability database

  8. Ontario Hydro's nuclear program

    International Nuclear Information System (INIS)

    Jackson, H.A.

    1982-06-01

    In 1981 Ontario Hydro generated over 100 billion KWh of electrical energy. Approximately one third of this was from nuclear units. There are ten CANDU units (5 250 MW) currently in operation, and another twelve (8 600 MW) are under construction. The presently committed nuclear expansion program is estimated to involve expenditures of 16 billion dollars over the next 10 years. About 10 000 people are employed in the nuclear design and construction program. All projects are generally on schedule, with the stations coming into service during the following time periods: Pickering B, 1983-85; Bruce B, 1984-87; Darlington, 1988-90. The status of each project is reviewed. Planning is underway for some retubing projects, as early as 1985 for Pickering A

  9. Integrated plant safety assessment: systematic evaluation program. Oyster Creek nuclear generating station. GPU Nuclear Corporation and Jersey Central Power and Light Company. Docket No. 50-219

    International Nuclear Information System (INIS)

    1982-09-01

    The Systematic Evaluation Program was initiated in February 1978 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Oyster Creek Nuclear Generating Station (located in Ocean County, New Jersey), one of ten plants reviewed under Phase II of this program, and indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  10. Defining the "proven technology" technical criterion in the reactor technology assessment for Malaysia's nuclear power program

    Science.gov (United States)

    Anuar, Nuraslinda; Kahar, Wan Shakirah Wan Abdul; Manan, Jamal Abdul Nasir Abd

    2015-04-01

    Developing countries that are considering the deployment of nuclear power plants (NPPs) in the near future need to perform reactor technology assessment (RTA) in order to select the most suitable reactor design. The International Atomic Energy Agency (IAEA) reported in the Common User Considerations (CUC) document that "proven technology" is one of the most important technical criteria for newcomer countries in performing the RTA. The qualitative description of five desired features for "proven technology" is relatively broad and only provides a general guideline to its characterization. This paper proposes a methodology to define the "proven technology" term according to a specific country's requirements using a three-stage evaluation process. The first evaluation stage screens the available technologies in the market against a predefined minimum Technology Readiness Level (TRL) derived as a condition based on national needs and policy objectives. The result is a list of technology options, which are then assessed in the second evaluation stage against quantitative definitions of CUC desired features for proven technology. The potential technology candidates produced from this evaluation is further narrowed down to obtain a list of proven technology candidates by assessing them against selected risk criteria and the established maximum allowable total score using a scoring matrix. The outcome of this methodology is the proven technology candidates selected using an accurate definition of "proven technology" that fulfills the policy objectives, national needs and risk, and country-specific CUC desired features of the country that performs this assessment. A simplified assessment for Malaysia is carried out to demonstrate and suggest the use of the proposed methodology. In this exercise, ABWR, AP1000, APR1400 and EPR designs assumed the top-ranks of proven technology candidates according to Malaysia's definition of "proven technology".

  11. The structural aging assessment program: ranking methodology for CANDU nuclear generating station concrete components

    International Nuclear Information System (INIS)

    Philipose, K.E.; Muhkerjee, P.K.; McColm, E.J.

    1997-01-01

    Most of the major structural components in CANDU nuclear generating stations are constructed of reinforced concrete. Although passive in nature, these structures perform many critical safety functions in the operation of each facility. Aging can affect the structural capacity and integrity of structures. The reduction in capacity due to aging is not addressed in design codes. Thus a program is warranted to monitor the aging of safety-related CANDU plant structures and to prioritize those that require maintenance and repairs. Prioritization of monitoring efforts is best accomplished by focusing on those structures judged to be the most critical to plant performance and safety. The safety significance of each sub-element and its degradation with time can be evaluated using a numerical rating system. This will simplify the utility's efforts, thereby saving maintenance costs while providing a higher degree of assurance that performance is maintained. This paper describes the development of a rating system (ranking procedure) as part of the Plant Life Management of CANDU generating station concrete structures and illustrates its application to an operating plant. (author)

  12. Nuclear plant aging research program

    International Nuclear Information System (INIS)

    Eissenberg, D.M.

    1987-01-01

    The U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, has established the Nuclear Plant Aging Research (NPAR) program in its Division of Engineering Technology. Principal contractors for this program include Oak Ridge National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, and Pacific Northwest Laboratory. The program goals are: to identify and characterize time-dependent degradation (aging) of nuclear plant safety-related electrical and mechanical components which could lead to loss of safety function; to identify and recommend methods for detecting and trending aging effects prior to loss of safety function so that timely maintenance can be implemented; and to recommend maintenance practices for mitigating the effects of aging. Research activities include prioritization of system and component aging in nuclear plants, characterization of aging degradation of specific components including identification of functional indicators useful for trending degradation, and testing of practical methods and devices for measuring the functional indicators. Aging assessments have been completed on electric motors, snubbers, motor-operated valves, and check valves. Testing of trending methods and devices for motor-operated valves and check valves is in progress

  13. Integrated plant safety assessment, Systematic Evaluation Program: Dresden Nuclear Power Station, Unit 2 (Docket No. 50-237)

    International Nuclear Information System (INIS)

    1989-10-01

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0823), under the scope of the Systematic Evaluation Program (SEP), for the Commonwealth Edison Company (CECo) Dresden Nuclear Power Station, Unit 2 located in Grundy County, Illinois. The NRC initiated the SEP to provide the framework for reviewing the design of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review completed by means of the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations subsequent to issuing the final IPSAR for Dresden Unit 2. The review was provided for (1) an assessment of the significance of differences between current technical positions on selected issues and those that existed when Dresden Unit 2 was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. The final IPSAR and this supplement forms part of the bases for considering the conversion of the existing provisional operating license to a full-term operating license. 83 refs., 9 tabs

  14. The Korean nuclear power program

    International Nuclear Information System (INIS)

    Choi, Chang Tong

    1996-01-01

    Although the world nuclear power industry may appear to be in decline, continued nuclear power demand in Korea indicates future opportunities for growth and prosperity in this country. Korea has one of the world's most vigorous nuclear power programs. Korea has been an active promoter of nuclear power generation since 1978, when the country introduced nuclear power as a source of electricity. Korea now takes pride in the outstanding performance of its nuclear power plants, and has established a grand nuclear power scheme. This paper is aimed at introducing the nuclear power program of Korea, including technological development, international cooperation, and CANDU status in Korea. (author). 2 tabs

  15. National nuclear program

    International Nuclear Information System (INIS)

    Costa A, D.

    1980-01-01

    The basic concepts of the Nuclear program that Mexico plans are presented, to develop pointing out that it constitutes an outstanding event within the history of the country, that will result in an equilibrated profit of the resources of oil exploitation consolidating each step of its technical evolution; all of this represents a challenge since it establishes a qualitative transformation in the very roots of the National economy. Being certain that oil is a non renovable natural resource, the author points out that Mexican Government has emphasized the promotion of the research of alternate resource of energy in the future. According to this panorama, the quidelines that Mexico must undertake regarding production, distribution and consumption of nuclear energy, will point primarily to a global program, which will avoid the imports of equipment and technicians, to achieve maximum advantages for the Country. It stresses the fact that this program cannot start from zero; since first, Mexico, has to import foreign technology, which once assimilated, will give to the Mexican technicians the starting point to establish the proper solution to the foreseen objectives. Therefore, any kind of International cooperation must tend to accelerate the nuclear development and to obtain the transference to technology, within a frame of respect to Mexican sovereignity. The conclusion is that the task at which Mexico aims must be based on the existing human potentiality and on the one that will be prepared in the future, and also on the knowledge and adequate exploitation of the uranium reserves, having the ININ a prominent role of creating the necessary human infrastructure, the development of a Mexican nuclear energy can be achieved in a medium term. (author)

  16. Nuclear Technology Programs

    International Nuclear Information System (INIS)

    Harmon, J.E.

    1990-10-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R ampersand D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product 99 Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories

  17. Nuclear Technology Programs

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, J.E. (ed.)

    1990-10-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

  18. Nuclear technology programs

    International Nuclear Information System (INIS)

    Harmon, J.E.

    1992-01-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1989--March 1990. These programs involve R ampersand D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned water waste stream generated in production of 2,4,6-trinitrotoluene. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories

  19. The program system UFOMOD for assessing the consequences of nuclear accidents

    International Nuclear Information System (INIS)

    Ehrhardt, J.; Burkart, K.; Hasemann, I.; Matzerath, C.; Panitz, H.J.; Steinhauer, C.

    1988-10-01

    The programm system UFOMOD is a completely new accident consequence assessment (ACA) code. Its structure and modelling is based on the experience gained from applications of the old UFOMOD code during and after the German Risk Study - Phase A, the results of scientific investigations performed within the ongoing Phase B and the CEC-project MARIA, and the requirements resulting from the extended use of ACAs to help in decision-making. One of the most important improvements is the introduction of different trajecotry models for describing atmospheric dispersion in the near range and at larger distances. Emergency actions and countermeasures modelling takes into account recommendations of international commissions. The dosimetric models contain completely new age-, sex- and time-dependent data of dose-conversion factors for external and internal radiation; the ingestion pathway is modelled to consider seasonal dependencies. New dose-risk-relationships for stochastic and non-stochastic health effects are implemented; a special algorithm developed for ACA codes allows individual and collective leukemia and cancer risks to be presented as a function of time after the accident. According to the modular structure of the new program system UFOMOD, an easy access to parameter values and the results of the various submodels exists what facilitates sensitivity and uncertainty analyses. (orig.) [de

  20. National Peer Reviews. Self-assessment programs of German nuclear power plants

    International Nuclear Information System (INIS)

    Grauf, E.

    2000-01-01

    Preliminary experience seems to indicate that the concept of national peer reviews is a useful tool capable of improving and harmonizing the standards of operation in German plants. However, a final evaluation is possible only after completion of the program, i.e. probably by the end 2000. The internal national peer reviews do not replace existing reviews, such as the WANO peer reviews or the IAEA OSART missions, but rather supplement them. As a major element of self-assessment, they mainly serve to exchange effectively among German plants know-how and experience, to harmonize standards of plant operation, eliminate any weak spots identified, and generally counteract blindness to one's own faults. Whether the envisaged objective of standardized plant operations will be achieved in the end depends very much on the way in which the results of the reviews will be handled. In particular, it will be interesting to see to what extent there is willingness to take on board any recommendations and proposals made and/or introduce what is called good operating practice. (orig.) [de

  1. Thai Nuclear Power Program

    International Nuclear Information System (INIS)

    Namwong, Ratanachai

    2011-01-01

    The Electricity Generating Authority of Thailand (EGAT), the main power producer in Thailand, was first interested in nuclear power as an electricity option in 1967 when the electricity demand increased considerably for the first time as a result of the economic and industrial growth. Its viability had been assessed several times during the early seventies in relation to the changing factors. Finally in the late 1970s, the proceeding with nuclear option was suspended for a variety of reasons, for instance, public opposition, economic repercussion and the uncovering of the indigenous petroleum resources. Nonetheless, EGAT continued to maintain a core of nuclear expertise. During 1980s, faced with dwindling indigenous fossil fuel resources and restrictions on the use of further hydro as an energy source, EGAT had essentially reconsidered introducing nuclear power plants to provide a significant fraction to the long term future electricity demand. The studies on feasibility, siting and environmental impacts were conducted. However, the project was never implemented due to economics crisis in 1999 and strong opposition by environmentalists and activists groups. The 1986 Chernobyl disaster was an important cause. After a long dormant period, the nuclear power is now reviewed as one part of the solution for future energy supply in the country. Thailand currently relies on natural gas for 70 percent of its electricity, with the rest coming from oil, coal and hydro-power. One-third of the natural gas consumed in Thailand is imported, mainly from neighbouring Myanmar. According to Power Development Plan (PDP) 2007 rev.2, the total installed electricity capacity will increase from 28,530.3 MW in 2007 to 44,281 MW by the end of plan in 2021. Significantly increasing energy demand, concerns over climate change and dependence on overseas supplies of fossil fuels, all turn out in a favor of nuclear power. Under the current PDP (as revised in 2009), two 1,000- megawatt nuclear

  2. The Brazilian Nuclear Energy Program

    International Nuclear Information System (INIS)

    Carvalho, H.G. de

    1980-01-01

    A survey is initially of the international-and national situation regarding energetic resources. The Brazilian Nuclear Energy Policy and the Brazilian Nuclear Program are dealt with, as well as the Nuclear Cooperation agreement signed with the Federal Republic of Germany. The situation of Brazil regarding Uranium and the main activities of the Brazilian Nuclear Energy Commission are also discussed [pt

  3. NRC performance assessment program

    International Nuclear Information System (INIS)

    Coplan, S.M.

    1986-01-01

    The U.S. Nuclear Regulatory Commission's (NRC) performance assessment program includes the development of guidance to the U.S. Department of Energy (DOE) on preparation of a license application and on conducting the studies to support a license application. The nature of the licensing requirements of 10 CFR Part 60 create a need for performance assessments by the DOE. The NRC and DOE staffs each have specific roles in assuring the adequacy of those assessments. Performance allocation is an approach for determining what testing and analysis will be needed during site characterization to assure that an adequate data base is available to support the necessary performance assessments. From the standpoint of establishing is implementable methodology, the most challenging performance assessment needed for licensing is the one that will be used to determine compliance with the U.S. Environmental Protection Agency's (EPA) containment requirement

  4. Development of Internal Dose Assessment Program for Nuclear Power Plant Employees

    Energy Technology Data Exchange (ETDEWEB)

    Song, Myung Jae; Kang, Duck Won; Maeng, Sung Jun; Kim, Hee Geun; Son, Soon Whan; Lim, Young Kee; Son, Joong Kwon; Park, Keyoung Rock [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jang, See Young; Ha, Jong Woo; Suh, Keyoung Won [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Oh, Oak Doo; Lee, Joong Woo; Yoon, Sung Sik [Yonsei University, Seoul (Korea, Republic of)

    1996-12-31

    Internal exposure monitoring based on new concept of radiation protection. Analysis and Performance test of the in vivo systems being operated in nuclear power plants in Korea. Design and fabrication of humanoid phantom for calibration of in vivo system. Development of internal dose evaluation code based on the ICRP 30 dosimetric model. (author). 44 refs., figs.

  5. METHUSELAH II - A Fortran program and nuclear data library for the physics assessment of liquid-moderated reactors

    International Nuclear Information System (INIS)

    Brinkworth, M.J.; Griffiths, J.A.

    1966-03-01

    METHUSELAH II is a Fortran program with a nuclear data library, used to calculate cell reactivity and burn-up in liquid-moderated reactors. It has been developed from METHUSELAH I by revising the nuclear data library, and by introducing into the program improvements relating to nuclear data, improvements in efficiency and accuracy, and additional facilities which include a neutron balance edit, specialised outputs, fuel cycling, and fuel costing. These developments are described and information is given on the coding and usage of versions of METHUSELAH II for the IBM 7030 (STRETCH), IBM 7090, and KDF9 computers. (author)

  6. Participation of the ARN (Autoridad Regulatoria Nuclear) in the quality assessment program of the EML-USDOE

    International Nuclear Information System (INIS)

    Bonino, N.O.; Equillor, H.E.; Fernandez, J.A.; Gavini, R.M.; Grinman, A.D.R.; Serdeiro, N.H.; Lewis, E.C.; Bomben, A.M.; Diodati, J.M.

    1998-01-01

    Full text: A radiochemical laboratory must count with optimized analytical techniques and calibrated measurement systems in order to get reliable results. In addition to the internal controls that each laboratory must carry out, it is indispensable to include in the quality assurance programs, intercomparisons with qualified laboratories. The Nuclear Regulatory Authority (ARN) of the Republica Argentina participates since 1995, in the Quality Assessment Program organized by the Environmental Measurements Laboratory - EML, of the United States. The participation in this program consist in: 1) Measurement of different gamma emitters in 4 environmental matrixes: water, filter, soil and vegetation; 2) Determination of actinides in the named matrixes; 3) Determination of tritium and iron-55 in water; 4) Determination of strontium-90 in water, filter, soil and vegetation; 5) Gross alpha and gross beta measurement in water and filter. In this paper, the results of the ARN in the six previous intercomparisons are exposed. An analysis of the deviations of the informed dates related to the EML values are made, and they are compared with the results of the rest of the participating laboratories. The determination methods and the measurement systems utilized in each matrix and for each radionuclide, are mentioned. (author) [es

  7. China's nuclear programs and policies

    International Nuclear Information System (INIS)

    Wang, C.

    1983-01-01

    Economics and the futility of arms competition with the US and USSR has forced China to shift its nuclear effort to peaceful uses, although its current nuclear-deterrent warrants including China in arms negotiations. China's nuclear program began during the 1950s with an emphasis on weaponry and some development in space technology. Proponents of nuclear power now appear to have refuted the earlier arguments that nuclear-plant construction would be too slow, too dangerous and polluting, and too expensive and the idea that hydro resources would be adequate. The current leadership supports a serious nuclear-power-plant construction program. 6 references

  8. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle descriptions

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    The Nonproliferation Alternative Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates. Volume IX is divided into three sections: Chapter 1, Reactor Systems; Chapter 2, Fuel-Cycle Systems; and the Appendixes. Chapter 1 contains the characterizations of the following 12 reactor types: light-water reactor; heavy-water reactor; water-cooled breeder reactor; high-temperature gas-cooled reactor; gas-cooled fast reactor; liquid-metal fast breeder reactor; spectral-shift-controlled reactor; accelerator-driven reactor; molten-salt reactor; gaseous-core reactor; tokamak fusion-fisson hybrid reactor; and fast mixed-spectrum reactor. Chapter 2 contains similar information developed for fuel-cycle facilities in the following categories: mining and milling; conversion and enrichment; fuel fabrication; spent fuel reprocessing; waste handling and disposal; and transportation of nuclear materials.

  9. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle descriptions

    International Nuclear Information System (INIS)

    1979-12-01

    The Nonproliferation Alternative Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates. Volume IX is divided into three sections: Chapter 1, Reactor Systems; Chapter 2, Fuel-Cycle Systems; and the Appendixes. Chapter 1 contains the characterizations of the following 12 reactor types: light-water reactor; heavy-water reactor; water-cooled breeder reactor; high-temperature gas-cooled reactor; gas-cooled fast reactor; liquid-metal fast breeder reactor; spectral-shift-controlled reactor; accelerator-driven reactor; molten-salt reactor; gaseous-core reactor; tokamak fusion-fisson hybrid reactor; and fast mixed-spectrum reactor. Chapter 2 contains similar information developed for fuel-cycle facilities in the following categories: mining and milling; conversion and enrichment; fuel fabrication; spent fuel reprocessing; waste handling and disposal; and transportation of nuclear materials

  10. Technical and Political Assessment of Peaceful Nuclear Power Program Prospects in North Africa and the Middle East

    Energy Technology Data Exchange (ETDEWEB)

    Windsor, Lindsay K.; Kessler, Carol E.

    2007-09-11

    An exceptional number of Middle Eastern and North African nations have recently expressed interest in developing nuclear energy for peaceful purposes. Many of these countries have explored nuclear research in limited ways in the past, but the current focused interest and application of resources towards developing nuclear-generated electricity and nuclear-powered desalination plants is unprecedented. Consequently, questions arise in response to this emerging trend: What instigated this interest? To what end(s) will a nuclear program be applied? Does the country have adequate technical, political, legislative, nonproliferation, and safety infrastructure required for the capability desired? If so, what are the next steps for a country in preparation for a future nuclear program? And if not, what collaboration efforts are possible with the United States or others? This report provides information on the capabilities and interests of 13 countries in the region in nuclear energy programs in light of safety, nonproliferation and security concerns. It also provides information useful for determining potential for offering technical collaboration, financial aid, and/or political support.

  11. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Rummery, T.E.; Rosinger, E.L.J.

    1983-05-01

    The Canadian Nuclear Fuel Waste Management Program is now well established. This report outlines the generic research and technological development underway in this program to assess the concept of immobilization and subsequent disposal of nuclear fuel waste deep in a stable plutonic rock in the Canadian Shield. The program participants, funding, schedule and associated external review processes are briefly outlined. The major scientific and engineering components of the program, namely, immobilization studies, geoscience research and environmental and safety assessment, are described in more detail

  12. IAEA Nuclear Security Human Resource Development Program

    International Nuclear Information System (INIS)

    Braunegger-Guelich, A.

    2009-01-01

    The IAEA is at the forefront of international efforts to strengthen the world's nuclear security framework. The current Nuclear Security Plan for 2006-2009 was approved by the IAEA Board of Governors in September 2005. This Plan has three main points of focus: needs assessment, prevention, detection and response. Its overall objective is to achieve improved worldwide security of nuclear and other radioactive material in use, storage and transport, and of their associated facilities. This will be achieved, in particular, through the provision of guidelines and recommendations, human resource development, nuclear security advisory services and assistance for the implementation of the framework in States, upon request. The presentation provides an overview of the IAEA nuclear security human resource development program that is divided into two parts: training and education. Whereas the training program focuses on filling gaps between the actual performance of personnel working in the area of nuclear security and the required competencies and skills needed to meet the international requirements and recommendations described in UN and IAEA documents relating to nuclear security, the Educational Program in Nuclear Security aims at developing nuclear security experts and specialists, at fostering a nuclear security culture and at establishing in this way sustainable knowledge in this field within a State. The presentation also elaborates on the nuclear security computer based learning component and provides insights into the use of human resource development as a tool in achieving the IAEA's long term goal of improving sustainable nuclear security in States. (author)

  13. Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.

    Energy Technology Data Exchange (ETDEWEB)

    Marietta, Melvin Gary; Anderson, D. Richard; Bonano, Evaristo J.; Meacham, Paul Gregory (Raytheon Ktech, Albuquerque, NM)

    2011-11-01

    Sandia National Laboratories (SNL) is the world leader in the development of the detailed science underpinning the application of a probabilistic risk assessment methodology, referred to in this report as performance assessment (PA), for (1) understanding and forecasting the long-term behavior of a radioactive waste disposal system, (2) estimating the ability of the disposal system and its various components to isolate the waste, (3) developing regulations, (4) implementing programs to estimate the safety that the system can afford to individuals and to the environment, and (5) demonstrating compliance with the attendant regulatory requirements. This report documents the evolution of the SNL PA methodology from inception in the mid-1970s, summarizing major SNL PA applications including: the Subseabed Disposal Project PAs for high-level radioactive waste; the Waste Isolation Pilot Plant PAs for disposal of defense transuranic waste; the Yucca Mountain Project total system PAs for deep geologic disposal of spent nuclear fuel and high-level radioactive waste; PAs for the Greater Confinement Borehole Disposal boreholes at the Nevada National Security Site; and PA evaluations for disposal of high-level wastes and Department of Energy spent nuclear fuels stored at Idaho National Laboratory. In addition, the report summarizes smaller PA programs for long-term cover systems implemented for the Monticello, Utah, mill-tailings repository; a PA for the SNL Mixed Waste Landfill in support of environmental restoration; PA support for radioactive waste management efforts in Egypt, Iraq, and Taiwan; and, most recently, PAs for analysis of alternative high-level radioactive waste disposal strategies including repositories deep borehole disposal and geologic repositories in shale and granite. Finally, this report summarizes the extension of the PA methodology for radioactive waste disposal toward development of an enhanced PA system for carbon sequestration and storage systems

  14. Radiological environmental monitoring programs at Canadian nuclear facilities - a practical model for follow-up activities under the Canadian Environmental Assessment Act

    International Nuclear Information System (INIS)

    Tamm, J.A.; Zach, R.

    2000-01-01

    Under the Canadian Environmental Assessment Act (the Act), a federal authority, if it considers it appropriate, is to design a follow-up program for a project undergoing a federal environmental assessment and arrange for implementation of that program. Under the Act a follow-up program means a set of activities for verifying the accuracy of the environmental assessment (EA) of a project and for determining the effectiveness of any measures taken to mitigate any adverse environmental effects resulting from the project. The Act currently does not include regulations, guidelines, standards or procedures regarding the design, content and implementation requirements for follow-up programs (Canadian Environmental Assessment Agency [the Agency] 1999). Uncertainties also exist regarding the roles and responsibilities in designing, implementing, enforcing and auditing such activities. The Agency is presently specifying appropriate activities to address these issues. This paper considers the existing radiological environmental monitoring programs at nuclear facilities. Such programs consist of two types of monitoring-radioactivity releases from the facility via liquid and gaseous waste streams, and radioactivity in the environment at large, beyond the facility's immediate location. Such programs have been developed by AECL, Canadian nuclear utilities and uranium mining companies. Our analysis show that these programs can provide a good model for follow-up programs under the Act. (author)

  15. Nuclear Reactor Sharing Program

    International Nuclear Information System (INIS)

    1994-01-01

    The Ohio State University Research Reactor (OSURR) is licensed to operate at a maximum power level of 500 kW. A pool-type reactor using flat-plate, low enriched fuel elements, the OSURR provides several experimental facilities including two 6-inch i.d. beam ports, a graphite thermal column, several graphite-isotope-irradiation elements, a pneumatic transfer system (Rabbit), various dry tubes, and a Central Irradiation Facility (CIF). The core arrangement and accessibility facilitates research programs involving material activation or core parameter studies. The OSURR control room is large enough to accommodate laboratory groups which can use control instrumentation for monitoring of experiments. The control instrumentation is relatively simple, without a large amount of duplication. This facilitates opportunities for hands-on experience in reactor operation by nuclear engineering students making reactor parameter measurements. For neutron activation analysis and analyses of natural environmental radioactivity, the NRL maintains the gamma ray spectroscopy system (GRSS). It is comprised of two PC-based 8192-channel multichannel analyzers (MCAs) with all the required software for quantitative analysis. A 3 double-prime x 3 double-prime NaI(Tl), a 14 percent Ge(Li), and a High Purity Germanium detector are currently available for use with the spectroscopy system

  16. Integrated Plant Safety Assessment: Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Final report

    International Nuclear Information System (INIS)

    1983-06-01

    The Systematic Evaluation program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  17. Integrated Plant Safety Assessment, Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Draft report

    International Nuclear Information System (INIS)

    1983-02-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  18. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.

    1984-12-01

    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 fourth 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 1983 are described in this report

  19. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume III. Resources and fuel cycle facilities

    International Nuclear Information System (INIS)

    1980-06-01

    The ability of uranium supply and the rest of the nuclear fuel cycle to meet the demand for nuclear power is an important consideration in future domestic and international planning. Accordingly, the purpose of this assessment is to evaluate the adequacy of potential supply for various nuclear resources and fuel cycle facilities in the United States and in the world outside centrally planned economy areas (WOCA). Although major emphasis was placed on uranium supply and demand, material resources (thorium and heavy water) and facility resources (separative work, spent fuel storage, and reprocessing) were also considered

  20. Integrated Plant Safety Assessment: Systematic Evaluation Program. Millstone Nuclear Power Station, Unit 1, Northeast Nuclear Energy Company, Docket No. 50-245. Final report

    International Nuclear Information System (INIS)

    1983-02-01

    This report documents the review of the Millstone Nuclear Power Station, Unit 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit 1, is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the Draft Report, issued in November 1982

  1. Waste isolation safety assessment program

    International Nuclear Information System (INIS)

    Brandstetter, A.; Harwell, M.A.

    1979-05-01

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE), through the National Waste Terminal Storage (NWTS) Program, is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Among the analyses required for isolation system evaluation is the detailed assessment of the post-closure performance of nuclear waste repositories in geologic formations. This assessment is essential, since it is concerned with aspects of the nuclear power program which previously have not been addressed. Specifically, the nature of the isolation systems (e.g., involving breach scenarios and transport through the geosphere), and the time-scales necessary for isolation, dictate the development, demonstration and application of novel assessment capabilities. The assessment methodology needs to be thorough, flexible, objective, and scientifically defensible. Further, the data utilized must be accurate, documented, reproducible, and based on sound scientific principles

  2. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Rummery, T.E.; Rosinger, E.L.J.

    1984-12-01

    The Canadian Nuclear Fuel Waste Management Program is in the fourth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the basic safety and environmental aspects of the concept of isolating immobilized fuel waste by deep underground disposal in plutonic rock. The major scientific and engineering components of the program, namely immobilization studies, geoscience research, and environmental and safety assessment, are described. Program funding, scheduling and associated external review processes are briefly outlined

  3. US nuclear power programs

    International Nuclear Information System (INIS)

    McGolf, D.J.

    1994-01-01

    In the United States, coal provided 56 percent of the electricity generated in 1992. Nuclear energy was the next largest contributor, supplying 22 percent. Natural gas provided 9 percent, while hydro-electric and renewables together supplied another 9 percent. Currently, the 109 nuclear power plants in the U.S. have an overall generating capacity of 99,000 MWe. To improve efficiency, safety, and performance, the lessons of 30 years of experience with nuclear powerplants are being incorporated into design criteria for the next generation of U.S. plants. The new Advanced Light Water Reactor plants will feature simpler designs, which will enable more cost-effective construction and maintenance. To enhance safety, design margins are being increased, and human factors are being considered and incorporated into the designs

  4. US nuclear power programs

    Energy Technology Data Exchange (ETDEWEB)

    McGolf, D J

    1994-12-31

    In the United States, coal provided 56 percent of the electricity generated in 1992. Nuclear energy was the next largest contributor, supplying 22 percent. Natural gas provided 9 percent, while hydro-electric and renewables together supplied another 9 percent. Currently, the 109 nuclear power plants in the U.S. have an overall generating capacity of 99,000 MWe. To improve efficiency, safety, and performance, the lessons of 30 years of experience with nuclear powerplants are being incorporated into design criteria for the next generation of U.S. plants. The new Advanced Light Water Reactor plants will feature simpler designs, which will enable more cost-effective construction and maintenance. To enhance safety, design margins are being increased, and human factors are being considered and incorporated into the designs.

  5. Accreditation of nuclear engineering programs

    International Nuclear Information System (INIS)

    Williamson, T.G.

    1989-01-01

    The American Nuclear Society (ANS) Professional Development and Accreditation Committee (PDAC) has the responsibility for accreditation of engineering and technology programs for nuclear and similarly named programs. This committee provides society liaison with the Accreditation Board for Engineering and Technology (ABET), is responsible for the appointment and training of accreditation visitors, nomination of members for the ABET Board and Accreditation Commissions, and review of the criteria for accreditation of nuclear-related programs. The committee is composed of 21 members representing academia and industry. The ABET consists of 19 participating bodies, primarily professional societies, and 4 affiliate bodies. Representation on ABET is determined by the size of the professional society and the number of programs accredited. The ANS, as a participating body, has one member on the ABET board, two members on the Engineering Accreditation Commission, and one on the Technology Accreditation Commission. The ABET board sets ABET policy and the commissions are responsible for accreditation visits

  6. Programs for nuclear data analysis

    International Nuclear Information System (INIS)

    Bell, R.A.I.

    1975-01-01

    The following report details a number of programs and subroutines which are useful for analysis of data from nuclear physics experiments. Most of them are available from pool pack 005 on the IBM1800 computer. All of these programs are stored there as core loads, and the subroutines and functions in relocatable format. The nature and location of other programs are specified as appropriate. (author)

  7. Nuclear wastes: research programs

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    The management of long-living and high level radioactive wastes in France belongs to the framework of the December 30, 1991 law which defines three ways of research: the separation and transmutation of radionuclides, their reversible storage or disposal in deep geologic formations, and their processing and surface storage during long duration. Research works are done in partnership between public research and industrial organizations in many French and foreign laboratories. Twelve years after its enforcement, the impact of this law has overstepped the simple research framework and has led to a deep reflection of the society about the use of nuclear energy. This short paper presents the main results obtained so far in the three research ways, the general energy policy of the French government, the industrial progresses made in the framework of the 1991 law and the international context of the management of nuclear wastes. (J.S.)

  8. Sloan foundation nuclear education program

    International Nuclear Information System (INIS)

    Kursunoglu, B.N.

    1992-01-01

    The Alfred P. Sloan Foundation realized the time had come for a real and significant contribution to the enlightenment of university students concerning nuclear matters. The Sloan Foundation chose to educate the youth of four-year colleges and universities with a curriculum established with the resource information sieved from three workshops for professors in these institutions. The three workshops were organized by groups at Harvard-MIT (two-week Summer Program on Nuclear Weapons and Arms Control), the University of California, San Diego (two-week Summer Seminar on Global Security and Arms Control), and the University of Miami (one-week Winter Workshop on Enlightenment: The Best Security in a Nuclear-Armed World). In this report the author focuses on a unified presentation of the basic facts, aims, and results of the Sloan Foundation Nuclear Education Program based on three workshops directed by Jack Ruina (MIT), Herbert York (USCD), and Behram Kursunoglu (UM) and offered from 1983-1990

  9. Soviet Union's Nuclear Power Program

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    Glasnost has dramatically increased the availability of information about the Soviet Union's nuclear industry. In the future, even more information is likely to become known as Soviet participation in international forums increases. Not only is much more general information now available, but up-to-date details are regularly provided, including information such as the Soviet nuclear industry's strategic direction and goals, recent reactor design changes, safety inspection results, and reports of public opposition and protest. This article summarizes the current status of the Soviet nuclear power program, reconciling the often conflicting reports from various public sources

  10. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle description

    International Nuclear Information System (INIS)

    1980-06-01

    The Nonproliferation Alterntive Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates

  11. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle description

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    The Nonproliferation Alterntive Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates.

  12. Assessments of nuclear systems

    International Nuclear Information System (INIS)

    Ekholm, R.

    1978-01-01

    Assessments of competing energy systems are gaining increased importance as a means for an optimal choice of energy source for each specific major application considering the growing energy needs and the shortage of supply. However it is important to make sure that the assessments reflect scientific facts rather than private interests. If this is not achieved, scientists will lose credibility and one will lose the basis for political decisions. It is concluded that to accomplish the globally justified needs for thousands of nuclear reactors soon after the year 2000 and to save a maximum of lives with a minimum of environmental impact, emphasis must be put on low energy costs and on a good fuel and capital resource utilization. This goal can be best accomplished by expendient introduction of the fast breeders and of promising advanced reactors. The gas cooled breeder and the high temperature reactor have outstanding short and long terms merits on this respect, but are not enjoying the financial support that they deserve. (UK)

  13. Passive Nuclear Plants Program (UPDATE)

    International Nuclear Information System (INIS)

    Chimeno, M. A.

    1998-01-01

    The light water passive plants program (PCNP), today Advanced Nuclear Power Plants Program (PCNA), was constituted in order to reach the goals of the Spanish Electrical Sector in the field of advanced nuclear power plants, optimize the efforts of all Spanish initiatives, and increase joint presence in international projects. The last update of this program, featured in revision 5th of the Program Report, reflects the consolidation of the Spanish sector's presence in International programs of the advanced power plants on the basis of the practically concluded American ALWR program. Since the beginning of the program , the PCNP relies on financing from the Electrical sector, Ocide, SEPI-Endesa, Westinghouse, General Electric, as well as from the industrial cooperators, Initec, UTE (Initec- Empresarios Agrupados), Ciemat, Enusa, Ensa and Tecnatom. The program is made up of the following projects, already concluded: - EPRI's Advanced Light Water Plants Certification Project - Westinghouse's AP600 Project - General Electric's SBWR Project (presently paralyzed) and ABWR project Currently, the following project are under development, at different degrees of advance: - EPP project (European Passive Plant) - EBWR project (European Advanced Boiling Water Reactor)

  14. Integrated plant safety assessment: Systematic Evaluation Program, San Onofre Nuclear Generating Station, Unit 1 (Docket No. 50-206): Final report

    International Nuclear Information System (INIS)

    1986-12-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues; (2) a basis for deciding on how these differences should be resolved in an integrated plant review; and (3) a documented evaluation of plant safety. This report documents the review of San Onofre Nuclear Generating Station, Unit 1, operated by Southern California Edison Company. The San Onofre plant is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. This report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the draft report issued in April 1985

  15. Integrated plant safety assessment systematic evaluation program. R.E. Ginna Nuclear Power Plant, Rochester Gas and Electric Corporation, Docket No. 50-244

    International Nuclear Information System (INIS)

    1982-05-01

    The Systematic Evaluation Program was initiated in February 1978 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the R.E. Ginna Nuclear Power Plant (located in Wayne County near Rochester, NY), one of ten plants reviewed under Phase II of this program, and indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  16. Integrated-plant-safety assessment Systematic Evaluation Program. Dresden Nuclear Power Station, Unit 2, Commonwealth Edison Company, Docket No. 50-237

    International Nuclear Information System (INIS)

    1982-10-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues; (2) a basis for deciding on how these differences should be resolved in an integrated plant review; and (3) a documented evaluation of plant safety. This report documents the review of Dresden Nuclear Generating Station, Unit 2 owned and operated by the Commonwealth Edison Company and located in Grundy County, Illinois. Dresden Unit 2 is one of ten plants reviewed under Phase II of this program, which indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  17. Nuclear data needs of Indian nuclear program

    International Nuclear Information System (INIS)

    Fernando, M.P.S.

    2015-01-01

    Currently 17 Pressurised Heavy water Reactors (PHWRs), 2 Boiling water reactors (BWRs) and 1 Pressurised water reactor (PWR) are being operated for power production by Nuclear Power Corporation India Limited (NPCIL). For PHWRs, different types of fuel bundles are simulated by the integral transport theory code, CLUB using a combination of collision probability method and interface current technique and employing IAEA supplied 69 /172 group WIMS cross section library based on ENDF-BVI, BVII. Ring power factors are calculated at different burnups and are used to estimate linear heat rating. The two group neutron cross sections of different type of lattices at different core irradiations are also generated by lattice code CLUB. Wherever reactivity devices are present, supercell approach is adopted and the suitable incremental absorption cross sections are obtained using BOXER which is based on 3-D integral transport theory considering two neutron energy groups. Using the appropriate properties for normal lattices and ones affected by reactivity devices, fuel management and core follow up studies are carried out using 3-D diffusion theory based TRIVENI code. The KAPS-1 power rise transient on March 10, 2004 brought to focus the importance of accurate nuclear data for reactor physics estimation in Indian PHWRs. With IAEA supplied libraries in WIMS format we could satisfactorily resolve the rate of power increase. Stability analysis and sensitivity analysis was carried out for different incore burnup situations resulting from peak flux operation. The quantification of output uncertainties is necessary to adequately establish safety margins of nuclear facilities. The uncertainties in the integral parameters such as reactivity worth and coefficients due to cross section can be assessed using cross section covariance data produced directly from the uncertainties of measurements. Covariance data processing codes and sensitivity analysis tools have to be developed. The part

  18. Amchitka bioenvironmental program. Geomorphology and plant ecology: an assessment of the impact of AEC nuclear test on Amchitka

    International Nuclear Information System (INIS)

    Everett, K.R.; Amundsen, C.C.

    1975-03-01

    The U. S. Atomic Energy Commission's underground nuclear testing on Amchitka has included two nuclear detonations: Milrow (about 1-megaton) in October 1969, and Cannikin (a little less than 5-megatons) in November 1971. This report assesses the impact of these tests on the basis of information collected since 1967 and through the 1973 growing season. To make these assessments and predictions realistic it was necessary to develop general descriptions of Amchitka's geomorphology, terrestrial plant ecology, and physical environment; and to assess the effects of man's previous use of the Island through World War II and the DOD Long Shot test. Mapping methods and methods for plant-community and soil-type studies and definitions are described because they were used to predict vegetative recovery on disturbed areas which are shown to have their counterparts as a consequence of the Island's natural landscape dynamics. Four annotated plates, covering the study area (45 percent of the Island), show disturbances (1) before 1948, (2) 1948 to 1969 before Milrow, (3) Milrow to 1971 before Cannikin, and (4) during 1971 after Cannikin. A fifth plate shows the plant community distribution in the study area. While classic sequential plant succession cannot be demonstrated on Amchitka, revegetation in disturbed areas, more properly described as recovery, is described for the various disturbances of terrain and vegetation cover. The photographs are keyed to indicate recovery time from date indicated, type of disturbance, and expected plant-community shift, as well as type of newly exposed or flooded substrate, drainage shifts, and other shock-related phenomena. (U.S.)

  19. Power program and nuclear power

    International Nuclear Information System (INIS)

    Chernilin, Yu.F.

    1990-01-01

    Main points of the USSR power program and the role of nuclear power in fuel and power complex of the country are considered. Data on dynamics of economic indices of electric power generation at nuclear power plants during 1980-1988 and forecasts till 2000 are presented. It is shown that real cost of 1 kW/h of electric power is equal to 1.3-1.8 cop., and total reduced cost is equal to 1.8-2.4 cop

  20. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Nuttall, K.

    1987-01-01

    Canada has established an extensive research program to develop and demonstrate the technology for safely disposing of nuclear fuel waste from Canadian nuclear electric generating stations. The program focuses on the concept of disposal deep in plutonic rock, which is abundant in the province of Ontario, Canada's major producer of nuclear electricity. Research is carried out at field research areas in the Canadian Precambrian Shield, and in government and university laboratories. The schedule calls for a document assessing the disposal concept to be submitted to regulatory and environmental agencies in late 1988. This document will form the basis for a review of the concept by these agencies and by the public. No site selection will be carried out before this review is completed. 10 refs.; 2 figs

  1. Defining the “proven technology” technical criterion in the reactor technology assessment for Malaysia’s nuclear power program

    International Nuclear Information System (INIS)

    Anuar, Nuraslinda; Kahar, Wan Shakirah Wan Abdul; Manan, Jamal Abdul Nasir Abd

    2015-01-01

    Developing countries that are considering the deployment of nuclear power plants (NPPs) in the near future need to perform reactor technology assessment (RTA) in order to select the most suitable reactor design. The International Atomic Energy Agency (IAEA) reported in the Common User Considerations (CUC) document that “proven technology” is one of the most important technical criteria for newcomer countries in performing the RTA. The qualitative description of five desired features for “proven technology” is relatively broad and only provides a general guideline to its characterization. This paper proposes a methodology to define the “proven technology” term according to a specific country’s requirements using a three-stage evaluation process. The first evaluation stage screens the available technologies in the market against a predefined minimum Technology Readiness Level (TRL) derived as a condition based on national needs and policy objectives. The result is a list of technology options, which are then assessed in the second evaluation stage against quantitative definitions of CUC desired features for proven technology. The potential technology candidates produced from this evaluation is further narrowed down to obtain a list of proven technology candidates by assessing them against selected risk criteria and the established maximum allowable total score using a scoring matrix. The outcome of this methodology is the proven technology candidates selected using an accurate definition of “proven technology” that fulfills the policy objectives, national needs and risk, and country-specific CUC desired features of the country that performs this assessment. A simplified assessment for Malaysia is carried out to demonstrate and suggest the use of the proposed methodology. In this exercise, ABWR, AP1000, APR1400 and EPR designs assumed the top-ranks of proven technology candidates according to Malaysia’s definition of “proven technology”

  2. Defining the “proven technology” technical criterion in the reactor technology assessment for Malaysia’s nuclear power program

    Energy Technology Data Exchange (ETDEWEB)

    Anuar, Nuraslinda, E-mail: nuraslinda@uniten.edu.my [College of Engineering, Universiti Tenaga Nasional, Jalan IKRAM-UNITEN, 43000 Kajang, Selangor (Malaysia); Kahar, Wan Shakirah Wan Abdul, E-mail: shakirah@tnb.com.my; Manan, Jamal Abdul Nasir Abd [Nuclear Energy Department, Regulatory Economics and Planning Division, Tenaga Nasional Berhad, No. 8 Jalan Tun Sambanthan, Brickfields, 50470 Kuala Lumpur (Malaysia)

    2015-04-29

    Developing countries that are considering the deployment of nuclear power plants (NPPs) in the near future need to perform reactor technology assessment (RTA) in order to select the most suitable reactor design. The International Atomic Energy Agency (IAEA) reported in the Common User Considerations (CUC) document that “proven technology” is one of the most important technical criteria for newcomer countries in performing the RTA. The qualitative description of five desired features for “proven technology” is relatively broad and only provides a general guideline to its characterization. This paper proposes a methodology to define the “proven technology” term according to a specific country’s requirements using a three-stage evaluation process. The first evaluation stage screens the available technologies in the market against a predefined minimum Technology Readiness Level (TRL) derived as a condition based on national needs and policy objectives. The result is a list of technology options, which are then assessed in the second evaluation stage against quantitative definitions of CUC desired features for proven technology. The potential technology candidates produced from this evaluation is further narrowed down to obtain a list of proven technology candidates by assessing them against selected risk criteria and the established maximum allowable total score using a scoring matrix. The outcome of this methodology is the proven technology candidates selected using an accurate definition of “proven technology” that fulfills the policy objectives, national needs and risk, and country-specific CUC desired features of the country that performs this assessment. A simplified assessment for Malaysia is carried out to demonstrate and suggest the use of the proposed methodology. In this exercise, ABWR, AP1000, APR1400 and EPR designs assumed the top-ranks of proven technology candidates according to Malaysia’s definition of “proven technology”.

  3. QA programs in nuclear power plants

    International Nuclear Information System (INIS)

    Ellingson, A.C.

    1976-01-01

    As an overview of quality assurance programs in nuclear power plants, the energy picture as it appears today is reviewed. Nuclear power plants and their operations are described and an attempt is made to place in proper perspective the alleged ''threats'' inherent in nuclear power. Finally, the quality assurance programs being used in the nuclear industry are described

  4. New nuclear build programs status and prospects

    International Nuclear Information System (INIS)

    Tankosic, D.; Sabinov, S.

    2010-01-01

    Presentation topics: Reactor technology update OECD OEMs development; Nuclear power sector development projections - global nuclear capacity projections to 2050 (NEA low , high and phase-out scenarios); new nuclear constructions Worley Parsons support to new nuclear Programs around the world; Drivers towards increased nuclear capacity - increased demand of generating capacities; climate change concerns; Security of supply; Economics; Robust to fuel price increases

  5. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.; Rosinger, E.L.J.

    1984-04-01

    This report, the fifth of a series of annual reports, reviews the progress that has been made in the research and development program for the safe management and disposal of Canada's nuclear fuel waste. The report summarizes activities over the past year in the following areas: public interaction; used fuel storage and transportation; immobilization of used fuel and fuel recycle waste; geoscience research related to deep underground disposal; environmental research; and environmental and safety assessment

  6. Concrete Technology program for nuclear power plants

    International Nuclear Information System (INIS)

    Hassazadeh, M.; Wrangensten, L.

    2009-01-01

    The nuclear power plants in Sweden and Finland were built during the seventies/eighties and it is planned to extend their service life and increase their production capacity. The challenges are now to assess the condition of the concrete structures; to verify whether or not the structures can withstand the prescribed loads and functions; and verify if the structures can be upgraded in order to fulfil the requirements regarding load bearing and functional capacity. A research program was launched whose priority is condition assessment of the reactor containment. The research includes condition of the pre-stressing reinforcement, reinforcement bars, lining, leakage etc. The conditions are assessed both by destructive and non-destructive test methods. The addressed properties are physical, mechanical, electro-chemical and geometrical. The paper presents the organisation of the program, the co-operating partners, the research program, and the content of the on-going and planned research projects

  7. Nuclear program of South Korea

    International Nuclear Information System (INIS)

    Brown, D.S.; James, K.R.

    1993-01-01

    Slightly larger than Portugal, South Korea comprises the lower half on the Korean Peninsula, covering approximately 38 thousand square miles. the Republic of Korea (South Korea) was established in 1948, and until 1962 the country grew slowly. However, through a series of five-year economic plans initiated by South Korean President Park Ching Hee, South Korea has since created an export-oriented economy, which now plays a major role in regional as well as global trade. South Korea has been forced to constantly upgrade its power generation structure in order to sustain the explosive growth it has experienced. Nuclear power has been a major player in this expansion and is expected to play an ever-increasing role. The country presently operates nine nuclear reactors with a total net generating capacity of 7,266 MWe. By the year 2006, the nuclear program is scheduled to grow to 27 reactors, with a net generating capacity exceeding 23 thousand MWe. Once this goal is reached, nuclear-generated power would account for more than 40 percent of the country's total installed electrical capacity

  8. Nuclear Engineering Academic Programs Survey, 2004

    International Nuclear Information System (INIS)

    Oak Ridge Institute for Science and Education

    2005-01-01

    This annual report details the number of nuclear engineering bachelor's, master's, and doctoral degrees awarded at a sampling of academic programs from 1998-2004. It also looks at nuclear engineering degrees by curriculum and the number of students enrolled in nuclear engineering degree programs at 31 U.S. universities in 2004

  9. Risk assessment and nuclear power

    International Nuclear Information System (INIS)

    Bodansky, D.

    1982-01-01

    The range of risk perceptions involving nuclear power is so great that there is little hope of bridging extreme positions, but a consensus based upon reasoned discussion among uncommitted people could determine a sensible path. Our concerns over the uncertainties of risk assessment have made it increasingly difficult to make responsible decisions fast enough to deal with modern needs. The result is an immobility in energy matters that can point to a 2% reduction in oil use as its only triumph. The risk of nuclear war as a result of military action over energy issues suggests to some that the solution is to abolish nuclear power (however impractical) and to others that a rapid spread of nuclear power will eliminate energy as an incentive for war. If nuclear war is the major risk to consider, risk assessments need to include the risks of war, as well as those of carbon dioxide buildup and socio-economic disruptions, all of which loom larger than the risks of nuclear-plant accidents. Energy choices should be aimed at diminishing these major risks, even if they include the use of nuclear power. 26 references

  10. Status of Iran's nuclear program and negotiations

    International Nuclear Information System (INIS)

    Albright, David

    2014-01-01

    Iran's nuclear program poses immense challenges to international security. Its gas centrifuge program has grown dramatically in the last several years, bringing Iran close to a point where it could produce highly enriched uranium in secret or declared gas centrifuge plants before its breakout would be discovered and stopped. To reduce the risk posed by Iran's nuclear program, the P5+1 have negotiated with Iran short term limits on the most dangerous aspects of its nuclear programs and is negotiating long-term arrangements that can provide assurance that Iran will not build nuclear weapons. These long-term arrangements need to include a far more limited and transparent Iranian nuclear program. In advance of arriving at a long-term arrangement, the IAEA will need to resolve its concerns about the alleged past and possibly on-going military dimensions of Iran's nuclear program

  11. Elements of a nuclear criticality safety program

    International Nuclear Information System (INIS)

    Hopper, C.M.

    1995-01-01

    Nuclear criticality safety programs throughout the United States are quite successful, as compared with other safety disciplines, at protecting life and property, especially when regarded as a developing safety function with no historical perspective for the cause and effect of process nuclear criticality accidents before 1943. The programs evolved through self-imposed and regulatory-imposed incentives. They are the products of conscientious individuals, supportive corporations, obliged regulators, and intervenors (political, public, and private). The maturing of nuclear criticality safety programs throughout the United States has been spasmodic, with stability provided by the volunteer standards efforts within the American Nuclear Society. This presentation provides the status, relative to current needs, for nuclear criticality safety program elements that address organization of and assignments for nuclear criticality safety program responsibilities; personnel qualifications; and analytical capabilities for the technical definition of critical, subcritical, safety and operating limits, and program quality assurance

  12. Nuclear power program and environment

    International Nuclear Information System (INIS)

    Subramanya, S.K.; Gupta, J.P.

    2012-01-01

    Access to energy is one of the basic requirements for human development. To meet these growing energy needs without creating negative side effects is a challenge. The possibility of global climate change resulting from an increase in GHG concentrations in the atmosphere due to developmental activities is a major global concern. India is passing through the process of economic growth. Although India has not created the problem of climate change, India stands ready to be a part of the solution. The largest chunk of emissions was from electricity generation amounting to 65 percent of the total CO 2 equivalent emissions from the energy sector. Nuclear energy and renewables stand as sources for electricity with minimum GHG emission. Production of electricity from any form of primary energy has some environmental effect. A balanced assessment is needed. Nuclear power is of importance to India because it has potentially unlimited resource base, does not emit GHGs and, depending on location, has potentially favourable economics versus coal. In the long term, if we are to preserve the environment, it will be necessary to tap this source to the maximum extent feasible, In nuclear power stations, all its wastes are contained. India being home to nearly a third of the entire world's thorium, the strategies for large scale deployment of nuclear energy is focused towards utilization of thorium. The electricity potential of 3-stage programme is estimated to be about 2 lakh GWe-yr. Nuclear Power Corporation of India Limited is currently operating 20 reactors and has accumulated more than 337 reactor-years of experience in safe operation. A defence-in-depth approach is at the heart of safety philosophy, where there are several lines of defence, one backing another. Radiation is relevant for nuclear, coal, oil, gas and geothermal power plants. The essential task is to prevent excessive amounts now or in the future. One of the guiding principles adopted is to ensure that radiation

  13. Overview of the DOE nuclear data program

    International Nuclear Information System (INIS)

    Whetstone, S.L.

    1991-01-01

    Numerous researchers receive support from the US Department of Energy's (DOE's) nuclear data program; others work closely with it, attending coordination meetings and contributing to data activities. Since fiscal year (FY) 1988, the nuclear data program has been included in the budget of the Division of Nuclear Physics in the DOE's Office of High Energy and Nuclear Physics. The budget for nuclear data consists of two budget categories: nuclear data compilation and evaluation and nuclear data measurements, both of which are contained within the low-energy nuclear physics program. The program has become essentially the sole supporter of the National Nuclear Data Center at Brookhaven National Laboratory. The Center coordinates the production of the ENSDF data base and Nuclear Data Sheets as well as, through the Cross Section Evaluation Working Group (CSEWG138), the production of the ENDF. Two rather large accelerator facilities, completely supported by the program, the Oak Ridge Electron Linear Accelerator and the fast neutron generator at Argonne National Laboratory, form the core of the nuclear data measurement activity together with measurement programs at Los Alamos National Laboratory's LAMPF/WNR facility, and at accelerator laboratories at Ohio University, Duke University, the University of Lowell, the University of Michigan, and the Colorado School of Mines. Some history is discussed and future modernizing plans are identified

  14. Underground Nuclear Testing Program, Nevada Test Site

    International Nuclear Information System (INIS)

    1975-09-01

    The Energy Research and Development Administration (ERDA) continues to conduct an underground nuclear testing program which includes tests for nuclear weapons development and other tests for development of nuclear explosives and methods for their application for peaceful uses. ERDA also continues to provide nuclear explosive and test site support for nuclear effects tests sponsored by the Department of Defense. This Supplement extends the Environmental Statement (WASH-1526) to cover all underground nuclear tests and preparations for tests of one megaton (1 MT) or less at the Nevada Test Site (NTS) during Fiscal Year 1976. The test activities covered include numerous continuing programs, both nuclear and non-nuclear, which can best be conducted in a remote area. However, if nuclear excavation tests or tests of yields above 1 MT or tests away from NTS should be planned, these will be covered by separate environmental statements

  15. Evaluation of Nuclear Facility Decommissioning Projects program

    International Nuclear Information System (INIS)

    Baumann, B.L.

    1983-01-01

    The objective of the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program is to provide the NRC licensing staff with data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. The data will also provide information to determine the funding level necessary to ensure timely and safe decommissioning operations. Actual decommissioning costs, methods and radiation exposures are compared with those estimated by the Battelle-PNL and ORNL NUREGs on decommissioning. Exposure reduction techniques applied to decommissioning activities to meet ALARA objectives are described. The lessons learned concerning various decommissioning methods are evaluated

  16. MRI assessment program

    International Nuclear Information System (INIS)

    1987-09-01

    The MRI Assessment Program involves installation and operation of five MRI units in Australian public hospitals and the evaluation at each unit of the cost and efficacy of the technology over a period of two years. This first report in a series presents preliminary usage and cost data for the year to 30 June 1987 as well as describing the background and the data set. 6 figs., tabs

  17. Results of comparative assessment of US and foreign nuclear power plant dose experience and dose reduction programs

    International Nuclear Information System (INIS)

    Baum, J.W.; Horan, J.R.; Dionne, B.J.

    1985-01-01

    The objectives of this study were to determine how collective dose equivalents at US nuclear power plants compare to those of other technically advanced countries, and to evaluate factors that contribute to the differences. Fifty Health Physicists and nuclear engineers from 10 countries met at BNL May 29 - June 1, 1984 to exchange information and hold discussions on ''Historical Dose Experience and Dose Reduction (ALARA) at Nuclear Power Plants''. Results of evaluation of data from this meeting and other data from recent publications are summarized. Based on data evaluated to date it is clear that US plants have higher collective dose equivalents per reactor and per MW-yr generated than most other countries. Factors which contribute to low doses include: 1) minimization of cobalt in primary system components exposed to water, 2) careful control of primary system oxygen and pH, 3) good primary system water purity to minimize corrosion product formation, 4) careful plant design, layout and component segregation and shielding, 5) management interest and commitment, 6) minimum number of workers and in-depth worker training, 7) use of special tools, and 8) plant standardization

  18. Nuclear Security Education Program at the Pennsylvania State University

    Energy Technology Data Exchange (ETDEWEB)

    Uenlue, Kenan [The Pennsylvania State University, Radiation Science and Engineering Center, University Park, PA 16802-2304 (United States); The Pennsylvania State University, Department of Mechanical and Nuclear Engineering, University Park, PA 16802-2304 (United States); Jovanovic, Igor [The Pennsylvania State University, Department of Mechanical and Nuclear Engineering, University Park, PA 16802-2304 (United States)

    2015-07-01

    The availability of trained and qualified nuclear and radiation security experts worldwide has decreased as those with hands-on experience have retired while the demand for these experts and skills have increased. The U.S. Department of Energy's National Nuclear Security Administration's (NNSA) Global Threat Reduction Initiative (GTRI) has responded to the continued loss of technical and policy expertise amongst personnel and students in the security field by initiating the establishment of a Nuclear Security Education Initiative, in partnership with Pennsylvania State University (PSU), Texas A and M (TAMU), and Massachusetts Institute of Technology (MIT). This collaborative, multi-year initiative forms the basis of specific education programs designed to educate the next generation of personnel who plan on careers in the nonproliferation and security fields with both domestic and international focus. The three universities worked collaboratively to develop five core courses consistent with the GTRI mission, policies, and practices. These courses are the following: Global Nuclear Security Policies, Detectors and Source Technologies, Applications of Detectors/Sensors/Sources for Radiation Detection and Measurements Nuclear Security Laboratory, Threat Analysis and Assessment, and Design and Analysis of Security Systems for Nuclear and Radiological Facilities. The Pennsylvania State University (PSU) Nuclear Engineering Program is a leader in undergraduate and graduate-level nuclear engineering education in the USA. The PSU offers undergraduate and graduate programs in nuclear engineering. The PSU undergraduate program in nuclear engineering is the largest nuclear engineering programs in the USA. The PSU Radiation Science and Engineering Center (RSEC) facilities are being used for most of the nuclear security education program activities. Laboratory space and equipment was made available for this purpose. The RSEC facilities include the Penn State Breazeale

  19. Nuclear Security Education Program at the Pennsylvania State University

    International Nuclear Information System (INIS)

    Uenlue, Kenan; Jovanovic, Igor

    2015-01-01

    The availability of trained and qualified nuclear and radiation security experts worldwide has decreased as those with hands-on experience have retired while the demand for these experts and skills have increased. The U.S. Department of Energy's National Nuclear Security Administration's (NNSA) Global Threat Reduction Initiative (GTRI) has responded to the continued loss of technical and policy expertise amongst personnel and students in the security field by initiating the establishment of a Nuclear Security Education Initiative, in partnership with Pennsylvania State University (PSU), Texas A and M (TAMU), and Massachusetts Institute of Technology (MIT). This collaborative, multi-year initiative forms the basis of specific education programs designed to educate the next generation of personnel who plan on careers in the nonproliferation and security fields with both domestic and international focus. The three universities worked collaboratively to develop five core courses consistent with the GTRI mission, policies, and practices. These courses are the following: Global Nuclear Security Policies, Detectors and Source Technologies, Applications of Detectors/Sensors/Sources for Radiation Detection and Measurements Nuclear Security Laboratory, Threat Analysis and Assessment, and Design and Analysis of Security Systems for Nuclear and Radiological Facilities. The Pennsylvania State University (PSU) Nuclear Engineering Program is a leader in undergraduate and graduate-level nuclear engineering education in the USA. The PSU offers undergraduate and graduate programs in nuclear engineering. The PSU undergraduate program in nuclear engineering is the largest nuclear engineering programs in the USA. The PSU Radiation Science and Engineering Center (RSEC) facilities are being used for most of the nuclear security education program activities. Laboratory space and equipment was made available for this purpose. The RSEC facilities include the Penn State Breazeale

  20. Management plan for the Nuclear Standards Program

    International Nuclear Information System (INIS)

    1979-11-01

    This Management Plan was prepared to describe the manner in which Oak Ridge National Laboratory will provide technical management of the Nuclear Standards Program. The organizational structure that has been established within ORNL for this function is the Nuclear Standards Management Center, which includes the Nuclear Standards Office (NSO) already in existence at ORNL. This plan is intended to support the policies and practices for the development and application of technical standards in ETN projects, programs, and technology developments as set forth in a standards policy memorandum from the DOE Program Director for Nuclear Energy

  1. Nuclear Nonproliferation Ontology Assessment Team Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Strasburg, Jana D.; Hohimer, Ryan E.

    2012-01-01

    Final Report for the NA22 Simulations, Algorithm and Modeling (SAM) Ontology Assessment Team's efforts from FY09-FY11. The Ontology Assessment Team began in May 2009 and concluded in September 2011. During this two-year time frame, the Ontology Assessment team had two objectives: (1) Assessing the utility of knowledge representation and semantic technologies for addressing nuclear nonproliferation challenges; and (2) Developing ontological support tools that would provide a framework for integrating across the Simulation, Algorithm and Modeling (SAM) program. The SAM Program was going through a large assessment and strategic planning effort during this time and as a result, the relative importance of these two objectives changed, altering the focus of the Ontology Assessment Team. In the end, the team conducted an assessment of the state of art, created an annotated bibliography, and developed a series of ontological support tools, demonstrations and presentations. A total of more than 35 individuals from 12 different research institutions participated in the Ontology Assessment Team. These included subject matter experts in several nuclear nonproliferation-related domains as well as experts in semantic technologies. Despite the diverse backgrounds and perspectives, the Ontology Assessment team functioned very well together and aspects could serve as a model for future inter-laboratory collaborations and working groups. While the team encountered several challenges and learned many lessons along the way, the Ontology Assessment effort was ultimately a success that led to several multi-lab research projects and opened up a new area of scientific exploration within the Office of Nuclear Nonproliferation and Verification.

  2. Status of the Canadian Nuclear Fuel Waste Management Program

    International Nuclear Information System (INIS)

    Lyon, R.B.

    1985-10-01

    The Canadian Nuclear Fuel Waste Management Program is in the fifth year of a ten-year generic research and development phase. The major objective of this phase of the program is to assess the basic safety and environmental aspects of the concept of isolating immobilized fuel waste by deep underground disposal in plutonic rock. The major scientific and engineering components of the program, namely immobilization studies, geoscience research, and environmental and safety assessment, are well established

  3. The University of Utah Nuclear Engineering Program

    International Nuclear Information System (INIS)

    Jevremovic, T.; McDonald, L. IV; Schow, R.

    2016-01-01

    As of 2014, the University of Utah Nuclear Engineering Program (UNEP) manages and maintains over 7,000 ft 2 (~650 m 2 ) nuclear engineering facilities that includes 100 kW TRIGA Mark I and numerous laboratories such as radiochemistry, microscopy, nuclear forensics, nuclear medicine, radiation detection and instrumentation laboratories. The UNEP offers prestigious educational and training programs in the field of faculty reserach: reactor physics, reactor design and operation, advanced numerical modeling and visualizations in radiation transport, radiochemistry, nuclear forensics, radiation detection and detector designs, signal processing, nuclear medicine, nuclear space and nuclear robotic’s engineering and radiological sciences. With the state-of-the-art nuclear instrumentation and state-of-the-art numerical modeling tools, reserach reactor and modernized educational and training programs, we positioned ourselves in the last five years as the fastest growing national nuclear engineering program attracting the students from many disciplines such as but not limited to: chemical engineering, civil engineering, environmental engineering, chemistry, physics, astronomy, medical sciences, and others. From 2012, we uniquely developed and implemented the nuclear power plants’ safety culture paradigm that we use for day-to-day operation, management and maintenance of our facilities, as well as train all our students at undergraduate and graduate levels of studies. We developed also a new distance-learning approaches in sharing knowledge about experiential learning based on no-cost internet-tools combined with the use of mobile technologies. (author)

  4. MRI assessment program

    International Nuclear Information System (INIS)

    1988-05-01

    Usage, cost and efficacy data from the MRI Assessment Program to 30 March 1988 is presented, as a continuation of an earlier analysis. Analysis has been performed on data from 8565 examinations relating to 7997 patients at 4 hospitals. MRI was used mainly for examination of the head and spine. Some details of the follow up studies being conducted on selected patients and disease categories are given. A consensus statement is included which summaries the view of the Technical Committee on the potential applications of MRI in Australia. The MRI unit quench incident at Royal Adelaide Hospital is described. Refs., 10 figs., tabs

  5. Nuclear Power Infrastructure Development Program: Korean Education Program

    International Nuclear Information System (INIS)

    Choi, Sung Yeol; Hwang, Il Soon; Kim, Si Hwan

    2009-01-01

    Many countries have decided nuclear power for next energy resources as one of the long-term energy supply options. IAEA projected nuclear power expansion up to 2030 reaching between 447 GWe and 691 GWe compared to 370 GWe and 2660 TWh at the end of 2006. Both low and high projection is accompanied with new nuclear power plant constructions respectively 178 and 357, about 11 units per year, and most new construction is in North America, the Far East, Eastern Europe, the Middle East, and Southeast Asia. During the last forty years, thirty three countries have established commercial nuclear power programs but only some of them have developed comprehensive and large scale peaceful nuclear power infrastructure. Although various cooperation and guidance program of nuclear power infrastructure, developing appropriate environment and infrastructure of nuclear power plant is still challenging problems for developing countries launching nuclear power program. With increasing the demand of safety and safeguard from international society, creating appropriate infrastructure becomes essential requirements in national nuclear power program. In the viewpoint of developing countries, without sufficient explanation and proper guidance, infrastructure could be seen only as another barrier in its nuclear power program. The importance of infrastructure development would be obscured by ostensible business and infrastructure program can result in increasing entering barriers to peaceful nuclear power application field without benefits to developing countries and international community. To avoid this situation by providing enough explanation and realistic case example and cooperate with the countries wanting to establish comprehensive nuclear power infrastructure in the peaceful applications, we are creating the education program of infrastructure development with basic guidelines of the IAEA infrastructure series and Korean experiences from least developed country to advanced country

  6. Knowledge Management (KM) Risk Assessment of Critical Knowledge Loss in an Organization with Expanding Nuclear Power Program

    International Nuclear Information System (INIS)

    Mohsin, M.

    2014-01-01

    Risk and KM risk assessment of critical knowledge loss: • Risk is defined in the Project Management Body of Knowledge (PMBOK,2004) as an event or unclear situation that will influence the timing, cost and quality of a project. • This study considers attrition due to retirements of its workforce -- A risk for the organization as it has implications of loss of knowledge for the organization and thereby on its quality and output. • This study assesses the magnitude of the anticipated Risk of Knowledge Loss in three Operational NPPs namely CNPGS (C-1 and C-2) and K-1 based on the factor of Time until Retirement

  7. NASA program planning on nuclear electric propulsion

    International Nuclear Information System (INIS)

    Bennett, G.L.; Miller, T.J.

    1992-03-01

    As part of the focused technology planning for future NASA space science and exploration missions, NASA has initiated a focused technology program to develop the technologies for nuclear electric propulsion and nuclear thermal propulsion. Beginning in 1990, NASA began a series of interagency planning workshops and meetings to identify key technologies and program priorities for nuclear propulsion. The high-priority, near-term technologies that must be developed to make NEP operational for space exploration include scaling thrusters to higher power, developing high-temperature power processing units, and developing high power, low-mass, long-lived nuclear reactors. 28 refs

  8. Iran's Nuclear Program: Recent Developments

    National Research Council Canada - National Science Library

    Squassoni, Sharon

    2006-01-01

    International Atomic Energy Agency (IAEA) inspections since 2003 have revealed almost two decades' worth of undeclared nuclear activities in Iran, including uranium enrichment and plutonium separation efforts...

  9. Iran's Nuclear Program: Recent Developments

    National Research Council Canada - National Science Library

    Squassoni, Sharon

    2007-01-01

    International Atomic Energy Agency (IAEA) inspections since 2003 have revealed two decades' worth of undeclared nuclear activities in Iran, including uranium enrichment and plutonium separation efforts...

  10. Iran's Nuclear Program: Recent Developments

    National Research Council Canada - National Science Library

    Squassoni, Sharon

    2006-01-01

    International Atomic Energy Agency (IAEA) inspections since 2003 have revealed almost two decades worth of undeclared nuclear activities in Iran, including uranium enrichment and plutonium separation efforts...

  11. Iran's Nuclear Program: Recent Developments

    National Research Council Canada - National Science Library

    Squassoni, Sharon

    2006-01-01

    International Atomic Energy Agency (IAEA) inspections since 2003 have revealed two decades worth of undeclared nuclear activities in Iran, including uranium enrichment and plutonium separation efforts...

  12. HSE Nuclear Safety Research Program

    Energy Technology Data Exchange (ETDEWEB)

    Bagley, M.J. [Health and Safety Executive, Sheffield (United Kingdom)

    1995-12-31

    HSE funds two programmes of nuclear safety research: a programme of {approx} 2.2M of extramural research to support the Nuclear Safety Division`s regulatory activities and a programme of {approx} 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author).

  13. HSE Nuclear Safety Research Program

    International Nuclear Information System (INIS)

    Bagley, M.J.

    1995-01-01

    HSE funds two programmes of nuclear safety research: a programme of ∼ 2.2M of extramural research to support the Nuclear Safety Division's regulatory activities and a programme of ∼ 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author)

  14. Conducting a Nuclear Security Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Leach, Janice [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Snell, Mark K. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-06-01

    There are three general steps that make up a nuclear security assessment: 1. Develop data Libraries that indicate how effective the physical protection measures are both individually but also as parts of subsystems and actual systems. 2. Perform Path Analysis 3. Perform Scenario Analysis. Depending upon the nature and objectives of the assessment not all three of these steps may need to be performed; for example, at facilities with simple layouts there may not be a need to perform path analysis. Each of these steps is described within this report.

  15. Quality assurance program for nuclear power plants

    International Nuclear Information System (INIS)

    Gamon, T.H.

    1976-02-01

    The Topical Report presented establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of the report

  16. Quality assurance program for nuclear power plants

    International Nuclear Information System (INIS)

    Gamon, T.H.

    1976-06-01

    This topical report establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of this report

  17. Nuclear safety training program (NSTP) for dismantling

    International Nuclear Information System (INIS)

    Cretskens, Pieter; Lenie, Koen; Mulier, Guido

    2014-01-01

    European Control Services (GDF Suez) has developed and is still developing specific training programs for the dismantling and decontamination of nuclear installations. The main topic in these programs is nuclear safety culture. We therefore do not focus on technical training but on developing the right human behavior to work in a 'safety culture' environment. The vision and techniques behind these programs have already been tested in different environments: for example the dismantling of the BN MOX Plant in Dessel (Belgium), Nuclear Safety Culture Training for Electrabel NPP Doel..., but also in the non-nuclear industry. The expertise to do so was found in combining the know-how of the Training and the Nuclear Department of ECS. In training, ECS is one of the main providers of education in risky tasks, like elevation and manipulation of charges, working in confined spaces... but it does also develop training on demand to improve safety in a certain topic. Radiation Protection is the core business in the Nuclear Department with a presence on most of the nuclear sites in Belgium. Combining these two domains in a nuclear safety training program, NSTP, is an important stage in a dismantling project due to specific contamination, technical and other risks. It increases the level of safety and leads to a harmonization of different working cultures. The modular training program makes it possible to evaluate constantly as well as in group or individually. (authors)

  18. Update on DOE's Nuclear Energy University Program

    International Nuclear Information System (INIS)

    Lambregts, Marsha J.

    2009-01-01

    The Nuclear Energy University Program (NEUP) Office assists the U.S. Department of Energy Office of Nuclear Energy (DOE-NE) by administering its University Program. To promote accountable relationships between universities and the Technical Integration Offices (TIOs)/Technology Development Offices (TDOs), a process was designed and administered which includes two competitive Requests for Proposals (RFPs) and two Funding Opportunity Announcements (FOAs) in the following areas: (1) Research and Development (R and D) Grants, (2) Infrastructure improvement, and (3) Scholarships and Fellowships. NEUP will also host periodic reviews of university mission-specific R and D that document progress, reinforce accountability, and assess return on investment; sponsor workshops that inform universities of the Department's research needs to facilitate continued alignment of university R and D with NE missions; and conduct communications activities that foster stakeholder trust, serve as a catalyst for accomplishing NEUP objectives, and provide national visibility of NEUP activities and accomplishments. Year to date efforts to achieve these goals will be discussed.

  19. Nuclear medicine research: an evaluation of the ERDA program

    International Nuclear Information System (INIS)

    1976-08-01

    Legislation which established the Energy Research and Development Administration (ERDA) January 19, 1975, stipulated that this new agency should be responsible for all activities previously assigned to the Atomic Energy Commission (AEC) and not specifically assigned to other agencies. Such activities included the nuclear medicine research program of the AEC Division of Biomedical and Environmental Research (DBER). To determine whether continuation of this program under the broader ERDA mission of energy-related research was in fact appropriate, a special task force was appointed in January 1975 by Dr. James L. Liverman, the director of DBER. This task force, comprised of established scientists knowledgeable about issues related to nuclear medicine either currently or in the past, was charged specifically to assess the historical impact of the AEC/ERDA nuclear medicine program on the development of nuclear medicine, the current status of this program, and its future role within the structure of ERDA. The specific recommendations, in brief form, are as follows: the federal government should continue to support the medical application of nuclear technology; ERDA should retain primary responsibility for support and management of federal nuclear medicine research programs; and management and emphasis of the ERDA nuclear medicine program require modification in certain areas, which are set forth

  20. 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

  1. Establishing Requirements for Nuclear Engineering Educational Programs

    International Nuclear Information System (INIS)

    Geraskin, N.I.; Kosilov, A.N.; Sbaffoni, M.M.

    2014-01-01

    Conclusions: » There is no single approach in curricula development. » New programmes must fit into national requirements. » Because of the strong international interdependency of all nations using nuclear energy, it is critically important that a competent staff is engaged at all nuclear power plants in every country. » International approach for benchmarking university programs is to be in place with a direct benefit to the countries with new nuclear power projects

  2. Assessment of nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    1975-09-01

    The status of technology and the regulatory situation are summarized; the level of Federal support believed to be necessary to ensure that the nuclear option plays its role in the National Energy Plan is estimated. The assessment is based on a review of the open literature (no proprietary information), preliminary economic calculations, and experience of the Du Pont staff in the design, construction, and operation of nuclear facilities at Hanford and Savannah River. Because of the limited time available for the review, the conclusions and recommendations are preliminary, but they should provide an appropriate point of departure for planning purposes. A summary of recommendations and conclusions is provided at the beginning of the report, a current status of the applicable technology is given in Appendix B, and a glossary of terms is provided at the end of the report

  3. Towards 'green' Vinca - Vinca institute nuclear program

    International Nuclear Information System (INIS)

    Subotic, K.; Pesic, M.P.; Ljubenov, V.Lj.; Sotic, O.; Plecas, I.; Milosevic, M.J.; Peric, A.; Pavlovic, R.

    2002-01-01

    In order to solve the main nuclear and radiation safety problems in the Vinca Institute of Nuclear Sciences related to the inadequate storage conditions for the RA research reactor spent fuel, further decommissioning of the RA reactor and construction of central national radioactive waste long term storage, the 'Vinca Nuclear Decommissioning Program' is initiated during first months of 2002. A systematic and interrelated approach to the solving of the problems is proposed. Program will consist of set of Projects and Activities, planned to be done in the next 10 years. Realization of Program should improve nuclear and radiation safety and should solve problems arose in the previous period. The paper describes existing conditions related to the RA reactor and spent fuel pools, the main actions done in previous period, program goals and proposed organization structure. (author)

  4. Bohunice Nuclear Power Plant Safety Upgrading Program

    International Nuclear Information System (INIS)

    Toth, A.; Fagula, L.

    1996-01-01

    Bohunice nuclear Power Plant generation represents almost 50% of the Slovak republic electric power production. Due to such high level of commitment to nuclear power in the power generation system, a special attention is given to safe and reliable operation of NPPs. Safety upgrading and operational reliability improvement of Bohunice V-1 NPP was carried out by the Bohunice staff continuously since the plant commissioning. In the 1990 - 1993 period extensive projects were realised. As a result of 'Small Reconstruction of the Bohunice V-1 NPP', the standards of both the nuclear safety and operational reliability have been significantly improved. The implementation of another modifications that will take place gradually during extended refuelling outages and overhauls in the course of 1996 through 1999, is referred to as the Gradual Reconstruction of the Bohunice V-1 Plant. The general goal of the V-1 NPP safety upgrading is the achievement of internationally acceptable level of nuclear safety. Extensive and financially demanding modification process of Bohunice V-2 NPP is likely to be implemented after a completion of the Gradual Reconstruction of the Bohunice V-1 NPP, since the year 1999. With this in mind, a first draft of the strategy of the Bohunice V-2 NPP upgrading program based on Probabilistic Safety assessment consideration was developed. A number of actions with a general effect on Bohunice site safety is evident. All these activities are aimed at reaching the essential objective of Bohunice NPP Management - to ensure a safe, reliable and effective electric energy and heat generation at the Bohunice site. (author)

  5. EPRI nuclear power plant decommissioning technology program

    International Nuclear Information System (INIS)

    Kim, Karen S.; Bushart, Sean P.; Naughton, Michael; McGrath, Richard

    2011-01-01

    The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. (author)

  6. Initiatives in training program evaluation outside the nuclear utility industry

    International Nuclear Information System (INIS)

    Allen, C.J.

    1987-01-01

    Training literature is reviewed, and program evaluative practices outside the nuclear utility industry are reported. The findings indicate some innovations in philosophy and practice and program evaluation, although not necessarily in the context of evaluation as a route to assessing the impact of training. Program evaluation is described in the context of the impact of training, suggesting continued efforts to accept a multivariate concept of individual and organizational performance

  7. Nuclear medicine quality assurance program in Argentina

    International Nuclear Information System (INIS)

    Levi de Cabrejas, Mariana; Arashiro, Jorge G.; Giannone, Carlos A.

    1999-01-01

    A two steps program has been implemented: the first one is the quality control of the equipment and the second one the development of standard procedures for clinical studies of patients. A training program for doctors and technicians of the nuclear medicine laboratories was carried out. Workshops on instrumentation and quality assurance in nuclear medicine have been organized in several parts of the country. A joint program of the CNEA and the University of Buenos Aires has trained medical physicists. A method has been established to evaluate the capability of the laboratories to produce high quality images and to follow up the implementation of the quality control program

  8. Review of EPRI Nuclear Human Factors Program

    International Nuclear Information System (INIS)

    Hanes, L.F.; O'Brien, J.F.

    1996-01-01

    The Electric Power Research Institute (EPRI) Human Factors Program, which is part of the EPRI Nuclear Power Group, was established in 1975. Over the years, the Program has changed emphasis based on the shifting priorities and needs of the commercial nuclear power industry. The Program has produced many important products that provide significant safety and economic benefits for EPRI member utilities. This presentation will provide a brief history of the Program and products. Current projects and products that have been released recently will be mentioned

  9. Lessons learned from Spain's nuclear program

    International Nuclear Information System (INIS)

    Garcia Rodriguez, A.

    1993-01-01

    The commercial nuclear program in Spain dates back to the beginning of the 1960s. There are currently nine units in operation, one more has been decommissioned and a further five are in different phases of construction but under nuclear moratorium since 1983. This article gives a general overview of the program, the criteria applied, what it has meant to and required of the industry and, finally, what lessons have been learned. (author) 2 figs

  10. Schedule of the nuclear program

    International Nuclear Information System (INIS)

    Heigl, F.

    1977-01-01

    The lecure tries to explain the main phases which must be passed to establish nuclear power plants, the feasibility phase, preconstruction and construction phase. Each phase consists of a lot of activities which are commented. Further the lecture tries to give some ideas of durances and dependence between the phases or activities to get a complete time schedule of the realization of a nuclear power project. (HP) [de

  11. Nuclear Engineering Academic Programs Survey, 2003

    International Nuclear Information System (INIS)

    Science and Engineering Education, Oak Ridge Institute for Science and Education

    2004-01-01

    The survey includes degrees granted between September 1, 2002 and August 31, 2003. Thirty-three academic programs reported having nuclear engineering programs during the survey time period and all responded (100% response rate). Three of the programs included in last year's report were discontinued or out-of-scope in 2003. One new program has been added to the list. This year the survey data include U.S. citizenship, gender, and race/ethnicity by degree level

  12. Revised inspection program for nuclear power plants

    International Nuclear Information System (INIS)

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) regulates nuclear power plants to assure adequate protection of the public and the environment from the dangers associated with nuclear materials. NRC fulfills this responsibility through comprehensive safety reviews of nuclear facilities, licensing of organizations that use nuclear materials, and continuing inspection. The NRC inspection program is currently conducted from the five regional offices in or near Philadelphia, Atlanta, Chicago, Dallas and San Francisco. Inspectors travel from the regional offices to nuclear power plants in various phases of construction, test and operation in order to conduct inspections. However, in June 1977 the Commission approved a revision to the inspection program that will include stationing inspectors at selected plants under construction and at all plants in operation. In addition, the revised program provides for appraising the performance of licensees on a national basis and involves more direct measurement and observation by NRC inspectors of work and tests in progress. The program also includes enhanced career management consisting of improved training and career development for inspectors and other professionals. The report was requested in the Conference Report on the NRC Authorization for Appropriations for Fiscal Year 1978. The report provides a discussion of the basis for both the current and revised inspection programs, describes these programs, and shows how the NRC inspection force will be trained and utilized. In addition, the report includes a discussion of the actions that will be taken to assure the objectivity of inspectors

  13. Canadian Nuclear Safety Commission's intern program

    International Nuclear Information System (INIS)

    Gilmour, P.E.

    2002-01-01

    The Intern Program was introduced at the Canadian Nuclear Safety Commission, Canada's Nuclear Regulator in response to the current competitive market for engineers and scientists and the CNSC's aging workforce. It is an entry level staff development program designed to recruit and train new engineering and science graduates to eventually regulate Canada's nuclear industry. The program provides meaningful work experience and exposes the interns to the general work activities of the Commission. It also provides them with a broad awareness of the regulatory issues in which the CNSC is involved. The intern program is a two-year program focusing on the operational areas and, more specifically, on the generalist functions of project officers. (author)

  14. Green Vinca - Vinca Institute nuclear decommissioning program

    International Nuclear Information System (INIS)

    Pesic, M.; Subotic, K.; Ljubenov, V.; Sotic, O.

    2003-01-01

    Current conditions related to the nuclear and radiation safety in the Vinca Institute of Nuclear Sciences, Belgrade, Serbia and Montenegro are the result of the previous nuclear programs in the former Yugoslavia and strong economic crisis during the previous decade. These conditions have to be improved as soon as possible. The process of establishment and initialisation of the Vinca Institute Nuclear Decommissioning (VIND) Program, known also as the 'Green Vinca' Program supported by the Government of the Republic Serbia, is described in this paper. It is supposed to solve all problems related to the accumulated spent nuclear fuel, radioactive waste and decommissioning of RA research reactor. Particularly, materials associated to the RA reactor facility and radioactive wastes from the research, industrial, medical and other applications, generated in the previous period, which are stored in the Vinca Institute, are supposed to be proper repackaged and removed from the Vinca site to some other disposal site, to be decided yet. Beside that, a research and development program in the modern nuclear technologies is proposed with the aim to preserve experts, manpower and to establish a solid ground for new researchers in field of nuclear research and development. (author)

  15. State Program Integrity Assessment (SPIA)

    Data.gov (United States)

    U.S. Department of Health & Human Services — The State Program Integrity Assessment (SPIA) is the Centers for Medicare and Medicaid Services (CMS) first national data collection on state Medicaid program...

  16. Nuclear Criticality Safety Department Qualification Program

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1996-01-01

    The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSD technical and managerial qualification as required by the Y-1 2 Training Implementation Matrix (TIM). This Qualification Program is in compliance with DOE Order 5480.20A and applicable Lockheed Martin Energy Systems, Inc. (LMES) and Y-1 2 Plant procedures. It is implemented through a combination of WES plant-wide training courses and professional nuclear criticality safety training provided within the department. This document supersedes Y/DD-694, Revision 2, 2/27/96, Qualification Program, Nuclear Criticality Safety Department There are no backfit requirements associated with revisions to this document

  17. Environmental assessment [of nuclear installations

    International Nuclear Information System (INIS)

    Townsley, M.

    1989-01-01

    The European Community has introduced a directive which instructs that for all projects likely to have a significant effect on the environment consent should only be given after a rigorous assessment of such effects has been carried out and presented as an environmental statement. Projects requiring environmental assessment include nuclear power stations, any thermal power station over 300MW, any radioactive waste storage or disposal facility, any installation which produces electricity, power lines, installations for fuel production, fuel reprocessing, radioactive waste processing and fuel enrichment. The statement must include a description of the likely effects, direct and indirect, on the environment of the development, with reference to human beings, flora, fauna, soil, water, air, climate, landscape, interactions of two or more of these, material assets and cultural heritage. Measures to avoid or remedy the impact must be included. (U.K.)

  18. Self-assessment program and actions in ANAV

    International Nuclear Information System (INIS)

    2004-01-01

    Since 1999, the Association Nuclear Asco-Vandellos II, AIE (ANAV) has a self-assessment program in place and controls and tracks the actions with the support of different databases. This article describes the improvements made in the self-assessment programs and actions of ANAV between 1999 up to the present, all the fruit of the experience gained in the application of these programs, Sector guidelines and international trends, as well as standardization with the other Spanish nuclear power plants. (Author)

  19. Behavioral reliability program for the nuclear industry. Technical report

    International Nuclear Information System (INIS)

    Buchanan, J.C.; Davis, S.O.; Dunnette, M.D.; Meyer, P.; Sharac, J.

    1981-07-01

    The subject of the study was the development of standards for a behavioral observation program which could be used by the NRC licensed nuclear industry to detect indications of emotional instability in its employees who have access to protected and vital areas. Emphasis was placed on those observable characteristics which could be assessed by supervisors or peers in a work environment. The behavioral reliability program, as was defined in this report, encompasses the concept and basic components of the program, the definition of the behavioral reliability program, the definition of the behavioral reliability criterion, and a set of instructions for the creation and implementation of the program by an individual facility

  20. Iran's nuclear program - for power generation or nuclear weapons?

    International Nuclear Information System (INIS)

    Kippe, Halvor

    2008-11-01

    This report addresses the development of a nuclear infrastructure in Iran, and assessments are made on the near-term potential this infrastructure might yield of either nuclear power or nuclear arms production. The most significant facilities are treated in a more elaborate fashion, as these are assumed to have key roles in either a true civilian programme, or in the prospect of weapons-grade fissile material production. The future potential capacity for the latter is calculated under certain presumptions, both in the case that Iran focuses its efforts on uranium-based nuclear weapons, and in the case that it should choose the plutonium path to nuclear weapons. All the conclusions and findings in this report are based on technological considerations. This means that social or political assessments have not prevailed, rather the picture of Iran's nuclear programme is drawn through descriptions and assessments of facilities and systems, and their role in the bigger context. Definite conclusions have not been made as to whether Iran's nuclear programme currently is aimed towards nuclear arms or nuclear power. The secrecy surrounding some of the most prominent nuclear sites together with more or less credible allegations of purely weapons-related activities in the past, make it hard not to conclude that Iran until the disclosures in 2002 made as great an effort as it could on its way on developing nuclear weapons covertly. The scope of today's nuclear programme seems, on the other hand, most likely to be in part to help relieve the ever-increasing need for energy, although considerable deficits to this strategy are identified, at the same time as the Iranian people are united in a giant, high-prestige project in defiance of massive international pressure. Adding to this is a much-feared ability to rapidly being able to redirect their nuclear efforts, and develop nuclear arms in perhaps as little as one year. This so-called break-out scenario, where Iran presumably

  1. Development of nuclear safety issues program

    Energy Technology Data Exchange (ETDEWEB)

    Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K

    2006-12-15

    The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants.

  2. Development of nuclear safety issues program

    International Nuclear Information System (INIS)

    Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K.

    2006-12-01

    The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants

  3. Environmental assessment report: Nuclear Test Technology Complex

    International Nuclear Information System (INIS)

    Tonnessen, K.; Tewes, H.A.

    1982-08-01

    The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report

  4. Nuclear programs in India and Pakistan

    Science.gov (United States)

    Mian, Zia

    2014-05-01

    India and Pakistan launched their respective nuclear programs in the 1940s and 1950s with considerable foreign technical support, especially from the United States Atoms for Peace Program. The technology and training that was acquired served as the platform for later nuclear weapon development efforts that included nuclear weapon testing in 1974 and in 1998 by India, and also in 1998 by Pakistan - which had illicitly acquired uranium enrichment technology especially from Europe and received assistance from China. As of 2013, both India and Pakistan were continuing to produce fissile material for weapons, in the case of India also for nuclear naval fuel, and were developing a diverse array of ballistic and cruise missiles. International efforts to restrain the South Asian nuclear build-up have been largely set aside over the past decade as Pakistani support became central for the U.S. war in Afghanistan and as U.S. geopolitical and economic interests in supporting the rise of India, in part as a counter to China, led to India being exempted both from U.S non-proliferation laws and international nuclear trade guidelines. In the absence of determined international action and with Pakistan blocking the start of talks on a fissile material cutoff treaty, nuclear weapon programs in South Asia are likely to keep growing for the foreseeable future.

  5. Nuclear programs in India and Pakistan

    Energy Technology Data Exchange (ETDEWEB)

    Mian, Zia [Program on Science and Global Security, Princeton University, Princeton, New Jersey (United States)

    2014-05-09

    India and Pakistan launched their respective nuclear programs in the 1940s and 1950s with considerable foreign technical support, especially from the United States Atoms for Peace Program. The technology and training that was acquired served as the platform for later nuclear weapon development efforts that included nuclear weapon testing in 1974 and in 1998 by India, and also in 1998 by Pakistan - which had illicitly acquired uranium enrichment technology especially from Europe and received assistance from China. As of 2013, both India and Pakistan were continuing to produce fissile material for weapons, in the case of India also for nuclear naval fuel, and were developing a diverse array of ballistic and cruise missiles. International efforts to restrain the South Asian nuclear build-up have been largely set aside over the past decade as Pakistani support became central for the U.S. war in Afghanistan and as U.S. geopolitical and economic interests in supporting the rise of India, in part as a counter to China, led to India being exempted both from U.S non-proliferation laws and international nuclear trade guidelines. In the absence of determined international action and with Pakistan blocking the start of talks on a fissile material cutoff treaty, nuclear weapon programs in South Asia are likely to keep growing for the foreseeable future.

  6. Nuclear programs in India and Pakistan

    International Nuclear Information System (INIS)

    Mian, Zia

    2014-01-01

    India and Pakistan launched their respective nuclear programs in the 1940s and 1950s with considerable foreign technical support, especially from the United States Atoms for Peace Program. The technology and training that was acquired served as the platform for later nuclear weapon development efforts that included nuclear weapon testing in 1974 and in 1998 by India, and also in 1998 by Pakistan - which had illicitly acquired uranium enrichment technology especially from Europe and received assistance from China. As of 2013, both India and Pakistan were continuing to produce fissile material for weapons, in the case of India also for nuclear naval fuel, and were developing a diverse array of ballistic and cruise missiles. International efforts to restrain the South Asian nuclear build-up have been largely set aside over the past decade as Pakistani support became central for the U.S. war in Afghanistan and as U.S. geopolitical and economic interests in supporting the rise of India, in part as a counter to China, led to India being exempted both from U.S non-proliferation laws and international nuclear trade guidelines. In the absence of determined international action and with Pakistan blocking the start of talks on a fissile material cutoff treaty, nuclear weapon programs in South Asia are likely to keep growing for the foreseeable future

  7. Waste management in Canadian nuclear programs

    International Nuclear Information System (INIS)

    Dyne, P.J.

    1975-08-01

    The report describes the wide-ranging program of engineering developments and applications to provide the Canadian nuclear industry with the knowledge and expertise it needs to conduct its waste management program. The need for interim dry storage of spent fuel, and the storage and ultimate disposal of waste from fuel reprocessing are examined. The role of geologic storage in AECL's current waste management program is also considered. (R.A.)

  8. Waste Isolation Safety Assessment Program scenario analysis methods for use in assessing the safety of the geologic isolation of nuclear waste

    International Nuclear Information System (INIS)

    Greenborg, J.; Winegardner, W.K.; Pelto, P.J.; Voss, J.W.; Stottlemyre, J.A.; Forbes, I.A.; Fussell, J.B.; Burkholder, H.C.

    1978-11-01

    The relative utility of the various safety analysis methods to scenario analysis for a repository system was evaluated by judging the degree to which certain criteria are satisfied by use of the method. Six safety analysis methods were reviewed in this report for possible use in scenario analysis of nuclear waste repositories: expert opinion, perspectives analysis, fault trees/event trees, Monte Carlo simulation, Markov chains, and classical systems analysis. Four criteria have been selected. The criteria suggest that the methods: (1) be quantitative and scientifically based; (2) model the potential disruptive events and processes, (3) model the system before and after failure (sufficiently detailed to provide for subsequent consequence analysis); and (4) be compatible with the level of available system knowledge and data. Expert opinion, fault trees/event trees, Monte Carlo simulation and classical systems analysis were judged to have the greatest potential appliation to the problem of scenario analysis. The methods were found to be constrained by limited data and by knowledge of the processes governing the system. It was determined that no single method is clearly superior to others when measured against all the criteria. Therefore, to get the best understanding of system behavior, a combination of the methods is recommended. Monte Carlo simulation was judged to be the most suitable matrix in which to incorporate a combination of methods

  9. Federal Nuclear Energy Program: a synopsis

    International Nuclear Information System (INIS)

    1983-01-01

    This document provides an overview of the new nuclear policy objectives and initiatives and summarizes the Department of Energy programmatic strategy to realize the full nuclear potential. Analyses have been made within the context of prevailing and potential economic conditions, alternative energy options and prior nuclear performance and growth patterns. The Department's organizational structure, which was realigned in June 1982 to conform with the activities mandated by the Administration's policy, is also discussed. The individual program elements for nuclear research and development are described as they contribute to a fully integrated fuel cycle and power generation system. Federal and commercial responsibilities for developmental activity are delinated, and relationship of the programs to broad national energy objectives is specified

  10. Human resources in nuclear power program

    International Nuclear Information System (INIS)

    Machi, Sueo

    2008-01-01

    Nuclear power utilization within 2020 horizon is expanding in Asia, particularly in Japan, China, India, Republic of Korea, Vietnam and Indonesia. The nuclear energy policy iof Japan sees the increase of nuclear power contribution for energy security and to control CO 2 emission with the contribution ratio through the 21 st century kept at the current level of 30-40% or even higher. Japan expects its first reprocessing plant to be operational in 2007 and its first commercial fast breeder reactor operational in 2050. Starting with her experience with the operation of its first research reactor in 1957, a power demonstration reactor from USA in 1963; the first commercial 166 MW power plant from UK in 1966 and then its first commercial 375 MW light water reactor from USA in 1970, Japan developed her own nuclear reactor technology. Today, Japan has 55 operating nuclear power plants (NPPs) totaling 49 GW which supply 30% of its electricity needs. There are two NPPs under construction and 11 additional NPPs to be completed by 2017. Japan's experience showed that engineers in the nuclear, mechanical, electrical, material and chemical fields are needed to man their nuclear power plant. For the period 1958 to about 1970, there was a rapid increase in the number of students enrolled for their bachelor of science majoring in nuclear science and technology but this number of enrollees leveled off beyond 1970 up to 2002. For those pursuing their masters of science degree in this field, there was a steady but moderate rise in the number of students from 1958 to 2002. The population of students in the Ph.D program in nuclear science and technology had the lowest number of enrollees and lowest level of increase from 1958 to 2002. The courses offered at the university for nuclear power are nuclear reactor physics and engineering, nuclear reactor safety engineering and radiation safety. Prior to graduation, the students undergo training at a nuclear research institute, nuclear power

  11. Department of Energy Nuclear Energy Standards Program

    International Nuclear Information System (INIS)

    Silver, E.G.

    1980-01-01

    The policy with respect to the development and use of standards in the Department of Energy (DOE) programs concerned with maintaining and developing the nuclear option for the civilian sector (both in the form of the currently used light water reactors and for advanced concepts including the Liquid Metal Fast Breeder Reactor), is embodied in a Nuclear Standards Policy, issued in 1978, whose perspectives and philosophy are discussed

  12. Nuclear pharmacy certificate program: distance learning

    International Nuclear Information System (INIS)

    Shaw, S.M.

    1998-01-01

    The Nuclear Pharmacy Certificate Program (NPCP) was developed to meet the need for licensed pharmacists wishing to change career paths and enter the practice of nuclear pharmacy. Additionally, the NPCP benefits employers that wish to employ a nuclear pharmacist in lieu of waiting for graduates that are available only at one time yearly from a college of pharmacy. The NPCP is not intended to replace traditional nuclear pharmacy education in academic institutions, but to offer an another option to pharmacists and potential employers. The NPCP is divided into two components. One component involves over 130 hours of instruction through videotapes and accompanying workbooks. This component is completed while working in a nuclear pharmacy and with the assistance of a nuclear pharmacist serving as a supervisor. The nuclear pharmacist is available to answer questions and to administer examinations over the videotape material. Examinations are prepared by Purdue faculty and returned for grading. Scores on exams must reflect learning to the same degree as in an academic environment. In the second component of the NPCP, the trainee attends a two-week session in the School of Pharmacy at Purdue University. the trainee must complete a significant portion of the videotape material before the on-campus session. In the on-campus component, videotape material is reinforced and expanded by laboratory exercises and lectures in dedicated, fully-equipped laboratories employed in the School of Pharmacy undergraduate program in nuclear pharmacy. Nuclear pharmacy faculty and consultants provide individualized instruction to each trainee. Assimilation of lecture and laboratory material is determined through several examinations. A comprehensive examination is administered which includes content from the videotape-workbook component of the NPCP. Certification is awarded to trainees who have completed the program and demonstrated their knowledge and competence by examination. Almost 200

  13. Progress of Nuclear Hydrogen Program in Korea

    International Nuclear Information System (INIS)

    Lee, Won Jae

    2009-01-01

    To cope with dwindling fossil fuels and climate change, it is clear that a clean alternative energy that can replace fossil fuels is required. Hydrogen is considered a promising future energy solution because it is clean, abundant and storable and has a high energy density. As other advanced countries, the Korean government had established a long-term vision for transition to the hydrogen economy in 2005. One of the major challenges in establishing a hydrogen economy is how to produce massive quantities of hydrogen in a clean, safe and economical way. Among various hydrogen production methods, the massive, safe and economic production of hydrogen by water splitting using a very high temperature gas-cooled reactor (VHTR) can provide a success path to the hydrogen economy. Particularly in Korea, where usable land is limited, the nuclear production of hydrogen is deemed a practical solution due to its high energy density. To meet the expected demand for hydrogen, the Korea Atomic Energy Institute (KAERI) launched a nuclear hydrogen program in 2004 together with Korea Institute of Energy Research (KIER) and Korea Institute of Science and Technology (KIST). Then, the nuclear hydrogen key technologies development program was launched in 2006, which aims at the development and validation of key and challenging technologies required for the realization of the nuclear hydrogen production demonstration system. In 2008, Korean Atomic Energy Commission officially approved a long-term development plan of the nuclear hydrogen system technologies as in the figure below and now the nuclear hydrogen program became the national agenda. This presentation introduces the current status of nuclear hydrogen projects in Korea and the progress of the nuclear hydrogen key technologies development. Perspectives of nuclear process heat applications are also addressed

  14. Nuclear energy - a professional assessment

    Energy Technology Data Exchange (ETDEWEB)

    1984-01-01

    The report falls under the headings: the role of the Watt Committee in nuclear energy; supply and demand, and economics of nuclear power; technical means (types of reactor; fuel cycle; nuclear energy for applications other than large-scale electricity generation); availability of resources (nuclear fuel; British industrial capacity; manpower requirements for a British nuclear power programme); environment (environmental issues; disposal of radioactive wastes); balance of risk and advantage in the peaceful use of nuclear energy (proliferation; safety and risk; benefits; public acceptability, awareness, education); summary and general comments.

  15. Nuclear energy - a professional assessment

    International Nuclear Information System (INIS)

    1984-01-01

    The report falls under the headings: the role of the Watt Committee in nuclear energy; supply and demand, and economics of nuclear power; technical means (types of reactor; fuel cycle; nuclear energy for applications other than large-scale electricity generation); availability of resources (nuclear fuel; British industrial capacity; manpower requirements for a British nuclear power programme); environment (environmental issues; disposal of radioactive wastes); balance of risk and advantage in the peaceful use of nuclear energy (proliferation; safety and risk; benefits; public acceptability, awareness, education); summary and general comments. (U.K.)

  16. The cost of French military nuclear programs

    International Nuclear Information System (INIS)

    Barrillot, B.

    1999-02-01

    The author tries to find out the real cost of French nuclear weaponry. According to this study the total cost of the French military nuclear programs for 1960-1998 period is about 1499 milliard francs (MdF). This cost can be distributed as follows: i) fabrication of the bomb: 690 MdF; ii) display of the bomb: 727 MdF; iii) control of the bomb: 50 Mdf; iv) protection against nuclear attacks: 9 MdF; and v) dismantling of the bomb: 23 MdF. It goes without saying that these figures exceed by far those given by French authorities. (A.C.)

  17. Nuclear Power Reactor simulator - based training program

    International Nuclear Information System (INIS)

    Abdelwahab, S.A.S.

    2009-01-01

    nuclear power stations will continue playing a major role as an energy source for electric generation and heat production in the world. in this paper, a nuclear power reactor simulator- based training program will be presented . this program is designed to aid in training of the reactor operators about the principles of operation of the plant. also it could help the researchers and the designers to analyze and to estimate the performance of the nuclear reactors and facilitate further studies for selection of the proper controller and its optimization process as it is difficult and time consuming to do all experiments in the real nuclear environment.this program is written in MATLAB code as MATLAB software provides sophisticated tools comparable to those in other software such as visual basic for the creation of graphical user interface (GUI). moreover MATLAB is available for all major operating systems. the used SIMULINK reactor model for the nuclear reactor can be used to model different types by adopting appropriate parameters. the model of each component of the reactor is based on physical laws rather than the use of look up tables or curve fitting.this simulation based training program will improve acquisition and retention knowledge also trainee will learn faster and will have better attitude

  18. Maintaining quality control in a nontraditional nuclear technology degree program

    International Nuclear Information System (INIS)

    DeSain, G.W.

    1989-01-01

    Regents College, created by the Board of Regents of the University of The State on New York in 1971, has been offering, since January 1985, AS and BS degrees in nuclear technology. The impetus for establishing the nuclear technology degrees came from nuclear utility management and had to do with the US Nuclear Regulatory Commission proposed rule regarding degreed operators on shift. There are a variety of ways to earn credits in Regents College degree programs: (1) college courses taken for degree-level credit from regionally accredited colleges; (2) courses sponsored by business, industry, or government that have been evaluated and recommended for credit by the New York National or American Council on Education (ACE's) Program on Noncollegiate Sponsored Instruction (PONSI); (3) military education that has been evaluated by ACE PONSI; (4) approved college-proficiency examinations; and (5) special assessment: an individualized examination of college-level knowledge gained from experience or independent study. Nuclear technology students primarily use college course work, evaluated military education, and proficiency examinations to complete degree programs. However, an increasing number of utilities are having training programs PONSI evaluated, resulting in an increased use of these courses in the nuclear technology degrees. Quality control is a function of several factors described in the paper

  19. Training within the French nuclear power program

    International Nuclear Information System (INIS)

    Jusselin, F.

    1987-01-01

    Training dispensed by the EDF Nuclear and Fossil Generation Division has contributed significantly toward successful startup and operation of French nuclear power plants. In 1986, the time-based availability of 900 MW PWRs totaled 85 %. This is just one example of how EDF training programs have benefited from 150 reactor-years of operating experience and the ensuing opportunities for perfecting and testing of training tool effectiveness. These programs have been adopted by utilities in other countries where suitable local facilities are making advantageous use of EDF training experience and methods. EDF expertise is also transferred to these countries indirectly through the simulator manufacturer

  20. The nuclear analysis program at MURR

    International Nuclear Information System (INIS)

    Glascock, M.D.

    1993-01-01

    The University of Missouri-Columbia (MU) has continually upgraded research facilities and programs at the MU research reactor (MURR) throughout its 26-yr history. The Nuclear Analysis Program (NAP) area has participated in these upgrades over the years. As one of the largest activation analysis laboratories on a university campus, the activities of the NAP are broadly representative of the diversity of applications for activation analysis and related nuclear science. This paper describes the MURR's NAP and several of the research, education, and service projects in which the laboratory is currently engaged

  1. Measurement control program for nuclear material accounting

    International Nuclear Information System (INIS)

    Brouns, R.J.; Roberts, F.P.; Merrill, J.A.; Brown, W.B.

    1980-06-01

    A measurement control program for nuclear material accounting monitors and controls the quality of the measurments of special nuclear material that are involved in material balances. The quality is monitored by collecting data from which the current precision and accuracy of measurements can be evaluated. The quality is controlled by evaluations, reviews, and other administrative measures for control of selection or design of facilities, equipment and measurement methods and the training and qualification of personnel who perform SNM measurements. This report describes the most important elements of a program by which management can monitor and control measurement quality

  2. The objective of this program is to develop innovative DNA detection technologies to achieve fast microbial community assessment. The specific approaches are (1) to develop inexpensive and reliable sequence-proof hybridization DNA detection technology (2) to develop quantitative DNA hybridization technology for microbial community assessment and (3) to study the microbes which have demonstrated the potential to have nuclear waste bioremediation

    International Nuclear Information System (INIS)

    Chen, Chung H.

    2004-01-01

    The objective of this program is to develop innovative DNA detection technologies to achieve fast microbial community assessment. The specific approaches are (1) to develop inexpensive and reliable sequence-proof hybridization DNA detection technology (2) to develop quantitative DNA hybridization technology for microbial community assessment and (3) to study the microbes which have demonstrated the potential to have nuclear waste bioremediation

  3. Programming for a nuclear reactor instrument simulation

    International Nuclear Information System (INIS)

    Cohn, C.

    1988-01-01

    This note discusses 8086/8087 machine-language programming for simulation of nuclear reactor instrument current inputs by means of a digital-analog converter (DAC) feeding a bank of series input resistors. It also shows FORTRAN programming for generating the parameter tales used in the simulation. These techniques would be generally useful for high-speed simulation of quantities varying over many orders of magnitude

  4. Romanian nuclear fuel program: past, present and future

    International Nuclear Information System (INIS)

    Budan, O.; Rotaru, I.; Galeriu, C.A.

    1997-01-01

    The paper presents and comments the policy adopted in Romania for the production of CANDU-6 nuclear fuel before and after 1990. In this paper the word 'past' refers to the period before 1990 and 'present' to the 1990-1997 period. The CANDU-6 nuclear fuel manufacturing started in Romania in December 1983. Neither AECL nor any Canadian nuclear fuel manufacturer were involved in the Romanian industrial nuclear fuel production before 1990. After January 1990, the new created Romanian Electricity Authority (RENEL) assumed the responsibility for the Romanian Nuclear Power Program. It was RENEL's decision to stop, in June 1990, the nuclear fuel production at the Institute for Nuclear Power Reactors (IRNE) Pitesti. This decision was justified by the Canadian specialists team findings, revealed during a general, but well enough technically founded analysis performed at IRNE in the spring of 1990. All fuel manufactured before June 1990 was quarantined as it was considered of suspect quality. By that time more than 31,000 fuel bundles had already been manufactured. This fuel was stored for subsequent assessment. The paper explains the reasons which provoked this decision. The paper also presents the strategy adopted by RENEL after 1990 regarding the Romanian Nuclear Fuel Program. After a complex program done by Romanian and Canadian partners, in November 1994, AECL issued a temporary certification for the Romanian nuclear fuel plant. During the demonstration manufacturing run, as an essential milestone for the qualification of the Romanian fuel supplier for CANDU-6 reactors, 202 fuel bundles were produced. Of these fuel bundles, 66 were part of the Cernavoda NGS Unit 1 first fuel load (the balance was supplied by Zircatec Precision Industries Inc. - ZPI). The industrial nuclear fuel fabrication re-started in Romania in January 1995 under AECL's periodical monitoring. In December 1995, AECL issued a permanent certificate, stating the Romanian nuclear fuel plant as a qualified

  5. Romanian nuclear power program - status and trends

    International Nuclear Information System (INIS)

    Chirica, T.; Condu, M.; Bilegan, I.C.; Glodeanu, F.; Popescu, D.

    1997-01-01

    The paper presents the status and the forecast for the Romanian Nuclear Power Program, as a component of the national strategy of power sector in Romania. The successful commissioning and operation of Cernavoda NPP - Unit 1 consolidated the opinion to go further for completion of Unit 2 to 5 on Cernavoda site. The focus is now on Unit 2, planned to be commissioned in 2001, and on the related projects for radioactive waste treatment and disposal. The Romanian national infrastructure supporting this program is also presented, including the research and development facilities. Romanian nuclear industry represents today one of the most advanced sector in engineering and technology and has the ability to meet the requirements of international codes and standards, proving also excellent quality assurance skills. Romanian nuclear industry has also the capability to compete on third market, for nuclear projects, together with the traditional suppliers. The conclusion of the paper is that for Romania, the nuclear energy is the best solution for future development of power sector, is safe, economic, and ethical. Nuclear sector created in Romania new jobs and activities contributing to the progress of Romanian society. (authors)

  6. Romanian nuclear power program - status and trends

    International Nuclear Information System (INIS)

    Chirica, T.; Condu, M.; Stiopol, M.; Bilegan, I. C.; Glodeanu, F.; Popescu, D.

    1997-01-01

    This paper presents the status and the forecast for the Romanian Nuclear Power Program, as a component of the national strategy of power sector in Romania. The successful commissioning and operation of Cernavoda NPP - Unit 1 consolidated the opinion to go further for completion of Unit 2 to 5 on Cernavoda site. The focus is now on Unit 2, planed to be commissioned in 2001, and on the related projects for radioactive waste treatment and disposal. The Romanian national infrastructure supporting this program is also presented, including the research and development facilities. Romanian nuclear industry represent today one of the most advanced sector in engineering and technology and has the ability to meet the requirements of international codes and standards, proving also excellent quality assurance skills. Romanian nuclear industry has also the capability to compete on third markets, for nuclear projects, together with the traditional suppliers. The conclusion of the paper is that for Romania the nuclear energy is the best solution for future development of power sector, is safe, economic and ethical. Nuclear sector created in Romania new jobs and activities, contributing to the progress of Romanian society. (author). 5 refs

  7. Economic consideration for Indonesia's nuclear power program

    International Nuclear Information System (INIS)

    Ahimsa, D.; Sudarsono, B.

    1987-01-01

    Indonesia experienced relatively high economic growth during the 1970s and the energy supply system was strained to keep up with demand. Several energy studies were thus carried out around 1980, including a nuclear power planning study and a nuclear plant feasibility study. During the 1980s, economic growth rates were subtantially lower, but surprisingly electricity demand remained fairly high. In 1984 it was therefore decided to update previous nuclear power studies. This effort was completed in 1986. Using energy projections and cost estimates developed during the updating of previous nuclear power studies, the paper discusses the economic justification for a nuclear power program in Indonesia. Results of the update, including computer runs of MAED and WASP models supplied by the IAEA, will be presented along with appropriate sensitivity analysis. These results are then analyzed in the light of 1986 developments in international oil price. Preparations for the forthcoming nuclear power program are described, including the construction of a multi-purpose reactor and associated laboratories in Serpong, near Jakarta. (author)

  8. Application of probabilistic risk assessment in nuclear and environmental licensing processes of nuclear reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Mata, Jonatas F.C. da; Vasconcelos, Vanderley de; Mesquita, Amir Z., E-mail: jonatasfmata@yahoo.com.br, E-mail: vasconv@cdtn.br, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2015-07-01

    The nuclear accident at Fukushima Daiichi, occurred in Japan in 2011, brought reflections, worldwide, on the management of nuclear and environmental licensing processes of existing nuclear reactors. One of the key lessons learned in this matter, is that the studies of Probabilistic Safety Assessment and Severe Accidents are becoming essential, even in the early stage of a nuclear development project. In Brazil, Brazilian Nuclear Energy Commission, CNEN, conducts the nuclear licensing. The organism responsible for the environmental licensing is Brazilian Institute of Environment and Renewable Natural Resources, IBAMA. In the scope of the licensing processes of these two institutions, the safety analysis is essentially deterministic, complemented by probabilistic studies. The Probabilistic Safety Assessment (PSA) is the study performed to evaluate the behavior of the nuclear reactor in a sequence of events that may lead to the melting of its core. It includes both probability and consequence estimation of these events, which are called Severe Accidents, allowing to obtain the risk assessment of the plant. Thus, the possible shortcomings in the design of systems are identified, providing basis for safety assessment and improving safety. During the environmental licensing, a Quantitative Risk Analysis (QRA), including probabilistic evaluations, is required in order to support the development of the Risk Analysis Study, the Risk Management Program and the Emergency Plan. This article aims to provide an overview of probabilistic risk assessment methodologies and their applications in nuclear and environmental licensing processes of nuclear reactors in Brazil. (author)

  9. Application of probabilistic risk assessment in nuclear and environmental licensing processes of nuclear reactors in Brazil

    International Nuclear Information System (INIS)

    Mata, Jonatas F.C. da; Vasconcelos, Vanderley de; Mesquita, Amir Z.

    2015-01-01

    The nuclear accident at Fukushima Daiichi, occurred in Japan in 2011, brought reflections, worldwide, on the management of nuclear and environmental licensing processes of existing nuclear reactors. One of the key lessons learned in this matter, is that the studies of Probabilistic Safety Assessment and Severe Accidents are becoming essential, even in the early stage of a nuclear development project. In Brazil, Brazilian Nuclear Energy Commission, CNEN, conducts the nuclear licensing. The organism responsible for the environmental licensing is Brazilian Institute of Environment and Renewable Natural Resources, IBAMA. In the scope of the licensing processes of these two institutions, the safety analysis is essentially deterministic, complemented by probabilistic studies. The Probabilistic Safety Assessment (PSA) is the study performed to evaluate the behavior of the nuclear reactor in a sequence of events that may lead to the melting of its core. It includes both probability and consequence estimation of these events, which are called Severe Accidents, allowing to obtain the risk assessment of the plant. Thus, the possible shortcomings in the design of systems are identified, providing basis for safety assessment and improving safety. During the environmental licensing, a Quantitative Risk Analysis (QRA), including probabilistic evaluations, is required in order to support the development of the Risk Analysis Study, the Risk Management Program and the Emergency Plan. This article aims to provide an overview of probabilistic risk assessment methodologies and their applications in nuclear and environmental licensing processes of nuclear reactors in Brazil. (author)

  10. Safety assessment principles for nuclear plants

    International Nuclear Information System (INIS)

    1992-01-01

    The present Safety Assessment Principles result from the revision of those which were drawn up following a recommendation arising from the Sizewell-B enquiry. The principles presented here relate only to nuclear safety; there is a section on risks from normal operation and accident conditions and the standards against which those risks are assessed. A major part of the document deals with the principles that cover the design of nuclear plants. The revised Safety assessment principles are aimed primarily at the safety assessment of new nuclear plants but they will also be used in assessing existing plants. (UK)

  11. Portuguese research program on nuclear fusion

    International Nuclear Information System (INIS)

    Varandas, C.A.F.; Cabral, J.A.C.; Manso, M.E.

    1994-01-01

    The Portuguese research program on nuclear fusion is presented. The experimental activity associated with the tokamak ISTTOK as well as the work carried out in the frame of international collaboration are summarized. The main technological features of ISTTOK are described along with studies on microwave reflectometry. Future plans are briefly described

  12. Nuclear Waste Disposal Program 2016

    International Nuclear Information System (INIS)

    2016-12-01

    This comprehensive brochure published by the Swiss National Cooperative for the Disposal of Radioactive Waste (NAGRA) discusses the many important steps in the management of radioactive waste that have already been implemented in Switzerland. The handling and packaging of waste, its characterisation and inventorying, as well as its interim storage and transport are examined. The many important steps in Swiss management of radioactive waste already implemented and wide experience gained in carrying out the associated activities are discussed. The legal framework and organisational measures that will allow the selection of repository sites are looked at. The various aspects examined include the origin, type and volume of radioactive wastes, along with concepts and designs for deep geological repositories and the types of waste to be stored therein. Also, an implementation plan for the deep geological repositories, the required capacities and the financing of waste management activities are discussed as is NAGRA’s information concept. Several diagrams and tables illustrate the program

  13. ITAC, an insider threat assessment computer program

    International Nuclear Information System (INIS)

    Eggers, R.F.; Giese, E.W.

    1988-01-01

    The insider threat assessment computer program, ITAC, is used to evaluate the vulnerability of nuclear material processing facilities to theft of special nuclear material by one or more authorized insider adversaries. The program includes two main parts: one is used to determine the timeliness of nuclear material accounting tests for loss of special nuclear material, and the other determines pathway aggregate detection probabilities for physical protection systems and material control procedures that could detect the theft. Useful features of ITAC include its ability to (1) evaluate and quantify the timeliness of material accounting tests, (2) analyze branching systems of physical pathways and adversary strategies, (3) analyze trickle or abrupt theft situations for combinations of insiders, (4) accept input probabilities and times in the form of ranges rather than discrete points, and (5) simulate input data using Monte Carlo methods to produce statistically distributed aggregate delay times and detection probabilities. The ITAC program was developed by the Security Applications Center of Westinghouse Hanford Comapny and Boeing Computer Services, Richland, WA

  14. Defense Programs Transportation Risk Assessment

    International Nuclear Information System (INIS)

    Clauss, D.B.

    1994-01-01

    This paper provides an overview of the methodology used in a probabilistic transportation risk assessment conducted to assess the probabilities and consequences of inadvertent dispersal of radioactive materials arising from severe transportation accidents. The model was developed for the Defense Program Transportation Risk Assessment (DPTRA) study. The analysis incorporates several enhancements relative to previous risk assessments of hazardous materials transportation including newly-developed statistics on the frequencies and severities of tractor semitrailer accidents and detailed route characterization using the 1990 Census data

  15. Spent Nuclear Fuel Alternative Technology Risk Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Perella, V.F.

    1999-11-29

    A Research Reactor Spent Nuclear Fuel Task Team (RRTT) was chartered by the Department of Energy (DOE) Office of Spent Fuel Management with the responsibility to recommend a course of action leading to a final technology selection for the interim management and ultimate disposition of the foreign and domestic aluminum-based research reactor spent nuclear fuel (SNF) under DOE''s jurisdiction. The RRTT evaluated eleven potential SNF management technologies and recommended that two technologies, direct co-disposal and an isotopic dilution alternative, either press and dilute or melt and dilute, be developed in parallel. Based upon that recommendation, the Westinghouse Savannah River Company (WSRC) organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and provide a WSRC recommendation to DOE for a preferred SNF alternative management technology. A technology risk assessment was conducted as a first step in this recommendation process to determine if either, or both, of the technologies posed significant risks that would make them unsuitable for further development. This report provides the results of that technology risk assessment.

  16. Spent Nuclear Fuel Alternative Technology Risk Assessment

    International Nuclear Information System (INIS)

    Perella, V.F.

    1999-01-01

    A Research Reactor Spent Nuclear Fuel Task Team (RRTT) was chartered by the Department of Energy (DOE) Office of Spent Fuel Management with the responsibility to recommend a course of action leading to a final technology selection for the interim management and ultimate disposition of the foreign and domestic aluminum-based research reactor spent nuclear fuel (SNF) under DOE''s jurisdiction. The RRTT evaluated eleven potential SNF management technologies and recommended that two technologies, direct co-disposal and an isotopic dilution alternative, either press and dilute or melt and dilute, be developed in parallel. Based upon that recommendation, the Westinghouse Savannah River Company (WSRC) organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and provide a WSRC recommendation to DOE for a preferred SNF alternative management technology. A technology risk assessment was conducted as a first step in this recommendation process to determine if either, or both, of the technologies posed significant risks that would make them unsuitable for further development. This report provides the results of that technology risk assessment

  17. Research program on nuclear technology and nuclear safety

    International Nuclear Information System (INIS)

    Dreier, J.

    2010-04-01

    This paper elaborated for the Swiss Federal Office of Energy (SFOE) presents the synthesis report for 2009 made by the SFOE's program leader on the research program concerning nuclear technology and nuclear safety. Work carried out, knowledge gained and results obtained in the various areas are reported on. These include projects carried out in the Laboratory for Reactor Physics and System Behaviour LRS, the LTH Thermohydraulics Laboratory, the Laboratory for Nuclear Materials LNM, the Laboratory for Final Storage Safety LES and the Laboratory for Energy Systems Analysis LEA of the Paul Scherrer Institute PSI. Work done in 2009 and results obtained are reported on, including research on transients in Swiss reactors, risk and human reliability. Work on the 'Proteus' research reactor is reported on, as is work done on component safety. International co-operation in the area of serious accidents and the disposal of nuclear wastes is reported on. Future concepts for reactors and plant life management are discussed. The energy business in general is also discussed. Finally, national and international co-operation is noted and work to be done in 2010 is reviewed

  18. Nuclear Materials Stewardship Within the DOE Environmental Management Program

    International Nuclear Information System (INIS)

    Bilyeu, J. D.; Kiess, T. E.; Gates, M. L.

    2002-01-01

    The Department of Energy (DOE) Environmental Management (EM) Program has made significant progress in planning disposition of its excess nuclear materials and has recently completed several noteworthy studies. Since establishment in 1997, the EM Nuclear Material Stewardship Program has developed disposition plans for excess nuclear materials to support facility deactivation. All nuclear materials have been removed from the Miamisburg Environmental Management Project (Mound), and disposition planning is nearing completion for the Fernald Environmental Management Project and the Rocky Flats Environmental Technology Site. Only a few issues remain for materials at the Hanford and Idaho sites. Recent trade studies include the Savannah River Site Canyons Nuclear Materials Identification Study, a Cesium/Strontium Management Alternatives Trade Study, a Liquid Technical Standards Trade Study, an Irradiated Beryllium Reflectors with Tritium study, a Special Performance Assessment Required Trade Study, a Neutron Source Trade Study, and development of discard criteria for uranium. A Small Sites Workshop was also held. Potential and planned future activities include updating the Plutonium-239 storage study, developing additional packaging standards, developing a Nuclear Material Disposition Handbook, determining how to recover or dispose of Pu-244 and U-233, and working with additional sites to define disposition plans for their nuclear materials

  19. CHOOZ-A expert assessment program

    International Nuclear Information System (INIS)

    Bouat, M.; Godin, R.

    1993-01-01

    CHOOZ-A Nuclear Power Plant, the first French-Belgian PWR unit (300 MWe) was definitively shut down at the end of October 1991, after 24 years in operation. Since summer 1991, the steering committee of the French (EDF) Lifetime Project has initiated a large inquiry to the different technical specialists of EDF and external organizations, trying to define a wide expert assessment program on this plant. The aim is to improve the knowledge of aging mechanisms such as those observed on the 52 PWR French nuclear power plants (900 and 1,300 MWe), and contribute to the validation of non-destructive in-service testing methods. This paper presents the retained CHOOZ-A expert assessment program and technical lines followed during its set up. First major project stages are described, then technical choices are explained, and at last the final program is presented with the specific content of each expert assessment. The definitive program is scheduled for a three year period starting at the moment of final shutdown license acquisition, with a provisional total budget of more than US $10 million

  20. 2016 LLNL Nuclear Forensics Summer Program

    Energy Technology Data Exchange (ETDEWEB)

    Zavarin, Mavrik [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-11-15

    The Lawrence Livermore National Laboratory (LLNL) Nuclear Forensics Summer Program is designed to give graduate students an opportunity to come to LLNL for 8–10 weeks for a hands-on research experience. Students conduct research under the supervision of a staff scientist, attend a weekly lecture series, interact with other students, and present their work in poster format at the end of the program. Students also have the opportunity to meet staff scientists one-on-one, participate in LLNL facility tours (e.g., the National Ignition Facility and Center for Accelerator Mass Spectrometry), and gain a better understanding of the various science programs at LLNL.

  1. 2017 LLNL Nuclear Forensics Summer Internship Program

    Energy Technology Data Exchange (ETDEWEB)

    Zavarin, Mavrik [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-12-13

    The Lawrence Livermore National Laboratory (LLNL) Nuclear Forensics Summer Internship Program (NFSIP) is designed to give graduate students an opportunity to come to LLNL for 8-10 weeks of hands-on research. Students conduct research under the supervision of a staff scientist, attend a weekly lecture series, interact with other students, and present their work in poster format at the end of the program. Students can also meet staff scientists one-on-one, participate in LLNL facility tours (e.g., the National Ignition Facility and Center for Accelerator Mass Spectrometry), and gain a better understanding of the various science programs at LLNL.

  2. 2016 LLNL Nuclear Forensics Summer Program

    International Nuclear Information System (INIS)

    Zavarin, Mavrik

    2016-01-01

    The Lawrence Livermore National Laboratory (LLNL) Nuclear Forensics Summer Program is designed to give graduate students an opportunity to come to LLNL for 8-10 weeks for a hands-on research experience. Students conduct research under the supervision of a staff scientist, attend a weekly lecture series, interact with other students, and present their work in poster format at the end of the program. Students also have the opportunity to meet staff scientists one-on-one, participate in LLNL facility tours (e.g., the National Ignition Facility and Center for Accelerator Mass Spectrometry), and gain a better understanding of the various science programs at LLNL.

  3. Marketing Prior Learning Assessment Programs.

    Science.gov (United States)

    Heeger, Gerald A.

    1983-01-01

    Experiential learning programs must be marketed effectively if they are to succeed. The formulation of market strategy is discussed including: strategic planning; identification of a market target; and development of a market mix. A commitment to marketing academic programs is seen as a commitment to self-assessment. (MW)

  4. Nuclear legislation system and nuclear program outlook in Thailand

    International Nuclear Information System (INIS)

    Charoensri, Apisara; Morev, Mikhail N.; Imazu, Hidenori; Kosako, Toshiso; Iimoto, Takeshi

    2009-01-01

    In Thailand, radioactive materials are widely used for the industry, medicine, research and development fields. Reported here are background and recent developments in the national nuclear legislation system, including regulation of radiation safety and current status of nuclear program in Thailand. Under the Atomic Energy for Peace Act, the Thai Atomic Energy Commission (Thai AEC) is authorized to approve regulations respecting, the conversion, enrichment, processing, reprocessing, possession, import, export, use, packaging, transport, management and storage of nuclear materials. The most recent developments are related to the New Ministerial Regulation on Licensing Requirements Procedures and Nuclear Material, By-Product or Atomic Energy Processing B. E 2550 (A. D. 2007) issued under the Atomic Energy for Peace Act, B. E. 2504 (A. D. 1961). Currently, the Thai Cabinet is discussing the draft new Atomic Energy for Peace Act which is to revise the Act. The draft Act is to sets forth criteria for protecting individuals, society and the environment from radiation hazards with the perspective for anticipated nuclear power sector development in Thailand. (author)

  5. Geoscience research for the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Whitaker, S.H.

    1987-01-01

    The Canadian Nuclear Fuel Waste Management Program is assessing the concept of deep disposal of nuclear fuel waste in plutonic rock. As part of that assessment, a broad program of geoscience and geotechnical work has been undertaken to develop methods for characterizing sites, incorporating geotechnical data into disposal facility design, and incorporating geotechnical data into environmental and safety assessment of the disposal system. General field investigations are conducted throughout the Precambrian Shield, subsurface investigations are conducted at designated field research areas, and in situ rock mass experiments are being conducted in an Underground Research Laboratory. Samples from the field research areas and elsewhere are subjected to a wide range of tests and experiments in the laboratory to develop an understanding of the physical and chemical processes involved in ground-water-rock-waste interactions. Mathematical models to simulate these processes are developed, verified and validated. 114 refs.; 13 figs

  6. The protection system to Brazilian Nuclear Program

    International Nuclear Information System (INIS)

    Andreuzza, Mario Giussepp Santezzi Bertottelli

    1997-01-01

    The Sistema de Protecao ao Programa Nuclear Brasileiro-SIPRON (Protection System to Brazilian Nuclear Program) was established in 1980. It is intended to accomplish in only one system, all the actions related to security and protection for Nuclear Facilities in Brazil. The author presents in detail the protection system SIPRON, describing the system structure and organization, the functions and obligations of the system involved main organizations, as well as, the system operation and behaviour during an postulated occurrence of a nuclear emergency. It is also described an Exercise that happened in June of 1997 at the Nuclear Power Plant (NPP) Angra I, after two simulated tests in December of 1996 and April of 1997. The NPP Angra I Emergency Plan Exercise was a good opportunity to test the SIPRON structure and preparedness program. It was verified, included by International Atomic Energy Agency observers, the system involved organizations effectiveness and the procedures efficacy to protect the public and the environmental. Finally, it is shown the SIPRON activities of routine, the system obstacles and the expected future performances. (author)

  7. Advancements in nuclear plant maintenance programs

    International Nuclear Information System (INIS)

    Meligi, A.E.; Maras, M.C.

    1993-01-01

    The viability of the nuclear option as a technology choice for present and future electricity generation will be decided primarily on the basis of operating cost to achieve plant performance objectives. In a nuclear plant, performance is judged not only on availability and output rate but also on safety risk and radiation exposure. Operating, cost is essentially made up of the fuel cost and operation and maintenance (O and M) cost. Over the past decade, the industry average nuclear plant performance has improved significantly; however, this improvement was accompanied by rising O and M cost. The net result was that the nuclear option lost its long-standing economic advantage over the coal option, based on the industry average comparison, around 1987 - with the gap narrowing slightly in the last 2 years. In recent times, gas-fired plants have also become a basis for comparison. The electric generation cost comparisons of various fuel options has led to even greater scrutiny of nuclear plant performance, with the poorer performing plants facing the risk of shutdown. While effective O and M programs improve plant performance, present industry data show that there is no direct correlation between the cost of a plant O and M program and its associated performance. There is a significant number of existing tools and techniques in the O and M area that have proved to be successful and have resulted in significant benefits and payback. This paper presents an overview of the nuclear industry efforts to improve the conduct of O and M activities, describes the basic elements of an effective O and M program, and addresses some of the state-of-the-art tools and techniques to enhance maintenance work planning, training, and procedures

  8. Review of the nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Hatcher, S.R.

    1980-06-01

    Progress over the previous year in the nuclear fuel waste management program is reviewed. Universities, industry and consultants have become increasingly involved, and the work is being overseen by a Technical Advisory Committee. The program has also been investigated by Ontario's Porter Commission and Select Committe on Ontario Hydro Affairs. A public information program has been extended to cover most of the Canadian Shield region of Ontario. Ontario Hydro is studying spent fuel storage and transportation, while AECL is covering immobilization of spent fuel or processing wastes, geotechnical and geochemical research in the laboratory and in the field, design of disposal facilities, and environmental and safety assessments. (L.L.)

  9. Revalidation program for nuclear standby diesel generators

    International Nuclear Information System (INIS)

    Muschick, R.P.

    1985-01-01

    This paper describes the program which Duke Power Company carried out to revalidate the diesel engines used in diesel generators for nuclear standby service at Unit 1 of the Catawba Nuclear Station. The diesels operated satisfactorily during the tests, and only relatively minor conditions were noted during the test and inspections, with one exception. This exception was that cracks were detected in the piston skirts. The piston skirts have been replaced with improved design skirts. The diesels have been fully revalidated for their intended service, and have been declared operable

  10. Reactor use in nuclear engineering programs

    International Nuclear Information System (INIS)

    Murray, R.L.

    1975-01-01

    Nuclear reactors for dual use in training and research were established at about 50 universities in the period since 1950, with assistance by the U. S. Atomic Energy Commission and the National Science Foundation. Most of the reactors are in active use for a variety of educational functions--laboratory teaching of undergraduates and graduate students, graduate research, orientation of visitors, and nuclear power plant reactor operator training, along with service to the technical community. As expected, the higher power reactors enjoy a larger average weekly use. Among special programs are reactor sharing and high-school teachers' workshops

  11. Military nuclear activities. The simulation program

    International Nuclear Information System (INIS)

    Delpuech, A.

    2000-01-01

    The durability of the French nuclear weapon dissuasion has to integrate two kind of problems: the geopolitical situation with the comprehensive nuclear test ban treaty (CTBT) and the aging of weapons. The replacement of decayed weapons requires a complete safety and reliability validation of the new weapons which is performed using simulation. This paper gives a brief presentation of the simulation program and of the technical means developed by the military division of the French atomic energy commission (CEA-DAM): the Airix X-ray radiography installation and the 'megajoule' laser facility. (J.S.)

  12. International Nuclear Model. Volume 3. Program description

    International Nuclear Information System (INIS)

    Andress, D.

    1985-01-01

    This is Volume 3 of three volumes of documentation of the International Nuclear Model (INM). This volume presents the Program Description of the International Nuclear Model, which was developed for the Nuclear and Alternate Fuels Division (NAFD), Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decisions for reactor deployment and fuel management decision based on an input set of technical economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. Companion volumes to Volume 3 are: Volume 1 - Model Overview, and Volume 2 - Data Base Relationships

  13. Seven principle of highly effective Nuclear Energy Programs

    International Nuclear Information System (INIS)

    Ferguson, Ch.D.; Reed, Ph.D.

    2010-01-01

    This paper presents seven principles that demand consideration for any country using a nuclear power program or wanting to acquire such a program. These principles are assessing the overall energy system, determining effective use of financial resources for energy development, ensuring high safety standards, implementing best security practices, preventing the spread of nuclear weapons, managing radioactive waste in a safe and secure manner, and enacting a legal framework that encompasses the other principle areas. The paper applies management methods that underscore development of strong independent national capabilities integrated within an interdependent international system. The paper discusses the individual responsibilities of states in all seven principles and offers recommendations for how states can benefit from greater international cooperation in nuclear energy development

  14. Nuclear power plant training simulator fidelity assessment

    International Nuclear Information System (INIS)

    Carter, R.J.; Laughery, K.R.

    1985-01-01

    The fidelity assessment portion of a methodology for evaluating nuclear power plant simulation facilities in regard to their appropriateness for conducting the Nuclear Regulatory Commission's operating test was described. The need for fidelity assessment, data sources, and fidelity data to be collected are addressed. Fidelity data recording, collection, and analysis are discussed. The processes for drawing conclusions from the fidelity assessment and evaluating the adequacy of the simulator control-room layout were presented. 3 refs

  15. Description of NORMTRI: a computer program for assessing the off-site consequences from air-borne releases of tritium during normal operation of nuclear facilities

    International Nuclear Information System (INIS)

    Raskob, W.

    1994-10-01

    The computer program NORMTRI has been developed to calculate the behaviour of tritium in the environment released into the atmosphere under normal operation of nuclear facilities. It is possible to investigate the two chemical forms tritium gas and tritiated water vapour. The conversion of tritium gas into tritiated water followed by its reemission back to the atmosphere as well as the conversion into organically bound tritium is considered. NORMTRI is based on the statistical Gaussian dispersion model ISOLA, which calculates the activity concentration in air near the ground contamination due to dry and wet deposition at specified locations in a polar grid system. ISOLA requires a four-parametric meteorological statistics derived from one or more years synoptic recordings of 1-hour-averages of wind speed, wind direction, stability class and precipitation intensity. Additional features of NORMTRI are the possibility to choose several dose calculation procedures, ranging from the equations of the German regulatory guidelines to a pure specific equilibrium approach. (orig.)

  16. Implementing an effective self-assessment program at Millstone Station

    International Nuclear Information System (INIS)

    Venable, J.M.

    1996-01-01

    The nuclear industry is becoming ever more reliant on self-assessments to ensure operational safety and to meet our increasingly competitive business challenges. This trend includes utility assessments modeled after major U.S. Nuclear Regulatory Commission (NRC) inspections such as safety system functional inspections (SSFI). Utility conducted SSFIs leveraged the limited resources of the NRC, making possible many evaluations that simply would not have been conducted otherwise. This report describes a self-assessment program at the Millstone Station plant

  17. Laboratory Cooperative Program: an assessment

    International Nuclear Information System (INIS)

    1979-11-01

    The Laboratory Cooperative Program (Lab Coop Program) was initiated by the US AEC over 20 years ago to promote the transfer of technical information from the national laboratories to the academic community utilizing the facilities and staff capabilities of the labs. Under the AEC, ERDA and DOE, the goals of the program have broadened gradually. Therefore, the program was examined to determine the extent to which it contributes to the current objectives of the DOE and to develop recommendations for any program changes. The assessment of the Lab Coop Program was based on a combination of review of program activity data and publications, review of general information regarding laboratory operations, and extensive interviews. The major findings of this evaluation were that: the program lacks a clear statement of purpose; program plans, priorities, and procedures are not explicit and operations tend to follow historical patterns; and the program is generally accepted as beneficial, but its benefits are difficult to quantify. It is recommended that the focus of the Lab Coop Program be limited and clearly defined, that performance plans be developed and measured against accomplishments, and that a national informational effort be initiated

  18. Farewell to the nuclear energy program

    International Nuclear Information System (INIS)

    Sangmeister, H.

    1986-01-01

    In summer 1985 Brazil, presided over by Jose Sarney, definitely decided not to go on with the building preparations for Angra III, a third nuclear power plant, and to suspend the planning and projecting of Iguape I and II (Sao Paulo). In view of decisions such as these there is no doubt about the fact that the Brazilian government soon after entering upon its office attaches but secondary importance to the establishment and extension of a national nuclear power industry. The trend already revealed in its rudiments towards the end of the last Brazilian military government of Joao Figueiredo has meanwhile taken on its definite character and direction: financial cuts and retardation of the ambitious nuclear energy program initiated in the 70s with the aim of corroborating Brazil's position as a dynamic promising industrial nation and hegemonial power of the Latin American subcontinent. (orig.) [de

  19. Probabilistic assessment of nuclear safety and safeguards

    International Nuclear Information System (INIS)

    Higson, D.J.

    1987-01-01

    Nuclear reactor accidents and diversions of materials from the nuclear fuel cycle are perceived by many people as particularly serious threats to society. Probabilistic assessment is a rational approach to the evaluation of both threats, and may provide a basis for decisions on appropriate actions to control them. Probabilistic method have become standard tools used in the analysis of safety, but there are disagreements on the criteria to be applied when assessing the results of analysis. Probabilistic analysis and assessment of the effectiveness of nuclear material safeguards are still at an early stage of development. (author)

  20. Internal Dosimetry for Nuclear Power Program

    International Nuclear Information System (INIS)

    Wo, Y.M.

    2011-01-01

    Internal dosimetry which refers to dosage estimation from internal part of an individual body is an important and compulsory component in order to ensure the safety of the personnel involved in operational of a Nuclear Power Program. Radionuclides particle may deposit in the human being through several pathways and release wave and/or particle radiation to irradiate that person and give dose to body until it been excreted or completely decayed from the body. Type of radionuclides of concerning, monitoring program, equipment's and technique used to measure the concentration level of such radionuclides and dose calculation will be discussed in this article along with the role and capability of Malaysian Nuclear Agency. (author)

  1. Fundamentals of the NEA Thermochemical Database and its influence over national nuclear programs on the performance assessment of deep geological repositories.

    Science.gov (United States)

    Ragoussi, Maria-Eleni; Costa, Davide

    2017-03-14

    For the last 30 years, the NEA Thermochemical Database (TDB) Project (www.oecd-nea.org/dbtdb/) has been developing a chemical thermodynamic database for elements relevant to the safety of radioactive waste repositories, providing data that are vital to support the geochemical modeling of such systems. The recommended data are selected on the basis of strict review procedures and are characterized by their consistency. The results of these efforts are freely available, and have become an international point of reference in the field. As a result, a number of important national initiatives with regard to waste management programs have used the NEA TDB as their basis, both in terms of recommended data and guidelines. In this article we describe the fundamentals and achievements of the project together with the characteristics of some databases developed in national nuclear waste disposal programs that have been influenced by the NEA TDB. We also give some insights on how this work could be seen as an approach to be used in broader areas of environmental interest. Copyright © 2017 Elsevier Ltd. All rights reserved.

  2. Nuclear chemistry in the traditional chemistry program

    International Nuclear Information System (INIS)

    Kleppinger, E.W.

    1993-01-01

    The traditional undergraduate program for chemistry majors, especially at institutions devoted solely to undergraduate education, has limited space for 'special topics' courses in areas such as nuclear and radiochemistry. A scheme is proposed whereby the basic topics covered in an introductury radiochemistry course are touched upon, and in some cases covered in detail, at some time during the four-year sequence of courses taken by a chemistry major. (author) 6 refs.; 7 tabs

  3. Nuclear Plant Aging Research (NPAR) program plan

    International Nuclear Information System (INIS)

    1991-06-01

    A comprehensive Nuclear Plant Aging Research (NPAR) Program was implemented by the US NRC office of Nuclear Regulatory Research in 1985 to identify and resolve technical safety issues related to the aging of systems, structures, and components in operating nuclear power plants. This is Revision 2 to the Nuclear Plant Aging Research Program Plant. This planes defines the goals of the program the current status of research, and summarizes utilization of the research results in the regulatory process. The plan also describes major milestones and schedules for coordinating research within the agency and with organizations and institutions outside the agency, both domestic and foreign. Currently the NPAR Program comprises seven major areas: (1) hardware-oriented engineering research involving components and structures; (2) system-oriented aging interaction studies; (3) development of technical bases for license renewal rulemaking; (4) determining risk significance of aging phenomena; (5) development of technical bases for resolving generic safety issues; (6) recommendations for field inspection and maintenance addressing aging concerns; (7) and residual lifetime evaluations of major LWR components and structures. The NPAR technical database comprises approximately 100 NUREG/CR reports by June 1991, plus numerous published papers and proceedings that offer regulators and industry important insights to aging characteristics and aging management of safety-related equipment. Regulatory applications include revisions to and development of regulatory guides and technical specifications; support to resolve generic safety issues; development of codes and standards; evaluation of diagnostic techniques; (e.g., for cables and valves); and technical support for development of the license renewal rule. 80 refs., 25 figs., 10 tabs

  4. AECL programs for new applications for nuclear energy

    International Nuclear Information System (INIS)

    Robertson, J.A.L.

    1982-05-01

    This document reports the activities of the New Applications Steering Committee (NASC) of Atomic Energy of Canada Ltd. The NASC is intended to develop future RβD programs, and more specifically to promote certain existing ideas that have not yet become part of established programs, stimulate new idaas, identify needs and opportunities for RβD, evaluate proposals for RβD programs, initiate action on new ideas, and provide feedback to a staff who may be expected to generate ideas. Major areas and technologies that have been studied by the NASC and are covered in this report include oil substitution by nuclear heat and by electricity, energy storage and the role of hydrogen, nuclear energy in liquid fuel production, assessment of Canadian energy resources, and computer modelling of energy systems

  5. Turkish nuclear program: a frustrated ambition

    International Nuclear Information System (INIS)

    Cognet, G.

    2016-01-01

    Turkey has launched an ambitious program for the construction of 3 plants involving a total of 12 reactors. Only the Akkuyu and the Sinop projects have been materialized by 2 international agreements. The Akkuyu project will benefit from Russian technology and financing while the Sinop project will rely on a Franco-Japanese technology: the ATMEA reactor. In the eighties there were previous projects on the same sites but they failed due to the lack of financing. Today's economic policy of the Turkish government relies on the construction of big infrastructures in the sectors of transport, defense and energy and nuclear plants are an integral part of it. Turkey's nuclear programme faces various challenges of different types: the seismic risk is very high, the regulation body is consistent for research reactors but not for power plants, there is a lack of trained people in nuclear sciences and engineering, contracts stipulate that local company should be involved in the construction but the industrial sector lacks enterprises that have been certified for working in the nuclear sector, nuclear controversy is emerging in Turkey and diplomatic difficulties with Russia concerning Syria conflict jeopardizes the project. (A.C.)

  6. Nuclear Energy Assessment Battery. Form C.

    Science.gov (United States)

    Showers, Dennis Edward

    This publication consists of a nuclear energy assessment battery for secondary level students. The test contains 44 multiple choice items and is organized into four major sections. Parts include: (1) a knowledge scale; (2) attitudes toward nuclear energy; (3) a behaviors and intentions scale; and (4) an anxiety scale. Directions are provided for…

  7. Legal framework for a nuclear program

    International Nuclear Information System (INIS)

    Santos, A. de los; Corretjer, L.

    1977-01-01

    Introduction of a nuclear program requires the establishment of an adequate legal framework as solutions to the problems posed by the use of nuclear energy are not included in Common Law. As far as Spain is concerned, legislation is capable of dealing with the main problems posed in this field. Spain is a Contracting Party in several International Conventions and participates in International Organizations related to this area and takes their recommendations into account when revising its national legislation. Specific Spanish legislation is constituted by Law 25/1964, of April 29th, on Nuclear Energy, which outlines the legal system regarding nuclear energy, and regulates all aspects which refer to same, from the competent organisms and authorities to the sanctions to be imposed for non-fulfilment of the provisions. In order to offer sufficient flexibility, so that it can be adapted to specific circumstances, the Law's provisions are very ample and development is foreseen by means of regulations. So far, two Regulations have been published: Regulation relating to Coverage of Risk of Nuclear Damage, which refers to Civil Responsibility and its Coverage; and Regulation relating to Nuclear and Radioactive Installations, which refers to the authorization and license system. At the present time, the Regulation relating to Radiation Protection is being elaborated and it will replace the present Radiation Protection Ordinances. In addition to the foregoing, reference is made to others which, although they are not specifically ''nuclear'', they include precepts related to this question, such as the Regulation regarding Nuisance, Unhealthy or Dangerous Industries or some Labor Law provisions [es

  8. Tank waste remediation system nuclear criticality safety program management review

    International Nuclear Information System (INIS)

    BRADY RAAP, M.C.

    1999-01-01

    This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999

  9. Tactical Vulnerability Assessment Training Program

    International Nuclear Information System (INIS)

    Al-Ayat, R.A.; Judd, B.R.; Renis, T.A.; Paulus, W.K.; Winblad, A.G.; Graves, B.R.

    1987-01-01

    The Department of Energy sponsors a 9-day training program for individuals who are responsible for evaluating and planning safeguards systems and for preparing DOE Master and Security Agreements (MSSAs). These agreements between DOE headquarters and operations offices establish required levels of protection. The curriculum includes: (1) the nature of potential insider and outsider threats involving theft or diversion of special nuclear material, (2) use of computerized tools for evaluating the effectiveness of physical protection and material control and accountability systems, and (3) methods for analyzing the benefits and costs of safeguards improvements and for setting priorities among proposed upgrades. The training program is varied and high interactive. Presentations are intermixed with class discussions and ''hands-on'' analysis using computer tools. At the end of the program, participants demonstrate what they have learned in a two-and-one-half day ''field exercise,'' which is conducted on a facility scale-model. The training program has been conducted six times and has been attended by representatives of all DOE facilities. Additional sessions are planned at four-month intervals. This paper describes the training program, use of the tools in preparing MSSAs for various DOE sites, and recent extensions and refinements of the evaluation tools

  10. Tactical Vulnerability Assessment Training Program

    International Nuclear Information System (INIS)

    Al-Ayat, R.A.; Judd, B.R.; Renis, T.A.; Paulus, W.K.; Winblad, A.E.; Graves, B.R.

    1987-01-01

    The Department of Energy sponsors a 9-day training program for individual who are responsible for evaluating and planning safeguards systems and for preparing DOE Master and Security Agreements (MSSAs). These agreements between DOE headquarters and operations offices establish required levels of protection. The curriculum includes: (1) the nature of potential insider and outsider threats involving theft or diversion of special nuclear material, (2) use of computerized tools for evaluating the effectiveness of physical protection and material control and acoountability systems, and (3) methods for analyzing the benefits and costs of safeguards improvements and for setting priorities among proposed upgrades. The training program is varied and highly interactive. Presentations are intermixed with class discussions and ''hands-on'' analysis using computer tools. At the end of the program, participants demonstrate what they have learned in a two-and-one-half day ''field excercise,'' which is conducted on a facility scale-model. The training programs has been conducted six times and has been attended by representatives of all DOE facilities. Additional sessions are planned at four-month intervals. This paper describes the training program, use of the tools in preparing MSSAs for various DOE sites, and recent extensions and refinements of the evaluation tools

  11. Nuclear engine system simulation (NESS) program update

    International Nuclear Information System (INIS)

    Scheil, C.M.; Pelaccio, D.G.; Petrosky, L.J.

    1993-01-01

    The second phase of development of a Nuclear Thermal Propulsion (NTP) engine system design analysis code has been completed. The standalone, versatile Nuclear Engine System Simulation (NESS) code provides an accurate, detailed assessment of engine system operating performance, weight, and sizes. The critical information is required to support ongoing and future engine system and stage design study efforts. This recent development effort included incorporation of an updated solid-core nuclear thermal reactor model that yields a reduced core weight and higher fuel power density when compared to a NERVA type reactor. NESS can now analyze expander, gas generator, and bleed cycles, along with multi-redundant propellant pump feed systems. Performance and weight of efficient multi-stage axial turbopump can now be determined, in addition to the traditional centrifugal pump

  12. Radiation detection technology assessment program (RADTAP)

    International Nuclear Information System (INIS)

    Smith, D.E.

    1998-01-01

    The U.S. Customs Service and the U.S. Department of Energy (DOE) conducted a technical and operational assessment of gamma ray radiation detection equipment during the period May 5-16, 1997 at a testing facility in North Carolina. The effort was entitled, ''Radiation Detection Technology Assessment Program (RADTAP)'', and was conducted for the purpose of assessing the applicability, sensitivity and robustness of a diverse suite of gamma ray detection and identification equipment for possible use by Customs and other law enforcement agencies. Thirteen companies entered 25 instruments into the assessment program. All detection equipment entered had to exhibit a minimum sensitivity of 20 micro-R per hour (background included) from a Cesium-137 point source. Isotope identifying spectrometers entered were man portable and operable at room temperature with read-out that could be interpreted by non-technical personnel. Radioactive sources used in the assessment included special nuclear material, industrial and health isotopes. Evaluators included Customs inspectors and technical experts from DOE and Customs. No conclusions or recommendations were issued based on the quantitative and qualitative test results, however, the results of the program provided law enforcement agencies with the necessary data to select equipment that best meets their operational needs and budgets. (author)

  13. Romanian network for structural integrity assessment of nuclear components

    International Nuclear Information System (INIS)

    Roth, Maria; Constantinescu, Dan Mihai; Brad, Sebastian; Ducu, Catalin

    2008-01-01

    Full text: Based of the Romanian option to develop and operate nuclear facilities, using as model the networks created at European level and taking into account the international importance of the structural integrity assessments for lifetime extension of the nuclear components, a national Project started since 2005 in the framework of the National Program 'Research of Excellence', Modulus I 2006-2008, managed by the Ministry of Education and Research. Entitled 'Integrated Network for Structural Integrity Monitoring of Critical Components in Nuclear Facilities', with the acronym RIMIS, the Project had two main objectives: - to elaborate a procedure applicable to the structural integrity assessment of the critical components used in Romanian nuclear facilities; - to integrate the national networking in a similar one, at European level, to enhance the scientific significance of Romanian R and D organizations as well as to increase the contribution to solving one of the major issue of the nuclear field. The paper aimed to present the activities performed in the Romanian institutes, involved in the Project, the final results obtained as part of the R and D activities, including experimental, theoretical and modeling ones regarding structural integrity assessment of nuclear components employed in CANDU type reactors. Also the activity carried out in the framework of the NULIFE network, created at European level of the FP6 Program and sustained by the RIMIS network will be described. (authors)

  14. Environmental impact assessment of nuclear desalination

    International Nuclear Information System (INIS)

    2010-03-01

    Nuclear desalination is gaining interest among the IAEA Member States, as indicated by the planned projects, and it is expected that the number of nuclear desalination plants will increase in the near future. The IAEA has already provided its Member States with reports and documents that disseminate information regarding the technical and economic feasibility of nuclear desalination. With the rising environmental awareness, in the scope of IAEA's activities on seawater desalination using nuclear power, a need was identified for a report that would provide a generic assessment of the environmental issues in nuclear desalination. In order to offer an overview of specific environmental impacts which are to be expected, their probable magnitude, and recommended mitigation measures, this publication encompasses information provided by the IAEA Member States as well as other specialized sources. It is intended for decision makers and experts dealing with environmental, desalination and water management issues, offering insight into the environmental aspects that are essential in planning and developing nuclear desalination

  15. Millstone nuclear power plant emergency system assessment

    International Nuclear Information System (INIS)

    Akhmad Khusyairi

    2011-01-01

    U.S.NRC determined an obligation to build a nuclear power plant emergency response organization for both on-site and off-site. Millstone Nuclear Power Plants have 3 nuclear reactors and 2 of 3 still in commercial operation. Reactor unit 1, BWR type has been permanently shut down in 1998, while the two others, units 2 and 3 obtain the extended operating license respectively until 2035 and 2045. As a nuclear installation has the high potential radiological impact, Millstone nuclear power plant emergency response organization must establish both on-site or off-site. Emergency response organization that is formed must involve several state agencies, both state agencies and municipality. They have specific duties and functions in a state of emergency, so that protective measures can be undertaken in accordance with the community that has been planned. Meanwhile, NRC conduct their own independent assessment of nuclear power plant emergencies. (author)

  16. Seismic design of nuclear power plants - an assessment

    International Nuclear Information System (INIS)

    Howard, G.E.; Ibanez, P.; Smith, C.B.

    1976-01-01

    This paper presents a review and evaluation of the design standards and the analytical and experimental methods used in the seismic design of nuclear power plants with emphasis on United States practice. Three major areas were investigated: (a) soils, siting, and seismic ground motion specification; (b) soil-structure interaction; and (c) the response of major nuclear power plant structures and components. The purpose of this review and evaluation program was to prepare an independent assessment of the state-of-the-art of the seismic design of nuclear power plants and to identify seismic analysis and design research areas meriting support by the various organizations comprising the 'nuclear power industry'. Criteria used for evaluating the relative importance of alternative research areas included the potential research impact on nuclear power plant siting, design, construction, cost, safety, licensing, and regulation. (Auth.)

  17. Complementary safety assessment assessment of nuclear facilities - Tricastin facility - AREVA

    International Nuclear Information System (INIS)

    2011-01-01

    This complementary safety assessment analyses the robustness of the Areva part of the Tricastin nuclear site to extreme situations such as those that led to the Fukushima accident. This study includes the following facilities: Areva NC Pierrelatte, EURODIF production, Comurhex Pierrelatte, Georges Besse II plant and Socatri. Robustness is the ability for the plant to withstand events beyond which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accidental sequence. Moreover, safety is not only a matter of design or engineered systems but also a matter of organizing: task organization (including subcontracting) as well as the setting of emergency plans or the inventory of nuclear materials are taken into consideration in this assessment. This report is divided into 10 main chapters: 1) the feedback experience of the Fukushima accident; 2) description of the site and its surroundings; 3) featuring of the site's activities and installations; 4) accidental sequences; 5) protection from earthquakes; 6) protection from floods; 7) protection from other extreme natural disasters; 8) the loss of electrical power and of the heat sink; 9) the management of severe accidents; and 10) subcontracting policy. This analysis has identified 5 main measures to be taken to limit the risks linked to natural disasters: -) continuing the program for replacing the current conversion plant and the enrichment plant; -) renewing the storage of hydrofluoric acid at the de-fluorination workshop; -) assessing the seismic behaviour of some parts of the de-fluorination workshop and of the fluorine fabrication workshop; -) improving the availability of warning and information means in case of emergency; and -) improving the means to mitigate accidental gaseous releases. (A.C.)

  18. Reading assessment and training program

    International Nuclear Information System (INIS)

    Lewis, C.L.

    1991-01-01

    The objective was to ensure ourselves and the general public that the workers in the Nuclear Materials Processing Department (NMPD) could read, follow, and understand procedures. Procedures were randomly selected and analyzed for reading levels. A tenth grade reading level was established as the standard for all NMPD employees. Employees were tested to determine reading levels and approximately 12% could not read at the target level. A Procedure Walk-Through Evaluation was administered to each person not reaching tenth grade reading level. This was a job performance measure given to ensure that the worker was competent in his/her present job, and should remain there while completing reading training. A mandatory Reading Training Program utilizing Computer Based Training was established. This program is self-paced, individualized instruction and provided to the worker on Company time. Results of the CBT Program have been very good. Instruction is supplemented with test-taking skills seminars, practice exams, individual conferences with their own reading specialist, and some self-directed study books. This paper describes the program at Savannah River Site

  19. ITRAP. Illicit trafficking radiation detection assessment program

    International Nuclear Information System (INIS)

    Beck, P.

    2001-02-01

    Illicit trafficking in nuclear materials (nuclear criminality) has become more and more a problem, due to the circulation of the a high number of radioactive sources and the big amount of nuclear material, particularly, caused by the changes of the organisational infrastructures to supervise these material within the successor states of the former Soviet Union. The IAEA data base counts at present more than 300 verified cases. The endangering cased thereby ranges from possible health defect for the publication to terrorists activities and production of nuclear weapons. In addition to the primary criminal reasons the illegal deposal of radioactive sources as salvage, scrap and others show a further problem, which has lead to severe accidents and lethal effects in the past (e.g. Goiana, Mexiko). As the study ITRAP (Illicit Trafficking Radiation Assessment Program) can show, also in Austria the cases of partly considerable contaminated scrap transports from neighbouring countries exists. Some countries have already under taken countermeasures (e.g. Monitoring at the Finnish-Russian and German-Polish border, border monitoring in Italy). The International Atomic Energy Agency (IAEA) has reacted on this actual problem by setting up a new program to fight against nuclear criminality and has suggested a pilot study for the practical test of border monitoring systems. Aim of the study was to work out the technical requirements and the practicability of an useful monitoring system at border crossings. The results of the study will be offered by the IAEA to the member states as international recommendations for border monitoring systems. (author)

  20. Evolution of GPU nuclear's training program

    International Nuclear Information System (INIS)

    Long, R.L.; Coe, R.P.

    1987-01-01

    GPU Nuclear Corporation (GPUN) manages the operators of Three Mile Island Unit 1 and Oyster Creek Nuclear Generating Stations and the recovery activities at the Three Mile Island Unit 2 plant. From the time it was formed in January 1980 GPUN emphasized the use of behavioral learning objectives as the basis for all its training programs. This paper describes the evolution to a formalized performance based Training System Development (TSD) Process. The Training and Education Department staff increased from 10 in 1979 to the current 120 dedicated professionals, with a corresponding increase in facilities and acquisition of sophisticated Basic Principles Training Simulators and a Three Mile Island Unit 1 control Room Replica Simulator. The impact of these developments and achievement of full INPO accreditation are discussed and related to plant performance improvements

  1. Nuclear programs see a qualified increase

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    This March 1995 Nuclear News article is a review of the proposed DOE budget for nuclear energy activities. This proposed budget increases spending by 32.7% and includes increases in nearly every individual program except civilian reactor development. Isotope production and distribution receive the largest increase, followed by termination costs for certain federal reactor projects. There is a 61.9% proposed increase (to $199M) for waste management activities, but with funding from other Departments, the actual budget would be $612M. The majority of this money would go toward Yucca Mountain activities. Except for the cancellation of the Advanced Neutron Source, the Science and Technology portion of the budget shows an overall small increase

  2. The United States nuclear merchant ship program

    International Nuclear Information System (INIS)

    Maynard, E.V.

    1978-01-01

    The issues of financial protection contemplate appropriate financing to permit construction of the involved vessels. In addition, the licensing process will require a demonstrated ability for financial response in the event of injury to persons or damage to property. Since the thrust in the United States is to use the Price-Anderson framework for Insurance and Indemnity, much attention is devoted to this legislation. The pre-existing regime is related to the distinguishing requirements of the Maritime field with proposals being advanced to more nearly parallel the insurance coverage philosophy of Europe, i.e., to utilize insurance pools for the nuclear risks and utilize the conventional insurance market for non-nuclear risks. Public affairs issues impact heavily on legislation efforts and thusly become significant in developing a program for Financial Protection

  3. Construction Improvement for the Korean Nuclear Program

    International Nuclear Information System (INIS)

    Yang, T. E.

    1992-01-01

    Construction of the nine Nuclear plants requires an enormous financial investment. The decision to build a nuclear unit is based on both economic and resource requirements. Korea has few natural resources to use for power generation so the use of diversified fuel sources is a part of the planning process. Nuclear has historically had economic advantages over the fossil fueled plant, however, this advantage has been reduced. This is mainly due to increasing decommissioning and waste disposal costs plus the financial outlays associated with gaining public acceptance of new nuclear units. One of the principal means to recover the economic advantage of a nuclear plant is to shorten the time needed for construction. Every extra day of construction costs large sums of money in interest and escalation expenses alone. The challenge is to shorten the construction period to the minimum feasible time and thereby reduce the financing costs. The methods that have to be employed to achieve this goal require the total commitment from the management of all entities involved in the program. Through the application of advanced management and construction techniques a new era in the construction of nuclear plants in Korea will occur. This will include changes to the methods used for managing, planning, licensing, designing and constructing the new plants. The ability to meet the aggressive plan for the construction of new nuclear power plants in Korea rests in the hands of the managers of all the parties involved. These men set all the rules by which the new plants will be constructed. It is their responsibility to tackle the current problems and develop the solutions to enable the plan to be realized. The changes suggested within this paper are major, but the potential benefits will allow the Korean Nuclear Industry to advance into the twenty first Century as a leader. The number of fully trained specialists needed to make this happen will not appear overnight. They will have to be

  4. U.S.-origin nuclear material removal program

    Energy Technology Data Exchange (ETDEWEB)

    Messick, C.E.; Galan, J.J. [U.S. Department of Energy, Washington, DC (United States). U.S.-Origin Nuclear Material Removal Program

    2014-12-15

    The United States (U.S.) Department of Energy (DOE) Global Threat Reduction Initiative's (GTRI) U.S.-Origin Nuclear Material Removal program, also known as the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program (FRR SNF AP), was established by the U.S. Department of Energy in May 1996. The program's mission provides a disposition pathway for certain U.S. origin spent nuclear fuel and other weapons-grade nuclear material. The program will continue until May 2016 with an additional three year window for fuel cooldown and transportation. This paper provides an update on recent program accomplishments, current program initiatives and future activities.

  5. U.S.-origin nuclear material removal program

    International Nuclear Information System (INIS)

    Messick, C.E.; Galan, J.J.

    2014-01-01

    The United States (U.S.) Department of Energy (DOE) Global Threat Reduction Initiative's (GTRI) U.S.-Origin Nuclear Material Removal program, also known as the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program (FRR SNF AP), was established by the U.S. Department of Energy in May 1996. The program's mission provides a disposition pathway for certain U.S. origin spent nuclear fuel and other weapons-grade nuclear material. The program will continue until May 2016 with an additional three year window for fuel cooldown and transportation. This paper provides an update on recent program accomplishments, current program initiatives and future activities.

  6. Assessing Breastfeeding Using Nuclear Science

    International Nuclear Information System (INIS)

    Henriques, Sasha

    2014-01-01

    Children who receive only human milk for the first 6 months of their lives are more resistant to disease and infection and less likely than children fed with formula milk to develop diabetes, cardiovascular disease, and cancer in adulthood. With the IAEA’s guidance, nuclear techniques are being used to test the effectiveness of breastfeeding promotion strategies. Researchers use non-radioactive stable isotopes of hydrogen ( 2 H) in water ( 2 H 2 O) to measure the movement of liquid from mother to child

  7. Economic assessment of nuclear power plant operation with regard to effective use of nuclear fuel

    International Nuclear Information System (INIS)

    Svec, P.; Raninec, S.; Mizov, J.

    1988-01-01

    The essential preconditions are discussed for the better utilization of fuel in nuclear power plants. The MORNAP program which models the operation of the reactor is used for assessing the consequences of various fuel utilization strategies on technical and economic parameters of WWER-440 nuclear power plant operation. Some results of model calculation are given for the third and fourth units of the Jaslovske Bohunice nuclear power plant. The calculations have served for the economic assessment of the transition of part of the nuclear fuel from a three-campaign to a four-campaign cycle. This transition reduces fuel costs by 1.7%. The implementation of this strategy on a larger scale is expected to save 7 to 9% of fuel costs. (Z.M.). 2 tabs., 7 refs

  8. NCT program at Nuclear Medicine, Inc

    International Nuclear Information System (INIS)

    Noonan, D.J.

    1986-01-01

    The Neutron Capture Therapy program at Nuclear Medicine, Inc. (NMI) is focused on obtaining Food and Drug Administration (FDA) approval of the treatment for malignant brain tumors. To minimize both the time and expense of the approval process, research efforts have been strictly focused and Orphan Drug sponsorship of the boron compound, Na 2 B 12 H 11 SH, has been obtained. The significance of Orphan Drug sponsorship and NMI's initial meeting with the FDA to discuss preclinical and clinical protocols are discussed. 9 references, 2 figures

  9. Environmental monitoring program for nuclear facilities

    International Nuclear Information System (INIS)

    Roenick, R.G.; Kreter, R.N.

    1984-01-01

    The programs aims to determine the area of largest environmental impact, taking into consideration the various installations in the Resende Industrial Complex. In the present work a mathematical model is applied based on regional data, and after the study of the use of land and waster resources in the area. The work, begin two years before the operation of the installation, has been subsequently modified by the environmental analyses obtained. The background levels of integrated dose are determined, and all the pollutents existing in the air, land and water have been classified, with the object of characterizing the region 20 Kilometers around the nuclear installation. (Author) [pt

  10. Conducting Computer Security Assessments at Nuclear Facilities

    International Nuclear Information System (INIS)

    2016-06-01

    Computer security is increasingly recognized as a key component in nuclear security. As technology advances, it is anticipated that computer and computing systems will be used to an even greater degree in all aspects of plant operations including safety and security systems. A rigorous and comprehensive assessment process can assist in strengthening the effectiveness of the computer security programme. This publication outlines a methodology for conducting computer security assessments at nuclear facilities. The methodology can likewise be easily adapted to provide assessments at facilities with other radioactive materials

  11. Pacific Northwest regional assessment program

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The Pacific Northwest (comprised of the states of Alaska, Idaho, Montana, Oregon, Washington and Wyoming) can by several measures be regarded as a national warehouse of fossil energy resources. This condition coupled with an evolving national policy stressing utilization of fossil fuels in the near term prior to development of more advanced technologies for energy supply, could result in the imposition of major changes in the region's environmental, socioeconomic and possibly health status. The objective of the Pacific Northwest Regional Assessment Program is to establish and exercise an integrated analytical assessment program for evaluation of these potential changes that may result from various energy development or conservation scenarios. After consideration of a variety of approaches to integrated assessment at a regional level, Pacific Northwest Laboratories (PNL) has concluded that dynamic simulation techniques provide the best available approach to evaluating the issues pertinent to the Northwest. As a result, the PNW Regional Assessment Program has been structured in a framework involving ten sectors. Each of these sectors involve their own submodels that receive information either from outside the model as exogenous inputs or from other sector submodels

  12. A self-assessment program for Commonwealth Edison Company

    International Nuclear Information System (INIS)

    Garner, D.; Krowzak, F.; Wishau, R.

    1987-01-01

    This paper explains the assessment program developed by Commonwealth Edison Company (CECo) to evaluate the effectiveness of technical activities at its nuclear generating stations. The technical activities evaluated are in the areas of chemistry, emergency planning, radiation protection, and radioactive waste operations. The stations have technical programs for each of these areas and are set up to comply with applicable governmental laws and regulations, industry guidelines, and corporate policies and procedures. Reviews and audits need to be performed to ensure that technical program objectives are being met and that the programs are progressing as intended. Many organizations, including the Institute of Nuclear Power Operations, U.S. Nuclear Regulatory Commission, American Nuclear Insurers, and the CECo Quality Assurance Department perform such reviews and audits, which generate a wide variety of information on the stations' activities

  13. Assessment and balancing of nuclear fuels

    International Nuclear Information System (INIS)

    Reinhard, H.

    1982-01-01

    In 1981 nuclear energy had a share of ca. 17% in the electric power supply of the F.R. of Germany. The amount of nuclear fuels required is equal to ca. 15 million tce. In public technical discussions the economic importance which must be assigned to nuclear energy, e.g. with regard to curbing the energy price development or relieving our balance of payments, is discussed in detail. On the other hand, a number of industrial aspects of nuclear energy utilization - problems of commercial or fiscal law - have been little considered in the technical literature. The following contribution is to present the principles of commercial and fiscal law which have taken shape in connection with the assessment and balancing of the single stages of the nuclear fuel cycle. (orig./UA) [de

  14. A comparative study of European nuclear energy programs

    Energy Technology Data Exchange (ETDEWEB)

    Presas i Puig, Albert [ed.

    2011-07-01

    The report includes the following contributions: Comparative study of European Nuclear Energy Programs. From international cooperation to the failure of a national program: the Austrian case. The ''go-and-stop'' of the Italian civil nuclear programs, among improvisations, ambitions and conspiracy. Nuclear energy in Spain - a research agenda for economic historians. The Portuguese nuclear program: a peripheral experience under dictatorship (1945-1973). The nuclear energy programs in Switzerland. The rise and decline of an independent nuclear power industry in Sweden, 1945-1970. The German fast breeder program, a historical review. Fast reactors as future visions - the case of Sweden. Transnational flows of nuclear knowledge between the U.S. and the U.K. and continental Europe in the 1950/60s. The Carter administration and its non-proliferation policies: the road to INFCE.

  15. The Cuban nuclear program and its Scientific and Technical Infrastructure

    International Nuclear Information System (INIS)

    Gandarias Cruz, D.; Codorniu Pujals, D.

    1995-01-01

    The present paper shows the aspects including the Cuban Nuclear Program and underlines its close connection with the strategy of economic, social and scientific technical development in the country, the organizing structure of the Cuban nuclear activity is explained. The application of nuclear techniques and research development activity in the nuclear field are also expressed in detailed in this paper

  16. Ground assessment methods for nuclear power plant

    International Nuclear Information System (INIS)

    1985-01-01

    It is needless to say that nuclear power plant must be constructed on the most stable and safe ground. Reliable assessment method is required for the purpose. The Ground Integrity Sub-committee of the Committee of Civil Engineering of Nuclear Power Plant started five working groups, the purpose of which is to systematize the assessment procedures including geological survey, ground examination and construction design. The works of working groups are to establishing assessment method of activities of faults, standardizing the rock classification method, standardizing assessment and indication method of ground properties, standardizing test methods and establishing the application standard for design and construction. Flow diagrams for the procedures of geological survey, for the investigation on fault activities and ground properties of area where nuclear reactor and important outdoor equipments are scheduled to construct, were established. And further, flow diagrams for applying investigated results to design and construction of plant, and for determining procedure of liquidification nature of ground etc. were also established. These systematized and standardized methods of investigation are expected to yield reliable data for assessment of construction site of nuclear power plant and lead to the safety of construction and operation in the future. In addition, the execution of these systematized and detailed preliminary investigation for determining the construction site of nuclear power plant will make much contribution for obtaining nation-wide understanding and faith for the project. (Ishimitsu, A.)

  17. Case assessments for nuclear medicine registrars

    International Nuclear Information System (INIS)

    Farlow, D.

    1994-01-01

    Westmead Hospital set some of the recent nuclear medicine cases for registrar training. These case assessments have been completed by the registrars and he thought it might be interesting for the general nuclear medicine community to attempt the cases themselves and compare their answers with the model reports and patient follow-ups. Edited versions of two cases and model answers are presented. 35 refs

  18. Proliferation resistance assessment of nuclear systems

    International Nuclear Information System (INIS)

    1978-09-01

    The paper focuses on examining the degree to which nuclear systems could be used to acquire nuclear weapons material. It establishes a framework for proliferation resistance assessment and illustrates its applicability through an analysis of reference systems for once-through cycles, breeder cycles and thermal recycle. On a more tentative basis, the approach is applied to various alternative technical and institutional measures. This paper was also submitted to Working Groups 5 and 8

  19. Nuclear fuel waste management - biosphere program highlights - 1978 to 1996

    Energy Technology Data Exchange (ETDEWEB)

    Zach, R

    1997-07-01

    The biosphere program in support of the development of the disposal concept for Canadian nuclear fuel waste since 1978 is scheduled for close-out. AECL`s Environmental Science Branch (ESB) was mainly responsible for work in this program. In order to preserve as much information as possible, this report highlights many of the key achievements of the program, particularly those related to the development of the BIOTRAC biosphere model and its supporting research. This model was used for the assessment and review of the disposal concept in an environmental impact statement (EIS). The report also treats highlights related to alternative models, external scientific/technical reviews, EIS feedback, and the international BIOMOVS model validation program. Furthermore, it highlights basic aspects of future modelling and research needs in relation to siting a disposal facility. In this, feedback from the various reviews and the EIS is taken into account. Appendices of the report include listings of key ESB staff involved in the program, all the scientific/technical reports and papers produced under the program, contracts let to outside agencies, and issues raised by various participants or intervenors during the EIS review. Although the report is concerned with close-out of the biosphere program, it also provides valuable information for a continuing program concerned with siting a disposal facility. One of the conclusions of the report is that such a program is essential for successfully siting such a facility. (author) Refs.

  20. Nuclear fuel waste management - biosphere program highlights - 1978 to 1996

    International Nuclear Information System (INIS)

    Zach, R.

    1997-07-01

    The biosphere program in support of the development of the disposal concept for Canadian nuclear fuel waste since 1978 is scheduled for close-out. AECL's Environmental Science Branch (ESB) was mainly responsible for work in this program. In order to preserve as much information as possible, this report highlights many of the key achievements of the program, particularly those related to the development of the BIOTRAC biosphere model and its supporting research. This model was used for the assessment and review of the disposal concept in an environmental impact statement (EIS). The report also treats highlights related to alternative models, external scientific/technical reviews, EIS feedback, and the international BIOMOVS model validation program. Furthermore, it highlights basic aspects of future modelling and research needs in relation to siting a disposal facility. In this, feedback from the various reviews and the EIS is taken into account. Appendices of the report include listings of key ESB staff involved in the program, all the scientific/technical reports and papers produced under the program, contracts let to outside agencies, and issues raised by various participants or intervenors during the EIS review. Although the report is concerned with close-out of the biosphere program, it also provides valuable information for a continuing program concerned with siting a disposal facility. One of the conclusions of the report is that such a program is essential for successfully siting such a facility. (author)

  1. Developing new methodology for nuclear power plants vulnerability assessment

    International Nuclear Information System (INIS)

    Kostadinov, Venceslav

    2011-01-01

    new methodology and solution methods for vulnerability assessment can help the overall national energy sector to identify and understand the terrorist threats to and vulnerabilities of its critical infrastructure. Moreover, adopted methodology could help national regulators and agencies to develop and implement a vulnerability awareness and education programs for their critical assets to enhance the security and a safe operation of the entire energy infrastructure. New methods can also assist nuclear power plants to develop, validate, and disseminate assessment and surveys of new efficient countermeasures. Consequently, concise description of developed new quantitative method and adapted new methodology for nuclear regulatory vulnerability assessment of nuclear power plants are presented.

  2. Electronuclear's safety culture assessment and enhancement program

    International Nuclear Information System (INIS)

    Selvatici, E.; Diaz-Francisco, J.M.; Diniz de Souza, V.

    2002-01-01

    The present paper describes the Eletronuclear's safety culture assessment and enhancement program. The program was launched by the company's top management one year after the creation of Eletronuclear in 1997, from the merging of two companies with different organizational cultures, the design and engineering company Nuclen and the nuclear directorate of the Utility Furnas, Operator of the Angra1 NPP. The program consisted of an assessment performed internally in 1999 with the support and advice of the IAEA. This assessment, performed with the help of a survey, pooled about 80% of the company's employees. The overall result of the assessment was that a satisfactory level of safety culture existed; however, a number of points with a considerable margin for improvement were also identified. These points were mostly related with behavioural matters such as motivation, stress in the workplace, view of mistakes, handling of conflicts, and last but not least a view by a considerable number of employees that a conflict between safety and production might exist. An Action Plan was established by the company managers to tackle these weak points. This Plan was issued as company guideline by the company's Directorate. The subsequent step was to detail and implement the different actions of the Plan, which is the phase that we are at present. In the detailing of the Action Plan, special care was taken to sum up efforts, avoiding duplication of work or competition with already existing programs. In this process it was identified that the company had a considerable number of initiatives directly related to organizational and safety culture improvement, already operational. These initiatives have been integrated in the detailed Action Plan. A new assessment, for checking the effectiveness of the undertaken actions, is planned for 2003. (author)

  3. Practical standard for nuclear power plant life management programs: 2007

    International Nuclear Information System (INIS)

    2006-03-01

    The standard specifies the method of implementing nuclear power plant life management programs. The plant life management programs evaluate the integrity of the plant structures, systems and components, assessing if appropriate measures are taken against existing aging phenomena, if there are possibilities of occurrence and development of aging phenomena and if a sufficient level of margin is maintained to assure the integrity throughout the future operating period. The programs also assess the validity of the current maintenance activities, such as trend monitoring, walkdowns, periodic tests and inspections, repair and replacement work for the purpose of preventive maintenance, and utilization of lessons learned from past trouble experience, in order to newly identify maintenance measures. The technical evaluation on aging phenomena is conducted to establish the 10 year maintenance program for nuclear power plants until the plant reaches 30 years of service. The standard was established and issued by the Atomic Energy Society of Japan (AESJ) through the discussion of experts in the associated fields. (T. Tanaka)

  4. Fusion Nuclear Science Pathways Assessment

    Energy Technology Data Exchange (ETDEWEB)

    C.E. Kessel, et. al.

    2012-02-23

    With the strong commitment of the US to the success of the ITER burning plasma mission, and the project overall, it is prudent to consider how to take the most advantage of this investment. The production of energy from fusion has been a long sought goal, and the subject of several programmatic investigations and time line proposals [1]. The nuclear aspects of fusion research have largely been avoided experimentally for practical reasons, resulting in a strong emphasis on plasma science. Meanwhile, ITER has brought into focus how the interface between the plasma and engineering/technology, presents the most challenging problems for design. In fact, this situation is becoming the rule and no longer the exception. ITER will demonstrate the deposition of 0.5 GW of neutron heating to the blanket, deliver a heat load of 10-20 MW/m2 or more on the divertor, inject 50-100 MW of heating power to the plasma, all at the expected size scale of a power plant. However, in spite of this, and a number of other technologies relevant power plant, ITER will provide a low neutron exposure compared to the levels expected to a fusion power plant, and will purchase its tritium entirely from world reserves accumulated from decades of CANDU reactor operations. Such a decision for ITER is technically well founded, allowing the use of conventional materials and water coolant, avoiding the thick tritium breeding blankets required for tritium self-sufficiency, and allowing the concentration on burning plasma and plasma-engineering interface issues. The neutron fluence experienced in ITER over its entire lifetime will be ~ 0.3 MW-yr/m2, while a fusion power plant is expected to experience 120-180 MW-yr/m2 over its lifetime. ITER utilizes shielding blanket modules, with no tritium breeding, except in test blanket modules (TBM) located in 3 ports on the midplane [2], which will provide early tests of the fusion nuclear environment with very low tritium production (a few g per year).

  5. Health physics self-assessment and the nuclear regulatory oversight process at a nuclear power plant

    International Nuclear Information System (INIS)

    Schofield, R.S.

    2003-01-01

    The U.S. Nuclear Regulatory Commission has developed improvements in their Nuclear Power Plant inspection, assessment and enforcement practices. The objective of these changes was to link regulatory action with power plant performance through a risk- informed process which is intended to enhance objectivity. One of the Strategic Performance Areas of focus by the U.S. NRC is radiation safety. Two cornerstones, Occupational Radiation Safety and Public Radiation Safety, make up this area. These cornerstones are being evaluated through U.S. NRC Performance Indicators (PI) and baseline site inspections. Key to the U.S. NRC's oversight program is the ability of the licensee to implement a self-assessment program which pro-actively identifies potential problems and develops improvements to enhance management's effectiveness. The Health Physics Self-Assessment Program at San Onofre Nuclear Generating Station (SONGS) identifies radiation protection-related weakness or negative trends. The intended end result is improved performance through rapid problem identification, timely evaluation, corrective action and follow-up effectiveness reviews. A review of the radiation protection oversight process and the SONGS Health Physics Self-Assessment Program will be presented. Lessons learned and management tools, which evaluate workforce and Health Physics (HP) staff performance to improve radiological practices, are discussed. (author)

  6. Basis for snubber aging research: Nuclear Plant Aging Research Program

    International Nuclear Information System (INIS)

    Brown, D.P.; Palmer, G.R.; Werry, E.V.; Blahnik, D.E.

    1990-01-01

    This report describes a research plan to address the safety concerns of aging in snubbers used on piping and equipment in commercial nuclear power plants. The work is to be performed under Phase 2 of the Snubber Aging Study of the Nuclear Plant Aging Research Program of the US Nuclear Regulatory Commission with the Pacific Northwest Laboratory (PNL) as the prime contractor. Research conducted by PNL under Phase 1 provided an initial assessment of snubber operating experience and was primarily based on a review of licensee event reports. The work proposed is an extension of Phase 1 and includes research at nuclear power plants and in test laboratories. Included is technical background on the design and use of snubbers in commercial nuclear power applications; the primary failure modes of both hydraulic and mechanical snubbers are discussed. The anticipated safety, technical, and regulatory benefits of the work, along with concerns of the NRC and the utilities, are also described. 21 refs., 7 figs., 1 tab

  7. Status of Iran's nuclear program and negotiations

    Energy Technology Data Exchange (ETDEWEB)

    Albright, David [President, Institute for Science and International Security (ISIS), 236 Massachusetts Avenue, NE 305, Washington, DC 20002 (United States)

    2014-05-09

    Iran's nuclear program poses immense challenges to international security. Its gas centrifuge program has grown dramatically in the last several years, bringing Iran close to a point where it could produce highly enriched uranium in secret or declared gas centrifuge plants before its breakout would be discovered and stopped. To reduce the risk posed by Iran's nuclear program, the P5+1 have negotiated with Iran short term limits on the most dangerous aspects of its nuclear programs and is negotiating long-term arrangements that can provide assurance that Iran will not build nuclear weapons. These long-term arrangements need to include a far more limited and transparent Iranian nuclear program. In advance of arriving at a long-term arrangement, the IAEA will need to resolve its concerns about the alleged past and possibly on-going military dimensions of Iran's nuclear program.

  8. HEALTH - module for assessment of stochastic health effects after nuclear accidents

    International Nuclear Information System (INIS)

    Raicevic, J.J.; Gajic, M.; Popovic, Z.

    2003-01-01

    In this paper the program module HEALTH for assessment of stochastic health effects in the case of nuclear accidents is presented. Program module HEALTH is a part of the new European real-time computer system RODOS for nuclear emergency and preparedness. Some of the key features of module HEALTH are presented, and some possible further improvements are discussed (author)

  9. Standards for psychological assessment of nuclear facility personnel. Technical report

    International Nuclear Information System (INIS)

    Frank, F.D.; Lindley, B.S.; Cohen, R.A.

    1981-07-01

    The subject of this study was the development of standards for the assessment of emotional instability in applicants for nuclear facility positions. The investigation covered all positions associated with a nuclear facility. Conclusions reached in this investigation focused on the ingredients of an integrated selection system including the use of personality tests, situational simulations, and the clinical interview; the need for professional standards to ensure quality control; the need for a uniform selection system as organizations vary considerably in terms of instruments presently used; and the need for an on-the-job behavioral observation program

  10. Nuclear regulation. NRC's security clearance program can be strengthened

    International Nuclear Information System (INIS)

    Fultz, Keith O.; Kruslicky, Mary Ann; Bagnulo, John E.

    1988-12-01

    Because of the national security implications of its programs, the Nuclear Regulatory Commission (NRC) investigates the background of its employees and consultants as well as others to ensure that they are reliable and trustworthy. If the investigation indicates that an employee will not endanger national security, NRC grants a security clearance that allows access to classified information, material, and facilities. NRC also requires periodic checks for some clearance holders to ensure their continued clearance eligibility. The Chairman, Subcommittee on Environment, Energy, and Natural Resources, House Committee on Government Operations, asked GAO to review NRC's personnel security clearance program and assess the procedures that NRC uses to ensure that those who operate nuclear power plants do not pose a threat to the public. The Atomic Energy Act of 1954 requires NRC to conduct background investigations of its employees and consultants as well as others who have access to classified information, material, or facilities. To do this, NRC established a personnel security clearance program. Under NRC policies, a security clearance is granted after the Office of Personnel Management (OPM) or the Federal Bureau of Investigation checks the background of those applying for an NRC clearance. NRC also periodically reassesses the integrity of those holding the highest level clearance. NRC employees, consultants, contractors, and licensees as well as other federal employees hold approximately 10,600 NRC clearances. NRC does not grant clearances to commercial nuclear utility employees unless they require access to classified information or special nuclear material. However, the utilities have voluntarily established screening programs to ensure that their employees do not pose a threat to nuclear plants. NRC faces a dilemma when it hires new employees. Although its policy calls for new hires to be cleared before they start work, the security clearance process takes so long

  11. The Meteorological Monitoring program at a former nuclear weapons plant

    International Nuclear Information System (INIS)

    Maxwell, D.R.; Bowen, B.M.

    1994-01-01

    The purpose of the Meteorological Monitoring program at Rocky Flats Plant (RFP) is to provide meteorological information for use in assessing the transport, and diffusion, and deposition of effluent actually or potentially released into the atmosphere by plant operations. Achievement of this objective aids in protecting health and safety of the public, employees, and environment, and directly supports Emergency Response programs at RFP. Meteorological information supports the design of environmental monitoring networks for impact assessments, environmental surveillance activities, remediation activities, and emergency responses. As the mission of the plant changes from production of nuclear weapons parts to environmental cleanup and economic development, smaller releases resulting from remediation activities become more likely. These possible releases could result from airborne fugitive dust, evaporation from collection ponds, or grass fires

  12. Quantified risk assessment - a nuclear industry viewpoint

    International Nuclear Information System (INIS)

    Thomson, J.R.

    1994-01-01

    This paper presents a brief summary of the methodology used for the assessment of risk arising from fuel handling and dismantling operations in advanced gas-cooled reactor power stations. The difficulties with and problems arising from such risk assessments are discussed. In particular, difficulties arise from (i) the onerous risk criteria that nuclear plants are expected to satisfy, (ii) the necessary complexity of the plant, (iii) the conflicting requirements for the fault consequence assessments to be bounding but not grossly pessimistic, and (iv) areas of fault frequency assessment which contain possibly subjective considerations such as software and common mode failure. (author)

  13. Evolvement of nuclear criticality safety programs

    International Nuclear Information System (INIS)

    Ketzlach, N.

    1992-01-01

    Nuclear criticality safety (NCS) has developed from a discipline requiring the services of personnel with only a background in reactor physics to that involving reactor physics, process engineering, and design as well as administration of the program to ensure all its requirements are implemented. When Oak Ridge National Laboratory (ORNL) was designed and constructed, the physicists at Los Alamos National Laboratory (LANL) were performing the criticality analyses. A physicist who had no chemical process or engineering experience was brought in from LANL to determine whether the facility would be safe. It was only because of his understanding of the reactor physics principles, scientific intuition, and some luck that the design and construction of the facility led to a safe plant. It took a number of years of experience with facility operations and the dedication of personnel for NCS to reach its present status as a recognized discipline

  14. The DECADE performance assessment program

    International Nuclear Information System (INIS)

    Weber, B.V.; Ottinger, P.F.; Commisso, R.J.; Thompson, J.; Rowley, J.E.; Filios, P.; Babineau, M.A.

    1996-01-01

    Previous analyses of DECADE Module 1 experiments indicated significant current loss between the plasma opening switch (POS) and an electron-beam load. A program was initiated to diagnose and improve the power flow to assess the performance of a multi-module DECADE system. Power flow measurements between the POS and load indicate high vacuum flow, distributed current loss and azimuthal asymmetries. A decreased load impedance reduces the fraction of the load current flowing in vacuum. Improved plasma source symmetry reduces losses near the load for long conduction times. Increased POS impedance is required to significantly improve the power coupling to the load. (author). 6 figs., 9 refs

  15. The DECADE performance assessment program

    Energy Technology Data Exchange (ETDEWEB)

    Weber, B V; Ottinger, P F; Commisso, R J [Naval Research Lab., Washington, DC (United States). Plasma Physics Div.; Goyer, J R; Kortbawi, D [Physics International Co., Berkeley, CA (United States); Thompson, J [Maxwell Labs., San Diego, CA (United States); Rowley, J E; Filios, P [Defense Nuclear Agency, Alexandria, VA (United States); Babineau, M A [Sverdlup Technology, Tullahoma, TN (United States)

    1997-12-31

    Previous analyses of DECADE Module 1 experiments indicated significant current loss between the plasma opening switch (POS) and an electron-beam load. A program was initiated to diagnose and improve the power flow to assess the performance of a multi-module DECADE system. Power flow measurements between the POS and load indicate high vacuum flow, distributed current loss and azimuthal asymmetries. A decreased load impedance reduces the fraction of the load current flowing in vacuum. Improved plasma source symmetry reduces losses near the load for long conduction times. Increased POS impedance is required to significantly improve the power coupling to the load. (author). 6 figs., 9 refs.

  16. 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

  17. Understanding Iranian Foreign Policy - The Case of Iranian Nuclear Program

    Directory of Open Access Journals (Sweden)

    Emir Hadzikadunic

    2015-01-01

    Full Text Available This paper examines the complexity of the Iranian foreign policy through the case of Iranian nuclear program. The paper aims to assess foreign policy orientations and compares actions of the last three Iranian presidents, Mohammad Khatami, Mahmoud Ahmadinejad and current Hassan Rouhani in dealing with the international community (IC in pursuing its nuclear program. This assessment would not be complete without reference to the Iranian supreme leader Ali Khamenei who is actual head of the state and the most powerful political authority. This paper also relates Iranian foreign policy expectation to competing theories of international relations to identify the most dominant or the most consistent policy orientation. Its aim is to strengthen realist and power-based explanations that have dominated the discourse on Middle Eastern in general and Iranian foreign policy in particular. In this context, a number of questions will be addressed here. To what extend was Iranian negotiation with the IC over its nuclear program consistent throughout these three presidencies? What has changed, if anything, from Iranian foreign policy perspective and why? Can Iranian foreign policy behavior on this specific topic and in this specific time be explained through any international relations theory? As there are many other questions, so there are many theories to examine and explain true Iranian intentions, those below the surface of declared goals (Hadzikadunic, 2014. The methods employed in answering these questions are largely structured around a chronological account and comparative approach. It is also based on the analysis of foreign policy discourse and the assessment of key decision makers.

  18. China's Nuclear Power Program: Options for the US

    International Nuclear Information System (INIS)

    Suttmeier, R.P.

    1985-01-01

    The issue of American nuclear cooperation with the People's Republic of China is examined with regards to political relations, commercial benefits to the United States, and nonproliferation. China's interest in nuclear power is examined, and its nuclear program is briefly reviewed from the 1950's to present. China's international nuclear relations with other countries are discussed, and implications for the United States examined, particularly with regards to China's intentions toward nuclear proliferation, danger of diversion of material for nuclear weapons, use of pressurized water reactor technology for Chinese naval reactors, and the terms of the nuclear cooperation agreement

  19. Needs of National Infrastructure for Nuclear Energy Program in Macedonia

    International Nuclear Information System (INIS)

    Chaushevski, A.; Poceva, S.N.; Spasevska, H.; Popov, N.

    2016-01-01

    The introduction of a nuclear energy program is a major undertaking with significant implications for many aspects of national infrastructure, ranging from capacity of the power grid, access roads and production facilities, to the involvement of stakeholders and the development of human resources. For new comers countries without nuclear power, even for those who wish to realize substantial expansion of existing nuclear capacity, it can take up to 10-15 years to develop the necessary infrastructure. One of the crucial problems in nuclear energy implementation are human resources needs and educational infrastructure development in this field. No matter what will be the future energy scenario in the Republic of Macedonia, the nuclear educational program is the first step to have HR in the field of nuclear energy. This paper presents the proposed direction for having HR for establishing national infrastructure in nuclear energy program in Macedonia. This includes establishing and developing of MONEP (Macedonian NEPIO), and the enhancing the capabilities of the national regulatory body in the Republic of Macedonia. Keywords: NEP (Nuclear Energy Program), HR (Human Resources), NEPIO (Nuclear Energy Program Implementation Organization), MONEP Macedonian Organization for Nuclear Energy Program (Macedonian NEPIO), NRB (Nuclear Regulatory Body)

  20. Assessment of accident risks from german nuclear plants

    International Nuclear Information System (INIS)

    Heuser, F.W.

    1979-01-01

    The German risk study are presented. The main objectives can be summed up as follows: (a) An assessment of the societal risk due to accidents in nuclear power plants with reference to German conditions; (b) To get experience in the field of risk analysis and to provide a basis for estimation of uncertainties; (c) To provide guidance for future activities in the German Reactor Safety Research Program. Finally several conclusions reached by this study are discussed. (author)

  1. Independent assessment for new nuclear reactor safety

    Directory of Open Access Journals (Sweden)

    D'Auria Francesco

    2017-01-01

    Full Text Available A rigorous framework for safety assessment is established in all countries where nuclear technology is used for the production of electricity. On the one side, industry, i.e. reactor designers, vendors and utilities perform safety analysis and demonstrate consistency between results of safety analyses and requirements. On the other side, regulatory authorities perform independent assessment of safety and confirm the acceptability of safety of individual reactor units. The process of comparing results from analyses by reactor utilities and regulators is very complex. The process is also highly dependent upon mandatory approaches pursued for the analysis and from very many details which required the knowledge of sensitive proprietary data (e.g. spacer designs. Furthermore, all data available for the design, construction and operation of reactors produced by the nuclear industry are available to regulators. Two areas for improving the process of safety assessment for individual Nuclear Power Plant Units are identified: New details introduced by industry are not always and systematically requested by regulators for the independent assessment; New analytical techniques and capabilities are not necessarily used in the analyses by regulators (and by the industry. The established concept of independent assessment constitutes the way for improving the process of safety assessment. This is possible, or is largely facilitated, by the recent availability of the so-called Best Estimate Plus Uncertainty approach.

  2. Independent assessment for new nuclear reactor safety

    International Nuclear Information System (INIS)

    D'Auria, F.; Glaeser, H.; Debrecin, N.

    2017-01-01

    A rigorous framework for safety assessment is established in all countries where nuclear technology is used for the production of electricity. On one side, industry, i.e. reactor designers, vendors and utilities perform safety analysis and demonstrate consistency between results of safety analyses and requirements. On the other side, regulatory authorities perform independent assessment of safety and confirm the acceptability of safety of individual reactor units. The process of comparing results from analyses by reactor utilities and regulators is very complex. The process is also highly dependent upon mandatory approaches pursued for the analysis and from very many details which required the knowledge of sensitive proprietary data (e.g. spacer designs). Furthermore, all data available for the design, construction and operation of reactors produced by the nuclear industry are available to regulators. Two areas for improving the process of safety assessment for individual Nuclear Power Plant Units are identified: New details introduced by industry are not always and systematically requested by regulators for the independent assessment; New analytical techniques and capabilities are not necessarily used in the analyses by regulators (and by the industry). The established concept of independent assessment constitutes the way for improving the process of safety assessment. This is possible, or is largely facilitated, by the recent availability of the so-called Best Estimate Plus Uncertainty (BEPU) approach. (authors)

  3. Competency assessments for nuclear industry personnel

    International Nuclear Information System (INIS)

    2004-04-01

    In 1996, the IAEA published Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation: A Guidebook. This publication provides guidance for the development, implementation and evaluation of training programmes for all nuclear power plant personnel using the systematic approach to training (SAT) methodology. The SAT methodology has since been adopted and used for the development and implementation of training programmes for all types of nuclear facility and activities in the nuclear industry. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared to provide further guidance concerning competency assessments used for measuring the knowledge, skills and attitudes of personnel as the result of training. This publication has been prepared in response to that recommendation. A critical component of SAT (as part of the implementation phase) is the assessment of whether personnel have achieved the standards identified in the training objectives. The nuclear industry spends a significant amount of resources conducting competency assessments. Competency assessments are used for employee selection, trainee assessment, qualification, requalification and authorization (in some Member States the terminology may be 'certification' or 'licensing'), and job advancement and promotion. Ineffective testing methods and procedures, or inappropriate interpretation of test results, can have significant effects on both human performance and nuclear safety. Test development requires unique skills and, as with any skill, training and experience are needed to develop and improve them. Test item and examination development, use, interpretation of results and examination refinement, like all other aspects of SAT, should be part of an ongoing, systematic process. This publication is primarily intended for use by personnel responsible for developing and administering

  4. National emergency medical assistance program for commercial nuclear power plants

    International Nuclear Information System (INIS)

    Linnemann, R.E.; Berger, M.E.

    1987-01-01

    Radiation Management Consultant's Emergency Medical Assistance Program (EMAP) for nuclear facilities provides a twenty-four hour emergency medical and health physics response capability, training of site and off-site personnel, and three levels of care for radiation accident victims: first air and rescue at an accident site, hospital emergency assessment and treatment, and definitive evaluation and treatment at a specialized medical center. These aspects of emergency preparedness and fifteen years of experience in dealing with medical personnel and patients with real or suspected radiation injury will be reviewed

  5. Preliminary nuclear power reactor technology qualitative assessment for Malaysia

    International Nuclear Information System (INIS)

    Shamsul Amri Sulaiman

    2011-01-01

    Since the worlds first nuclear reactor major breakthrough in December 02, 1942, the nuclear power industry has undergone tremendous development and evolution for more than half a century. After surpassing moratorium of nuclear power plant construction caused by catastrophic accidents at Three-mile island (1979) and Chernobyl (1986), today, nuclear energy is back on the policy agendas of many countries, both developed and developing, signaling nuclear revival or nuclear renaissance. Selection of suitable nuclear power technology has thus been subjected to primary attention. This short paper attempts to draw preliminary technology assessment for the first nuclear power reactor technology for Malaysia. Methodology employed is qualitative analysis collating recent finding of tnb-kepco preliminary feasibility study for nuclear power program in peninsular malaysia and other published presentations and/or papers by multiple experts. The results suggested that pressurized water reactor (PWR) is the prevailing technology in terms of numbers and plant performances, and while the commercialization of generation IV reactors is remote (e.g. Not until 2030), generation III/ III+ NPP models are commercially available on the market today. Five (5) major steps involved in reactor technology selection were introduced with a focus on introducing important aspects of selection criteria. Three (3) categories for the of reactor technology selection were used for the cursory evaluation. The outcome of these analyses shall lead to deeper and full analyses of the recommended reactor technologies for a comprehensive feasibility study in the near future. Recommendations for reactor technology option were also provided for both strategic and technical recommendations. The paper shall also implore the best way to select systematically the first civilian nuclear power reactor. (Author)

  6. Update on Canada's nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Allan, C.J.

    1992-09-01

    The Canadian Nuclear Fuel Waste Management Program (CNFWMP) was launched in 1978 as a joint initiative by the governments of Canada and Ontario. Under the program, AECL has been developing and assessing a generic concept to dispose of nuclear fuel waste in plutonic rock of the Canadian Shield. The disposal concept has been referred for review under the Environmental Assessment and Review Process. AECL will submit an Environmental Impact Statement (EIS) to an Environmental Assessment Panel, which was appointed in late 1989. Hearings will be held in areas that have a particular interest in the concept and its application. At the end of the review, the Panel will make recommendations as to the acceptability of the concept and the course of future action. The federal government will decide on the next steps to be taken. In the spring of 1990 public open houses were held to tell prospective participants how to enter the process. Sessions designed to assist the Panel in determining the scope of the EIS took place in the autumn of 1990. In June 1991 the Panel issued for comment a set of draft guidelines for the EIS. More than 30 groups and individuals submitted comments. The final guidelines were issued in March 1992, and AECL expects to submit its EIS to the Panel in 1993. If the concept review is completed by 1995 and if the concept is approved, disposal could begin some time after 2025. (L.L.) (12 refs.)

  7. Overview assessment of nuclear-waste management

    International Nuclear Information System (INIS)

    Burton, B.W.; Gutschick, V.P.; Perkins, B.A.

    1982-08-01

    After reviewing the environmental control technologies associated with Department of Energy nuclear waste management programs, we have identified the most urgent problems requiring further action or follow-up. They are in order of decreasing importance: (1) shallow land disposal technology development; (2) active uranium mill tailings piles; (3) uranium mine dewatering; (4) site decommissioning; (5) exhumation/treatment of transuranic waste at Idaho National Engineering Laboratory; (6) uranium mine spoils; and (7) medical/institutional wastes. 7 figures, 33 tables

  8. 'THE UNVEILED HEART' a teaching program in cardiovascular nuclear medicine

    International Nuclear Information System (INIS)

    Itti, Roland; Merabet, Yasmina; Roca, Ramona; Bontemps, Laurence; Itti, Emmanuel

    2004-01-01

    The functional investigation of cardiac diseases using nuclear techniques involves several variables, such as myocardial perfusion, cellular viability or mechanical contraction. The combined, topographical and quantitative assessment of these variables can characterize the functional state of the heart in terms of normal myocardium, ischemia, hibernation or necrosis. The teaching program, 'The Unveiled Heart', has been designed in order to help nuclear physicians or cardiologists approaching these concepts and their implications for diagnosis of coronary artery disease, optimization of therapeutic strategies and prognosis evaluation. Anatomical correlations with coronary angiographic results obtained during balloon occlusion at the time of coronary angioplasty demonstrate the complementary role of imaging techniques and highlight the patient to patient variability of risk areas. A sectorial model derived from a polar projection of the myocardium presents for each sector the probability of involvement of a given coronary artery

  9. The technical feasibility of uranium enrichment for nuclear bomb construction at the parallel nuclear program plant

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1990-01-01

    It is discussed the hole of the Parallel Nuclear Program is Brazil and the feasibility of uranium enrichment for nuclear bomb construction. This program involves two research centers, one belonging to the brazilian navy and another to the aeronautics. Some other brazilian institutes like CTA, IPEN, COPESP and CETEX and also taking part in the program. (A.C.A.S.)

  10. Systematic Assessment for University Sexuality Programming.

    Science.gov (United States)

    Westefeld, John S.; Winkelpleck, Judy M.

    1982-01-01

    Suggests systematic empirical assessment is needed to plan university sexuality programing. Proposes the traditional approach of asking about students' attitudes, knowledge, and behavior is useful for developing specific programing content. Presents an assessment model emphasizing assessment of students' desires for sexuality programing in terms…

  11. Probabilistic risk assessment in nuclear power plant regulation

    Energy Technology Data Exchange (ETDEWEB)

    Wall, J B

    1980-09-01

    A specific program is recommended to utilize more effectively probabilistic risk assessment in nuclear power plant regulation. It is based upon the engineering insights from the Reactor Safety Study (WASH-1400) and some follow-on risk assessment research by USNRC. The Three Mile Island accident is briefly discussed from a risk viewpoint to illustrate a weakness in current practice. The development of a probabilistic safety goal is recommended with some suggestions on underlying principles. Some ongoing work on risk perception and the draft probabilistic safety goal being reviewed on Canada is described. Some suggestions are offered on further risk assessment research. Finally, some recent U.S. Nuclear Regulatory Commission actions are described.

  12. Specialization-Specific Course Assessments Integrated for Program Assessment

    OpenAIRE

    Qurban A. Memon; Adnan Harb; Shakeel Khoja

    2012-01-01

    The program assessment process combines assessments from individual courses to generate final program assessment to match accreditation benchmarks. In developing countries, industrial environment is not diversified to allow graduating engineers to seek jobs in all disciplines or specializations of an engineering program. Hence, it seems necessary to seek evolution of an engineering program assessment for specialized requirements of the industry. This paper describes how specialization-specifi...

  13. An assessment of seismic margins in nuclear plant piping

    International Nuclear Information System (INIS)

    Chen, W.P.; Jaquay, K.R.; Chokshi, N.C.; Terao, D.

    1995-01-01

    Interim results of an ongoing program to assist the U.S. Nuclear Regulatory Commission (NRC) in developing regulatory positions on the seismic analyses of piping and overall safety margins of piping systems are reported. Results of reviews of previous seismic testing, primarily the Electric Power Research Institute (EPRI)/NRC Piping and Fitting Dynamic Reliability Program, and assessments of the ASME Code, Section III, piping seismic design criteria as revised by the 1994 Addenda are reported. Major issues are identified herein only. Technical details are to be provided elsewhere. (author). 4 refs., 2 figs

  14. Considerations on Cyber Security Assessments of Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Jung-Woon; Song, Jae-Gu; Han, Kyung-Soo; Lee, Cheol Kwon; Kang, Mingyun

    2015-01-01

    Korea Institute of Nuclear Nonproliferation and Control (KINAC) has prepared the regulatory standard RS-015 based on RG 5.71. RS-015 defines the elements of a cyber security program to be established in nuclear facilities and describes the security control items and relevant requirements. Cyber security assessments are important initial activities in a cyber security program for NPPs. Cyber security assessments can be performed in the following key steps: 1) Formation of a cyber security assessment team (CSAT); 2) Identification of critical systems and critical digital assets (CDAs); 3) Plant compliance checks with the security control requirements in RS-015. Through the assessments, the current status of security controls applied to NPPs can be found out. The assessments provide baseline data for remedial activities. Additional analyses with the results from the assessments should be performed before the implementation of remedial security controls. The cyber security team at the Korea Atomic Energy Research Institute (KAERI) has studied how to perform cyber security assessments for NPPs based on the regulatory requirements. Recently, KAERI's cyber security team has performed pilot cyber security assessments of a Korean NPP. Based on this assessment experience, considerations and checkpoints which would be helpful for full-scale cyber security assessments of Korean NPPs and the implementation of remedial security controls are discussed in this paper. Cyber security assessment is one of important and immediate activities for NPP cyber security. The quality of the first assessment will be a barometer for NPP cyber security. Hence cyber security assessments of Korean NPPs should be performed elaborately

  15. Considerations on Cyber Security Assessments of Korean Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung-Woon; Song, Jae-Gu; Han, Kyung-Soo; Lee, Cheol Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kang, Mingyun [E-Gonggam Co. Ltd., Daejeon (Korea, Republic of)

    2015-10-15

    Korea Institute of Nuclear Nonproliferation and Control (KINAC) has prepared the regulatory standard RS-015 based on RG 5.71. RS-015 defines the elements of a cyber security program to be established in nuclear facilities and describes the security control items and relevant requirements. Cyber security assessments are important initial activities in a cyber security program for NPPs. Cyber security assessments can be performed in the following key steps: 1) Formation of a cyber security assessment team (CSAT); 2) Identification of critical systems and critical digital assets (CDAs); 3) Plant compliance checks with the security control requirements in RS-015. Through the assessments, the current status of security controls applied to NPPs can be found out. The assessments provide baseline data for remedial activities. Additional analyses with the results from the assessments should be performed before the implementation of remedial security controls. The cyber security team at the Korea Atomic Energy Research Institute (KAERI) has studied how to perform cyber security assessments for NPPs based on the regulatory requirements. Recently, KAERI's cyber security team has performed pilot cyber security assessments of a Korean NPP. Based on this assessment experience, considerations and checkpoints which would be helpful for full-scale cyber security assessments of Korean NPPs and the implementation of remedial security controls are discussed in this paper. Cyber security assessment is one of important and immediate activities for NPP cyber security. The quality of the first assessment will be a barometer for NPP cyber security. Hence cyber security assessments of Korean NPPs should be performed elaborately.

  16. Environmental Assessment Radioactive Source Recovery Program

    International Nuclear Information System (INIS)

    1995-01-01

    In a response to potential risks to public health and safety, the U.S. Department of Energy (DOE) is evaluating the recovery of sealed neutron sources under the Radioactive Source Recovery Program (RSRP). This proposed program would enhance the DOE's and the U.S. Nuclear Regulatory Commission's (NRC's) joint capabilities in the safe management of commercially held radioactive source materials. Currently there are no federal or commercial options for the recovery, storage, or disposal of sealed neutron sources. This Environmental Assessment (EA) analyzes the potential environmental impacts that would be expected to occur if the DOE were to implement a program for the receipt and recovery at the Los Alamos National Laboratory (LANL), Los Alamos, New Mexico, of unwanted and excess plutonium-beryllium ( 238 Pu-Be) and americium-beryllium ( 241 Am-Be) sealed neutron sources. About 1 kg (2.2 lb) plutonium and 3 kg (6.6 lb) americium would be recovered over a 15-year project. Personnel at LANL would receive neutron sources from companies, universities, source brokers, and government agencies across the country. These neutron sources would be temporarily stored in floor holes at the CMR Hot Cell Facility. Recovery reduces the neutron emissions from the source material and refers to a process by which: (1) the stainless steel cladding is removed from the neutron source material, (2) the mixture of the radioactive material (Pu-238 or Am-241) and beryllium that constitutes the neutron source material is chemically separated (recovered), and (3) the recovered Pu-238 or Am-241 is converted to an oxide form ( 238 PuO 2 or 241 AmO 2 ). The proposed action would include placing the 238 PuO 2 or 241 AmO 2 in interim storage in a special nuclear material vault at the LANL Plutonium Facility

  17. Attracting students to nuclear careers: INPO educational assistance program

    International Nuclear Information System (INIS)

    Dunkle, M.

    1981-01-01

    The utility industry is responding to a manpower shortage of 2000 at nuclear plants with a concerted analysis of regional training centers and educational assistance programs through the Institute of Nuclear Power Operations (INPO). University support and cooperation are generally strong. The INPO program includes undergraduate- and graduate-level scholarships and fellowships

  18. Nuclear plant service water system aging degradation assessment

    International Nuclear Information System (INIS)

    Jarrell, D.B.; Larson, L.L.; Stratton, R.C.; Bohn, S.J.; Gore, M.L.

    1992-10-01

    This report discusses the second phase of the aging assessment of nuclear plant service water systems (SWSs) which was performed by the Pacific Northwest Laboratory (PNL) to support the US Nuclear Regulatory Commission's (NRC's) Nuclear Plant Aging Research (NPAR) program. The SWS was selected for study because of its essential role in the mitigation of and recovery from accident scenarios involving the potential for core-melt, and because it is subject to a variety of aging mechanisms. The objectives of the SWS task under the NPAR program are to identify and characterize the principal age-related degradation mechanisms relevant to this system, to assess the impact of aging degradation on operational readiness, and to provide a methodology for the management of aging on the service water aspect of nuclear plant safety. The primary degradation mechanism in the SWSs as stated in the Phase I assessment and confirmed by the analysis in Phase II, is corrosion compounded by biologic and inorganic accumulation. It then follows that the most effective means for mitigating degradation in these systems is to pursue appropriate programs to effectively control the water chemistry properties when possible and to use biocidal agents where necessary. A methodology for producing a complete root-cause analysis was developed as a result of needs identified in the Phase I assessment for a more formal procedure that would lend itself to a generic, standardized approach. It is recommended that this, or a similar methodology, be required as a part of the documentation for corrective maintenance performed on the safety-related portions of SWSs to provide an accurate focus for effective management of aging

  19. Whistleblowers ask Congress to investigate TVA's nuclear power program

    International Nuclear Information System (INIS)

    Lane, E.

    1993-01-01

    Congress should investigate the Tennessee Valley Authority's nuclear power plant construction and operations programs as soon as possible, a coalition of Tennessee environmentalists and whistleblowers told reporters at a press conference in Washington, DC. The Foundation for Global Sustainability and four employees of TVA nuclear plants called for congressional action because they contend the Nuclear Regulatory Commission and the Department of Labor have failed to act to protect whistleblowers who report nuclear safety problems. The foundation contends the economics of nuclear plant construction by TVA do not make sense and in the rush to finish the Watts Bar nuclear plant, which has been under construction for 20 years, TVA has ignored safety issues

  20. PCNuDAT a PC Nuclear Data program

    International Nuclear Information System (INIS)

    Kinsey, R.R.

    1998-01-01

    The PC program PCNuDat is described which displays nuclear radioactive decay data and thermal cross section data. It requires 45 Megabytes (reduced version of PCNuDat requires 3 Megabytes) of disc space and can be obtained through Internet FTP or WWW from U.S. Nuclear Data Center or Nuclear Data Section of the IAEA. It can be obtained also on CD-ROM upon request sent to Nuclear Data Section. (author)

  1. Myocardial viability assessment using nuclear imaging

    International Nuclear Information System (INIS)

    Matsunari, Ichiro; Hisada, Kinichi; Taki, Junichi; Nakajima, Kenichi; Tonami, Norihisa

    2003-01-01

    Myocardial assessment continues to be an issue in patients with coronary artery disease and left ventricular dysfunction. Nuclear imaging has long played an important role in this field. In particular, PET imaging using 18 F-fluorodeoxyglucose is regarded as the metabolic gold standard of tissue viability, which has been supported by a wide clinical experience. Viability assessment using SPECT techniques has gained more wide-spread clinical acceptance than PET, because it is more widely available at lower cost. Moreover, technical advances in SPECT technology such as gated-SPECT further improve the diagnostic accuracy of the test. However, other imaging techniques such as dobutamine echocardiography have recently emerged as competitors to nuclear imaging. It is also important to note that they sometimes may work in a complementary fashion to nuclear imaging, indicating that an appropriate use of these techniques may significantly improve their overall accuracy. In keeping these circumstances in mind, further efforts are necessary to further improve the diagnostic performance of nuclear imaging as a reliable viability test. (author) 107 refs

  2. Department of Energy: Nuclear S&T workforce development programs

    International Nuclear Information System (INIS)

    Bingham, Michelle; Bala, Marsha; Beierschmitt, Kelly; Steele, Carolyn; Sattelberger, Alfred P.; Bruozas, Meridith A.

    2016-01-01

    The U.S. Department of Energy (DOE) national laboratories use their expertise in nuclear science and technology (S&T) to support a robust national nuclear S&T enterprise from the ground up. Traditional academic programs do not provide all the elements necessary to develop this expertise, so the DOE has initiated a number of supplemental programs to develop and support the nuclear S&T workforce pipeline. This document catalogs existing workforce development programs that are supported by a number of DOE offices (such as the Offices of Nuclear Energy, Science, Energy Efficiency, and Environmental Management), and by the National Nuclear Security Administration (NNSA) and the Naval Reactor Program. Workforce development programs in nuclear S&T administered through the Department of Homeland Security, the Nuclear Regulatory Commission, and the Department of Defense are also included. The information about these programs, which is cataloged below, is drawn from the program websites. Some programs, such as the Minority Serving Institutes Partnership Programs (MSIPPs) are available through more than one DOE office, so they appear in more than one section of this document.

  3. Assessment Practices in Undergraduate Accounting Programs

    Science.gov (United States)

    Lusher, Anna L.

    2010-01-01

    This study examined accounting program assessment plans at 102 colleges and universities in the United States. The research focused on identifying assessment practices in undergraduate accounting programs by examining the skills and competencies assessed and determining the methods of assessment used. The study also investigated what course and/or…

  4. Nuclear security assessment with Markov model approach

    International Nuclear Information System (INIS)

    Suzuki, Mitsutoshi; Terao, Norichika

    2013-01-01

    Nuclear security risk assessment with the Markov model based on random event is performed to explore evaluation methodology for physical protection in nuclear facilities. Because the security incidences are initiated by malicious and intentional acts, expert judgment and Bayes updating are used to estimate scenario and initiation likelihood, and it is assumed that the Markov model derived from stochastic process can be applied to incidence sequence. Both an unauthorized intrusion as Design Based Threat (DBT) and a stand-off attack as beyond-DBT are assumed to hypothetical facilities, and performance of physical protection and mitigation and minimization of consequence are investigated to develop the assessment methodology in a semi-quantitative manner. It is shown that cooperation between facility operator and security authority is important to respond to the beyond-DBT incidence. (author)

  5. Radiation Monitoring - A Key Element in a Nuclear Power Program

    International Nuclear Information System (INIS)

    Hussein, A.S.; El-dally, T.A.

    2008-01-01

    For a nuclear power plant, radiation is especially of great concern to the public and the environment. Therefore, a radiation monitoring program is becoming a critical importance. This program covers all phases of the nuclear plant including preoperational, normal operation, accident and decommissioning. The fundamental objective of radiation monitoring program is to ensure that the health and safety of public inside and around the plant and to confirm the radiation doses are below the dose limits for workers and the public. This paper summarizes the environmental radiation monitoring program for a nuclear power plant

  6. Nuclear Explosion Monitoring Research and Engineering Program - Strategic Plan

    Energy Technology Data Exchange (ETDEWEB)

    Casey, Leslie A. [DOE/NNSA

    2004-09-01

    The Department of Energy (DOE)/National Nuclear Security Administration (NNSA) Nuclear Explosion Monitoring Research and Engineering (NEM R&E) Program is dedicated to providing knowledge, technical expertise, and products to US agencies responsible for monitoring nuclear explosions in all environments and is successful in turning scientific breakthroughs into tools for use by operational monitoring agencies. To effectively address the rapidly evolving state of affairs, the NNSA NEM R&E program is structured around three program elements described within this strategic plan: Integration of New Monitoring Assets, Advanced Event Characterization, and Next-Generation Monitoring Systems. How the Program fits into the National effort and historical accomplishments are also addressed.

  7. The Nordic safety program on accident consequence assessment

    International Nuclear Information System (INIS)

    Tveten, U.

    1988-01-01

    One important part of Nordic cooperation is partially funded by the Nordic Council of Ministers, namely the work performed within the Nordic Safety Program (often referred to as the NKA projects). NKA is the Nordic abbreviation of the Nordic Liaison Committee on Atomic Energy. One program area in the present four-year period is concerned with problems related to reactor accident consequence assessment, and contains almost twenty projects covering a wide range of subjects. The author is program coordinator for this program area. The program will be completed in 1989. The program was strongly influenced by Chernobyl, and a number of new projects were included in the program in 1986. Involved in the program are these Nordic institutions: Riso National Laboratory (Denmark). Technical Research Centre of Finland. Finnish Centre for Radiation and Nuclear Safety. Finnish Meteorological Institute. Institute for Energy Technology (Norway). Agricultural University of Norway. Meteorological Institute of Norway. Studsvik Energiteknik AB (Sweden). National Defence Research Laboratory (Sweden)

  8. Nuclear Plant Aging Research (NPAR) program plan

    International Nuclear Information System (INIS)

    1985-07-01

    The nuclear plant aging research described in this plan is intended to resolve issues related to the aging and service wear of equipment and systems at commercial reactor facilities and their possible impact on plant safety. Emphasis has been placed on identification and characterization of the mechansims of material and component degradation during service and evaluation of methods of inspection, surveillance, condition monitoring and maintenance as means of mitigating such effects. Specifically the goals of the program are as follows: (1) to identify and characterize aging and service wear effects which, if unchecked, could cause degradation of structures, components, and systems and thereby impair plant safety; (2) to identify methods of inspection, surveillance and monitoring, or of evaluating residual life of structures, components, and systems, which will assure timely detection of significant aging effects prior to loss of safety function; and (3) to evaluate the effectiveness of storage, maintenance, repair and replacement practices in mitigating the rate and extent of degradation caused by aging and service wear

  9. Nuclear program of Iran plans and development

    International Nuclear Information System (INIS)

    2016-01-01

    Described are the history of nuclear energy planning in Iran and the development of the Bushehr Nuclear Power Plant (BNPP-1) project and its impact on the competency building in national companies, nuclear safety infrastructure, training activities, public awareness and acceptance. The activities of Nuclear Engineering Department is also presented. In order to enhance technical support services to BNPP1 and also to use capabilities of other companies in the international arena and in line with safe and reliable operation of Bushehr Nuclear Power Plant, NPPD/TAVANA Company has attempted to make contact with many companies outside the country

  10. Interim reliability evaluation program: analysis of the Arkansas Nuclear One. Unit 1 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Kolb, G.J.; Kunsman, D.M.; Bell, B.J.

    1982-06-01

    This report represents the results of the analysis of Arkansas Nuclear One (ANO) Unit 1 nuclear power plant which was performed as part of the Interim Reliability Evaluation Program (IREP). The IREP has several objectives, two of which are achieved by the analysis presented in this report. These objectives are: (1) the identification, in a preliminary way, of those accident sequences which are expected to dominate the public health and safety risks; and (2) the development of state-of-the-art plant system models which can be used as a foundation for subsequent, more intensive applications of probabilistic risk assessment. The primary methodological tools used in the analysis were event trees and fault trees. These tools were used to study core melt accidents initiated by loss of coolant accidents (LOCAs) of six different break size ranges and eight different types of transients

  11. Overall quality assurance program requirements for nuclear power plants

    International Nuclear Information System (INIS)

    1992-09-01

    This standard contains the requirements for the owner's overall quality assurance program for a nuclear power plant. This program encompasses all phases of a nuclear power plant life cycle, including site evaluation, design, procurement, manufacturing, construction and installation, commissioning, operation, and decommissioning. It covers the activities associated with specifying, directing, and administering the work to be done during these phases, and the evaluation and integrated of the activities and programs of participants

  12. An assessment of the inventory of uranium consumption and HLW production by the Angra 2 Nuclear Power Plant using the VISTA program

    Energy Technology Data Exchange (ETDEWEB)

    Goncalves, Leticia C.; Moreira, Joao M. L.; Maiorino, Jose R., E-mail: goncalves.leticia@ufabc.edu.br [Universidade Federal do ABC (UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Sociais Aplicadas

    2017-11-01

    This article presents an estimation of the inventory of spent nuclear fuel from Angra 2 accumulated over the years. We consider for that two situations: a) the once-through fuel cycle, and b) a cycle with partial reprocessing to recycle the fissile material. The results show that there are currently about 400 ton of spent fuel stored in Angra 2, and that its storage limit will be exhausted in the next 9 years. This is a worrying issue because, without the intention of reprocessing the fuel, and without the license to build a definitive repository, in less than a decade, Angra 2 would be required to cease its operation. This may not occur if some storage facility is built in the CNAAA site. It is hoped, therefore, that more work like this will is carried out to alert the competent authorities about the damage that will ensue if measures are not established in due time. (author)

  13. Fuel isolation research for the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    1982-06-01

    This document is intended to give a broad outline of the Fuel Isolatikn program and to indicate how this program fits into the overall framework of the Canadian Nuclear Fuel Waste Management Program. Similar activities in other countries are described, and the differences in philosophy behind these and the Canadian program are highlighted. A program plan is presented that outlines the development of research programs that contribute to the safety assessment of the disposal concept and the development of technology required for selection and optimization of a feasible fuel isolation system. Some indication of the work that might take place beyond concept assessment, at the end of the decade, is also given. The current program is described in some detail, with emphasis on what the prkgram has achieved to date and hopes to achieve in the future for the concept assessment phase of the waste management program. Finally, some major capital facilities associated with the fuel isolation program are described

  14. Nuclear plant service water system aging degradation assessment: Phase 1

    International Nuclear Information System (INIS)

    Jarrell, D.B.; Johnson, A.B. Jr.; Zimmerman, P.W.; Gore, M.L.

    1989-06-01

    The initial phase of an aging assessment of nuclear power plant service water systems (SWSs) was performed by the Pacific Northwest Laboratory to support the Nuclear Regulatory Commission Nuclear Plant Aging Research (NPAR) program. The SWS was selected for study because of its essential role in the mitigation of and recovery from accident scenarios involving the potential for core-melt. The objectives of the SWS task under the NPAR program are to identify and characterize the principal aging degradation mechanisms relevant to this system and assess their impact on operational readiness, and to provide a methodology for the mitigation of aging on the service water aspect of nuclear plant safety. The first two of these objectives have been met and are covered in this Phase 1 report. A review of available literature and data-base information indicated that motor operated valve torque switches (an electro-mechanical device) were the prime suspect in component service water systems failures. More extensive and detailed data obtained from cooperating utility maintenance records and personnel accounts contradicted this conclusion indicating that biologic and inorganic accumulation and corrosive attack of service water on component surfaces were, in fact, the primary degradation mechanisms. A review of the development of time dependent risk assessment (aging) models shows that, as yet, this methodology has not been developed to a degree where implementation is reliable. Improvements in the accuracy of failure data documentation and time dependent risk analysis methodology should yield significant gains in relating aging phenomena to probabilistic risk assessment. 23 refs., 8 figs., 10 tabs

  15. Nuclear data needs for US fast reactor programs

    International Nuclear Information System (INIS)

    Daughtry, J.W.; Rawlins, J.A.

    1985-05-01

    Recent developments in US Fast Reactor Programs are reviewed to provide a background for the nuclear data needs of these programs. Innovative designs, inherent safety, and space nuclear power are receiving increased emphasis. Longstanding and newly-identified nuclear data requirements are reviewed. These requirements are based on information obtained early in 1985 in response to an inquiry sent out by the authors. Finally, plans are outlined for development of an adjusted cross section set for FFTF reload design. The adjustment process suggests some possible changes in ENDF/B-V nuclear data

  16. AREN has going into action for nuclear program in Romania

    International Nuclear Information System (INIS)

    Chirica, T.; Mauna, T.

    2000-01-01

    Romania has been a member of world nuclear power community since December 1996 when the first Candu type nuclear unit became fully in service in Cernavoda NPP. The nominal power rating of the Unit is 706 MWe, covering about 10% of country's annual consumption. Now, the major issues of the Romanian nuclear sector is to promote and develop the activities regarding completion of the second unit at the Cernavoda site, connected to the natural uranium chain and waste management. The Romanian 'Nuclear Energy' Association (AREN) operates as a non-governmental and non-profit organization member of the European Nuclear Society and has been involved since 1990 in the nuclear field as a professional society and members of Council of AREN work as volunteers. The main programs developed by AREN are: 1. Nuclear Energy Days, organized in the last i quarter of the year; 2. International Nuclear Energy Symposium - SIEN, organized every two years; 3. Round Tables dedicated to different aspects of the nuclear energy, mainly addressed to the specialists. The intention of this paper is to discuss the impact of the reduction of the Romanian nuclear program on the different categories of people and companies involved in nuclear field, including the difficult aspect of nuclear brain drain. (authors)

  17. NPP Mochovce nuclear safety enhancement program

    International Nuclear Information System (INIS)

    Cech, J.; Baumester, P.

    1997-01-01

    Nuclear power plant Mochovce is currently under construction and an extensive nuclear safety enhancement programme is under way. The upgrading and modifications are based on IAEA documents and on those of the Nuclear Regulatory Authority of the Slovak Republic. Based on a contract concluded with Riskaudit from the CEC, safety examinations of the Mochovce design were performed. An extensive list of technical specifications of safety measures is given. (M.D.)

  18. Promotion of Bilateral Cooperative Programs in Nuclear Human Resources Development

    International Nuclear Information System (INIS)

    Lee, E. J.; Han, K. W.; Nam, Y. M.

    2009-08-01

    The purpose of this project is strengthening of bilateral cooperation with those countries for sharing Korea's technology, and providing of education and training on Korean experience regarding national nuclear policy, technology self reliance, and technology itself, in the field of nuclear power generation and the application of radioisotopes and radiation. This project covers an analysis on the need of nuclear human resource development in countries having interest in the introduction of nuclear power and/or promotion of the use of nuclear energy, and provision of courses on 'nuclear power policy, planning and management' and 'design and operation of nuclear research reactor, and application of radiation technology' along with the country specific needs. Education and training of key members in nuclear energy development from Egypt: It was implemented through bilateral cooperation and support by KOICA program. The first part, which targeted staff members from Egypt Nuclear Commission, was held for 2 months providing a KOICA course on policy, planning and management for nuclear power project, and second part was on the job training in Korea Hydro and Nuclear Power and Korea Institute of Nuclear Safety, KAERI respectively. On the job training of 1 scientist from Vietnam was implemented on the basis of bilateral cooperation in a research laboratory on radioactive waste treatment technology, at KAERI. Education and training for scientists from South East RCA countries were carried out for 11 participants from Vietnam, Thailand, Indonesia, China, Pakistan, Malaysia, Philippines, and Bangladesh. The course dealt with nuclear research reactor and radiation application technology. Development of nuclear education and training programs for key persons involved in nuclear power projects from countries of Middle East: The developed program consists of 15 courses addressing 3 technical levels, i.e. high level policy makers, middle level project implementers, and beginners

  19. Promotion of Bilateral Cooperative Programs in Nuclear Human Resources Development

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Han, K. W.; Nam, Y. M. (and others)

    2009-08-15

    The purpose of this project is strengthening of bilateral cooperation with those countries for sharing Korea's technology, and providing of education and training on Korean experience regarding national nuclear policy, technology self reliance, and technology itself, in the field of nuclear power generation and the application of radioisotopes and radiation. This project covers an analysis on the need of nuclear human resource development in countries having interest in the introduction of nuclear power and/or promotion of the use of nuclear energy, and provision of courses on 'nuclear power policy, planning and management' and 'design and operation of nuclear research reactor, and application of radiation technology' along with the country specific needs. Education and training of key members in nuclear energy development from Egypt: It was implemented through bilateral cooperation and support by KOICA program. The first part, which targeted staff members from Egypt Nuclear Commission, was held for 2 months providing a KOICA course on policy, planning and management for nuclear power project, and second part was on the job training in Korea Hydro and Nuclear Power and Korea Institute of Nuclear Safety, KAERI respectively. On the job training of 1 scientist from Vietnam was implemented on the basis of bilateral cooperation in a research laboratory on radioactive waste treatment technology, at KAERI. Education and training for scientists from South East RCA countries were carried out for 11 participants from Vietnam, Thailand, Indonesia, China, Pakistan, Malaysia, Philippines, and Bangladesh. The course dealt with nuclear research reactor and radiation application technology. Development of nuclear education and training programs for key persons involved in nuclear power projects from countries of Middle East: The developed program consists of 15 courses addressing 3 technical levels, i.e. high level policy makers, middle level project

  20. 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

  1. 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.

  2. A comprehensive program of nuclear engineering and science education

    International Nuclear Information System (INIS)

    Bereznai, G.; Lewis, B.

    2014-01-01

    The University of Ontario Institute of Technology offers undergraduate degrees in nuclear engineering, nuclear power, health physics and radiation science, graduate degrees (masters as well as doctorate) in nuclear engineering, and graduate diplomas that encompass a wide range of nuclear engineering and technology topics. Professional development programs tailored to specific utility needs are also offered, and the sharing of course material between the professional development and university education courses has strengthened both approaches to ensuring the high qualification levels required of professionals in the nuclear industry. (author)

  3. Creating a safe and stable nuclear program

    International Nuclear Information System (INIS)

    Muntzing, L.M.

    1993-01-01

    The institutional framework surrounding the development of the peaceful atom in many countries is composed of laws and implementing regulations. In the United States, this commenced with President Eisenhower's pledge in his 1953 address to the United National General Assembly that the United States would open-quotes devote its entire heart and mind to find the way by which the miraculous inventiveness of man shall not be dedicated to his death but consecrated to his life.close quotes Following this statement by President Eisenhower, the Atomic Energy Act of 1954 was enacted. The 1954 Act declared it to be the policy of the United States that open-quotes the development, use, and control of atomic energy shall be directed so as to make the maximum contribution to the general welfare.close quotes It directed the Atomic Energy Commission to conduct programs of research and development leading to the utilization of atomic energy for medical, biological, agricultural, health, industrial, or commercial purposes, including the generation of usable energy. From this beginning has come a never ending stream of innovations which has already contributed in a monumental way to human betterment. In the process, public and employee health and safety have been protected. Any objective evaluation must conclude that great benefits to the public have been achieved and the risk extraordinarily well managed. This legal and regulatory framework has worked well to benefit the public interest. The concept of laws and regulations defining the uses of peaceful nuclear energy applications has protected the public and operated for the benefit of mankind in many countries. Common principles exist, but diversity is also important

  4. Assessing the risk of nuclear energy

    International Nuclear Information System (INIS)

    Letourneau, E.G.; McCullough, R.S.; Meyerhof, D.P.; Somers, E.; Waight, P.J.

    1981-01-01

    The current concern with diminishing supplies of non-renewable energy has brought into clearer focus the debate on the future of nuclear energy. Application of the risk assessment process to the biological effects of radiation is considered worthwhile so that the nature and order of the hazards entailed can be appreciated in the total context of the problem. The derivation of regulations and the process of cost-risk-benefit analysis are also discussed. In view of the widespread public concern and, on occasion, apprehension about the development of nuclear energy it has been thought useful to tabulate the elements of this concern so as to gain a fuller understanding of the manner in which the public perceives and weighs risks. (author)

  5. Fatigue assessments in operating nuclear power plants

    International Nuclear Information System (INIS)

    Gosselin, S.R.; Deardorff, A.F.; Peltola, D.W.

    1994-01-01

    In November 1991, the ASME Section XI Task Group on Operating Plant Fatigue Assessment was formed to develop criteria and evaluation methodology for evaluating the effects of cyclic operation in operating nuclear power plants. The objective was to develop guidelines for inclusion in Section XI that could be used by plant operators in evaluating fatigue concerns and their impact on serviceability. This paper discusses the work performed by the Task Group. It explores the concept of ''Fatigue Design Basis'' versus ''Fatigue Operating Basis'' by examining the roles of ASME Section III and ASME Section XI in the design and operation of the nuclear power plants. Guidelines are summarized that may help plant operators perform effective design transient cycle evaluations and optimize cycle counting and fatigue usage tracking. The alternative fatigue evaluation approach using flaw tolerance is also introduced

  6. Reliability assessment of nuclear structural systems

    International Nuclear Information System (INIS)

    Reich, M.; Hwang, H.

    1983-01-01

    Reliability assessment of nuclear structural systems has been receiving more emphasis over the last few years. This paper deals with the recent progress made by the Structural Analysis Division of Brookhaven National Laboratory (BNL), in the development of a probability-based reliability analysis methodology for safety evaluation of reactor containments and other seismic category I structures. An important feature of this methodology is the incorporation of finite element analysis and random vibration theory. By utilizing this method, it is possible to evaluate the safety of nuclear structures under various static and dynamic loads in terms of limit state probability. Progress in other related areas, such as the establishment of probabilistic characteristics for various loads and structural resistance, are also described. Results of an application of the methodology to a realistic reinforced concrete containment subjected to dead and live loads, accidental internal pressures and earthquake ground accelerations are presented

  7. Status of US program for disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    Smith, R.I.

    1991-04-01

    In this paper, a brief history of the United States' program for the disposal of spent nuclear fuel (SNF) and the legislative acts that have guided the program are discussed. The current plans and schedules for beginning acceptance of SNF from the nuclear utilities for disposal are described, and some of the development activities supporting the program are discussed. And finally, the viability of the SNF disposal fee presently paid into the Nuclear Waste Fund by the owners/generators of commercial SNF and high-level waste (HLW) is examined. 12 refs., 9 figs

  8. A state perspective on the Nuclear Waste Policy Act program

    International Nuclear Information System (INIS)

    Stucker, J.J.

    1986-01-01

    The author discusses the problems he sees with the Nuclear Waste Policy Act (NWPA) program. He labels the problems as: against the law, all the eggs in one basket, acceptance rate, and the MRS program. The author comments of five issues that need to be addressed to right the wrongs of the NWPA program

  9. Programmatic Assessment of Radioactive Waste Management Nuclear Fuel And Waste Programs. Operational Planning and Development (Activity No. AR OS 10 05 K; ONL-WN06)

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1980-06-30

    Gilbert/Commonwealth (G/C) has performed an assessment of the waste management operations at Oak Ridge National Laboratory (ORNL). The objective of this study was to review radioactive waste management as practiced at ORNL and to recommend improvements or alternatives for further study. The study involved: 1) an on-site survey of ORNL radioactive waste management operations; 2) a review of radioactive waste source data, records, and regulatory requirements; 3) an assessment of existing and planned treatment, storage, and control facilities; and 4) identification of alternatives for improving waste management operations. Information for this study was obtained from both personal interviews and written reports. The G/C suggestions for improving ORNL waste management operations are summarized. Regulatory requirements governing ORNL waste management operations are discussed. Descriptions and discussions of the radioactive liquid, solid, and gaseous waste systems are presented. The waste operations control complex is discussed.

  10. The international framework for safeguarding peaceful nuclear energy programs

    International Nuclear Information System (INIS)

    Mazer, B.M.

    1980-01-01

    International law, in response to the need for safeguard assurances, has provided a framework which can be utilized by supplier and recipient states. Multilateral treaties have created the International Atomic Energy Agency which can serve a vital role in the establishment and supervision of safeguard agreements for nuclear energy programs. The Non-Proliferation Treaty has created definite obligations on nuclear-weapon and non-nuclear weapon states to alleviate some possibilities of proliferation and has rejuvenated the function of the IAEA in providing safeguards, especially to non-nuclear-weapon states which are parties to the Non-Proliferation treaty. States which are not parties to the Non-Proliferation Treaty may receive nuclear energy co-operation subject to IAEA safeguards. States like Canada, have insisted through the bilateral nuclear energy co-operation agreements that either individual or joint agreement be reached with the IAEA for the application of safeguards. Trilateral treaties among Canada, the recipient state and the IAEA have been employed and can provide the necessary assurances against the diversion of peaceful nuclear energy programs to military or non-peaceful uses. The advent of the Nuclear Suppliers Group and its guidlines has definitely advanced the cause of ensuring peaceful uses of nuclear energy. The ultimate objective should be the creation of an international structure incorporating the application of the most comprehensive safeguards which will be applied universally to all nuclear energy programs

  11. Nordic Nuclear Safety Research. Presentation of the 1994 - 1997 program

    International Nuclear Information System (INIS)

    Bennerstedt, Torkel

    1998-01-01

    NKS (Nordic Nuclear Safety Research) has just concluded its fifth 4-year program (1994 - 1997). The following nine projects were performed: Strategy for reactor safety: Studies of preparatory work to minimize the risk of accidents; Prevention of severe reactor accidents: studies of recriticality, core melt progression and support systems to minimize releases; Safe disposal of radioactive waste: Waste characterization, Performance analyses and environmental impact statements for repositories; Marine radioecology: Improved assessment methods for effects of releases of radionuclides; Long ecological half-lives in semi-natural systems: Models for transfer of cesium from nature to man; Preparedness strategies and procedures: Mobile measurements, quality assurance and interventions; Emergency preparedness drills and exercises; Preplanning of early cleanup: Check-list for planners and decision makers for various environments and fallout situations; Overriding information issues: Risk communication, real-time exchange of information after an accident. Together with additional financial support from a number of ministries and companies in the nuclear power field, the total NKS budget for the period 1994 - 1997 was some USD 5 million, evenly distributed over the years. To this should be added contributions in kind by participating organizations, worth at least another USD 10 million, without which this program would not have been possible. The nine projects and some practical results (rather than scientific detail) are outlined in this paper. (EG)

  12. Psychometric model for safety culture assessment in nuclear research facilities

    International Nuclear Information System (INIS)

    Nascimento, C.S. do; Andrade, D.A.; Mesquita, R.N. de

    2017-01-01

    Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

  13. Psychometric model for safety culture assessment in nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Nascimento, C.S. do, E-mail: claudio.souza@ctmsp.mar.mil.br [Centro Tecnológico da Marinha em São Paulo (CTMSP), Av. Professor Lineu Prestes 2468, 05508-000 São Paulo, SP (Brazil); Andrade, D.A., E-mail: delvonei@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil); Mesquita, R.N. de, E-mail: rnavarro@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil)

    2017-04-01

    Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

  14. The role of risk assessment in the nuclear regulatory process

    International Nuclear Information System (INIS)

    Levine, S.

    1979-01-01

    Since the publication of the Reactor Safety Study in the USA, the basic tasks of which are summarised, the use of quantitative risk-assessment techniques for the safety of nuclear power plants has increased considerably. Some of the viewpoints expressed on the use of these techniques are examined, and their limitations are discussed. Areas where risk-assessment techniques are applied by the NRC are listed and some recent examples are discussed. Risk assessment has also been used as a criteria for deciding the topics for the NRC's recommendations for research programs. It is concluded that the major contribution of risk assessment techniques should be in the form of background analyses that will aid decision making and could also significantly affect the scope and content of regulatory reviews. (UK)

  15. Iranian Nuclear Program: a Threat or a Demand for Equality?

    Directory of Open Access Journals (Sweden)

    Primož Šterbenc

    2013-06-01

    Full Text Available Ever since 2002 relations between the West and Israel on the one hand and Iran on the other have been deteriorating due to the contentious issue of Iranian nuclear programme. Israel and the US have been claiming that there has been a secret Iranian nuclear weapons program, on the grounds that Iran has persisted in its effort to acquire independent uranium enrichment capability and has since 2006 allowed only limited inspections by the International Atomic Energy Agency. Iran has been claiming that its nuclear program is entirely peaceful. Today, one certainly cannot exclude possibility of a military attack on Iranian nuclear facilities. However, one cannot properly understand the problem without taking into account the historical and structural dimensions. Namely, Iran's nuclear policy has been guided by country's determination that it will become independent and self-reliant in every possible field – a result of its very negative historical experience. Thus, Iran has been determined to fully exercise its right to peaceful nuclear development, to which it is entitled according to the Treaty on the Non-Proliferation of Nuclear Weapons. Iran has been striving to overcome the structural dependence of developing countries in the field of nuclear energy, as they have been denied the possibility of comprehensive nuclear development for peaceful purposes by countries possessing developed nuclear industries. The latter have prevented balanced implementation of the Treaty on the Non-Proliferation of Nuclear Weapons.

  16. The Maryland nuclear science baccalaureate degree program: The university perspective

    International Nuclear Information System (INIS)

    Janke, T.A.

    1989-01-01

    Nuclear utilities' efforts in response to industry-wide pressures to provide operations staff with degree opportunities have encountered formidable barriers. This paper describes, from the university's perspective, the development and operation of the University of Maryland University College (UMUC) special baccalaureate program in nuclear science. This program has successfully overcome these problems to provide degree education on-site, on-line, and on time. Program delivery began in 1984 with one utility and a single site. It is currently delivered at eight sites under contract to six utilities with a total active student count of over 500. The first graduates are expected in 1989. The program is an accredited university program and enjoys licensure approval from the six states within which it operates. In addition to meeting US Nuclear Regulatory Commission proposed guidelines for degreed operators, the program increasingly appears as part of utility management development programs for all plant personnel and a factor in employee retention. The owner utilities, the University of Maryland, and the growing user's group are committed to the academic integrity, technical capability, and responsiveness of the program. The full support of this partnership speaks well for the long-term service of the Bachelor of Science in Nuclear Science program to the nuclear power industry

  17. International Code Assessment and Applications Program: Annual report

    International Nuclear Information System (INIS)

    Ting, P.; Hanson, R.; Jenks, R.

    1987-03-01

    This is the first annual report of the International Code Assessment and Applications Program (ICAP). The ICAP was organized by the Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission (USNRC) in 1985. The ICAP is an international cooperative reactor safety research program planned to continue over a period of approximately five years. To date, eleven European and Asian countries/organizations have joined the program through bilateral agreements with the USNRC. Seven proposed agreements are currently under negotiation. The primary mission of the ICAP is to provide independent assessment of the three major advanced computer codes (RELAP5, TRAC-PWR, and TRAC-BWR) developed by the USNRC. However, program activities can be expected to enhance the assessment process throughout member countries. The codes were developed to calculate the reactor plant response to transients and loss-of-coolant accidents. Accurate prediction of normal and abnormal plant response using the codes enhances procedures and regulations used for the safe operation of the plant and also provides technical basis for assessing the safety margin of future reactor plant designs. The ICAP is providing required assessment data that will contribute to quantification of the code uncertainty for each code. The first annual report is devoted to coverage of program activities and accomplishments during the period between April 1985 and March 1987

  18. Management assessments of Quality Assurance Program implementation effectiveness

    International Nuclear Information System (INIS)

    Snyder, D.A.

    1984-01-01

    This paper describes a method currently being used by UNC Nuclear Industries, Richland, Washington, to help assure the effectiveness of Quality Assurance (QA) Program implementation. Assessments are conducted annually by management in each department, and the results summarized to the president and his staff. The purpose of these assessments is to review the adequacy of the department's implementing procedures, training/instruction on implementing procedures, and procedure implementation effectiveness. The primary purpose is to assess effectiveness and take improvement action where the need is indicated. The QA organization provides only general guidance in conducting the assessments

  19. Proliferation resistance assessment of nuclear systems

    International Nuclear Information System (INIS)

    1978-09-01

    The first part of the present paper describes the basic assessment procedure that is adopted in the analysis of the three generic nuclear systems. Once-through, fast breeder, and thermal recycle systems are then treated in Sections II, III, and IV, respectively. In each of these sections, a reference system is examined, possible technical and institutional improvements are considered, and alternative system types are indicated. Section V then discusses the relative proliferation resistance of the three generic systems. Although this paper emphasizes the analysis and comparison of individual fuel cycle alternatives, Section V indicates briefly how these analyses then have to be considered in a broader context where systems coexist

  20. Nuclear air cleaning programs in progress in France

    International Nuclear Information System (INIS)

    Mulcey, P.

    1991-01-01

    A short presentation is given of the nuclear air cleaning programs in progress in France with respect to pressurized water reactors, fuel reprocessing plants, radioactive waste management facilities, and the dismantling of nuclear facilities. The effects of fires in rooms and ventilation ducts in all nuclear facilities is being studied and computer simulation codes are being developed. A brief review of filter development and filter testing is also presented

  1. Uncertainty estimation in nuclear power plant probabilistic safety assessment

    International Nuclear Information System (INIS)

    Guarro, S.B.; Cummings, G.E.

    1989-01-01

    Probabilistic Risk Assessment (PRA) was introduced in the nuclear industry and the nuclear regulatory process in 1975 with the publication of the Reactor Safety Study by the U.S. Nuclear Regulatory Commission. Almost fifteen years later, the state-of-the-art in this field has been expanded and sharpened in many areas, and about thirty-five plant-specific PRAs (Probabilistic Risk Assessments) have been performed by the nuclear utility companies or by the U.S. Nuclear Regulatory commission. Among the areas where the most evident progress has been made in PRA and PSA (Probabilistic Safety Assessment, as these studies are more commonly referred to in the international community outside the U.S.) is the development of a consistent framework for the identification of sources of uncertainty and the estimation of their magnitude as it impacts various risk measures. Techniques to propagate uncertainty in reliability data through the risk models and display its effect on the top level risk estimates were developed in the early PRAs. The Seismic Safety Margin Research Program (SSMRP) study was the first major risk study to develop an approach to deal explicitly with uncertainty in risk estimates introduced not only by uncertainty in component reliability data, but by the incomplete state of knowledge of the assessor(s) with regard to basic phenomena that may trigger and drive a severe accident. More recently NUREG-1150, another major study of reactor risk sponsored by the NRC, has expanded risk uncertainty estimation and analysis into the realm of model uncertainty related to the relatively poorly known post-core-melt phenomena which determine the behavior of the molten core and of the rector containment structures

  2. Introducing Knowledge Management in Study Program of Nuclear Engineering

    International Nuclear Information System (INIS)

    Pleslic, S.

    2012-01-01

    to introduce concept of knowledge management in study program of nuclear engineering to prepare future nuclear professionals on adequate actions.(author).

  3. The Department of Energy nuclear criticality safety program

    International Nuclear Information System (INIS)

    Felty, J.R.

    2004-01-01

    This paper broadly covers key events and activities from which the Department of Energy Nuclear Criticality Safety Program (NCSP) evolved. The NCSP maintains fundamental infrastructure that supports operational criticality safety programs. This infrastructure includes continued development and maintenance of key calculational tools, differential and integral data measurements, benchmark compilation, development of training resources, hands-on training, and web-based systems to enhance information preservation and dissemination. The NCSP was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 97-2, Criticality Safety, and evolved from a predecessor program, the Nuclear Criticality Predictability Program, that was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 93-2, The Need for Critical Experiment Capability. This paper also discusses the role Dr. Sol Pearlstein played in helping the Department of Energy lay the foundation for a robust and enduring criticality safety infrastructure.

  4. Genesis of the Brazilian nuclear power plants program

    International Nuclear Information System (INIS)

    Syllus, G.; Lepecki, W.

    1996-01-01

    The genesis of the Brazilian Nuclear Power Program is described by the authors - who participated in the events - from the beginning of the sixties, until the definition and the start of the implementation in 1975 of the Reference Nuclear Power Program. A description is made of the main events, studies and decisions that contributed to the evolution of the Program: the GTRP (Nuclear Power Plant Working Group); the Thorium Group; the Lane Group; the decision about Angra 1; CNEN's analyses about the reactor line and, finally, the creation of CBTN (Nuclear Technology Brazilian Company), which elaborated the studies that resulted in the final definition of the Program and led to the Brazilian German Agreement and the establishment of NUCLEBRAS. (author)

  5. Industrial development - consequences about the implantation of Brazilian Nuclear Program

    International Nuclear Information System (INIS)

    Syllus, C.

    1987-07-01

    The strategy to promote the growing industry participation in the Brazilian Nuclear Program, the difficulties, the measurements adopted for overcoming and the results obtained in terms of industrial development, are presented. (M.C.K.) [pt

  6. Nuclear Human Resources Development Program using Educational Core Simulator

    International Nuclear Information System (INIS)

    Choi, Yu Sun; Hong, Soon Kwan

    2015-01-01

    KHNP-CRI(Korea Hydro and Nuclear Power Co.-Central Research Institute) has redesigned the existing Core Simulator(CoSi) used as a sort of training tools for reactor engineers in operating nuclear power plant to support Nuclear Human Resources Development (NHRD) Program focusing on the nuclear department of Dalat university in Vietnam. This program has been supported by MOTIE in Korea and cooperated with KNA(Korea Nuclear Association for International Cooperation) and HYU(Hanyang University) for enhancing the nuclear human resources of potential country in consideration with Korean Nuclear Power Plant as a next candidate energy sources. KHNP-CRI has provided Edu-CoSi to Dalat University in Vietnam in order to support Nuclear Human Resources Development Program in Vietnam. Job Qualification Certificates Program in KHNP is utilized to design a training course for Vietnamese faculty and student of Dalat University. Successfully, knowhow on lecturing the ZPPT performance, training and maintaining Edu-CoSi hardware are transferred by several training courses which KHNP-CRI provides

  7. Nuclear Human Resources Development Program using Educational Core Simulator

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Yu Sun; Hong, Soon Kwan [KHNP-CRI, Daejeon (Korea, Republic of)

    2015-10-15

    KHNP-CRI(Korea Hydro and Nuclear Power Co.-Central Research Institute) has redesigned the existing Core Simulator(CoSi) used as a sort of training tools for reactor engineers in operating nuclear power plant to support Nuclear Human Resources Development (NHRD) Program focusing on the nuclear department of Dalat university in Vietnam. This program has been supported by MOTIE in Korea and cooperated with KNA(Korea Nuclear Association for International Cooperation) and HYU(Hanyang University) for enhancing the nuclear human resources of potential country in consideration with Korean Nuclear Power Plant as a next candidate energy sources. KHNP-CRI has provided Edu-CoSi to Dalat University in Vietnam in order to support Nuclear Human Resources Development Program in Vietnam. Job Qualification Certificates Program in KHNP is utilized to design a training course for Vietnamese faculty and student of Dalat University. Successfully, knowhow on lecturing the ZPPT performance, training and maintaining Edu-CoSi hardware are transferred by several training courses which KHNP-CRI provides.

  8. Assessing New Employee Orientation Programs

    Science.gov (United States)

    Acevedo, Jose M.; Yancey, George B.

    2011-01-01

    Purpose: This paper aims to examine the importance of new employee orientation (NEO) programs, the quality of typical NEOs, and how to improve NEOs. Design/methodology/approach: The paper provides a viewpoint of the importance of new employee orientation programs, the quality of typical NEOs, and how to improve NEOs. Findings: Although western…

  9. Utility of Social Modeling in Assessment of a State's Propensity for Nuclear Proliferation

    International Nuclear Information System (INIS)

    Coles, Garill A.; Brothers, Alan J.; Whitney, Paul D.; Dalton, Angela C.; Olson, Jarrod; White, Amanda M.; Cooley, Scott K.; Youchak, Paul M.; Stafford, Samuel V.

    2011-01-01

    This report is the third and final report out of a set of three reports documenting research for the U.S. Department of Energy (DOE) National Security Administration (NASA) Office of Nonproliferation Research and Development NA-22 Simulations, Algorithms, and Modeling program that investigates how social modeling can be used to improve proliferation assessment for informing nuclear security, policy, safeguards, design of nuclear systems and research decisions. Social modeling has not to have been used to any significant extent in a proliferation studies. This report focuses on the utility of social modeling as applied to the assessment of a State's propensity to develop a nuclear weapons program.

  10. Utility of Social Modeling in Assessment of a State’s Propensity for Nuclear Proliferation

    Energy Technology Data Exchange (ETDEWEB)

    Coles, Garill A.; Brothers, Alan J.; Whitney, Paul D.; Dalton, Angela C.; Olson, Jarrod; White, Amanda M.; Cooley, Scott K.; Youchak, Paul M.; Stafford, Samuel V.

    2011-06-01

    This report is the third and final report out of a set of three reports documenting research for the U.S. Department of Energy (DOE) National Security Administration (NASA) Office of Nonproliferation Research and Development NA-22 Simulations, Algorithms, and Modeling program that investigates how social modeling can be used to improve proliferation assessment for informing nuclear security, policy, safeguards, design of nuclear systems and research decisions. Social modeling has not to have been used to any significant extent in a proliferation studies. This report focuses on the utility of social modeling as applied to the assessment of a State's propensity to develop a nuclear weapons program.

  11. Approaches to Education and Training for Kenya's Nuclear Power Program

    International Nuclear Information System (INIS)

    Kalambuka, H.A.

    2014-01-01

    1. Review of status and development of E and T for the nuclear power program in Kenya; 2. Review of challenges in nuclear E and T, and the initiatives being undertaken to mitigate them: • Recommendations for strategic action; 3. State of nuclear skills in the context of key drivers of the global revival in nuclear energy; 4. Point of view: Education in Applied Nuclear and Radiation physics at Nairobi: • Its growth has helped identify the gaps, and relevant practical approaches for realizing the broad spectrum of technical capacity to conduct a national NPP; 5. Proposed approach to support the E and T infrastructure necessary to allow the country to plan, construct, operate, regulate, and safely and securely handle nuclear facilities sustainably; 6. Specified E and T initiatives in the context of the national industrial development strategy and nuclear energy policy and funding for the complete life cycle and technology localization. (author)

  12. Programs for low-energy nuclear physics data processing

    International Nuclear Information System (INIS)

    Antuf'ev, Yu.P.; Dejneko, A.S.; Ekhichev, O.I.; Kuz'menko, V.A.; Mashkarov, Yu.G.; Nemashkalo, B.A.; Skakun, E.A.; Storizhko, V.E.; Shlyakhov, N.A.

    1978-01-01

    Purpose of six computer programs developed in KhPTI of AN USSR for the processing of the experimental data on low energy nuclear physics ia friendly described. The programs are written in Algol-60 language. They are applied to some types of nuclear reactions and permit to process differential cross sections and γ spectra, to compute statistical tensors and excitation functions as well as to analyze some processes by means of theoretical models

  13. Overview of the Nuclear Regulatory Commission's safety research program

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1989-01-01

    Accomplishments during 1988 of the Office of Nuclear Regulatory Research and the program of safety research are highlighted, and plans, expections, and needs of the next year and beyond are discussed. Topics discussed include: ECCS Appendix K Revision; pressurized thermal shock; NUREG-1150, or the PRA method performance document; resolution of station blackout; severe accident integration plan; nuclear safety research review committee; and program management

  14. NNSA Program Develops the Next Generation of Nuclear Security Experts

    Energy Technology Data Exchange (ETDEWEB)

    Brim, Cornelia P.; Disney, Maren V.

    2015-09-02

    NNSA is fostering the next generation of nuclear security experts is through its successful NNSA Graduate Fellowship Program (NGFP). NGFP offers its Fellows an exceptional career development opportunity through hands-on experience supporting NNSA mission areas across policy and technology disciplines. The one-year assignments give tomorrow’s leaders in global nuclear security and nonproliferation unparalleled exposure through assignments to Program Offices across NNSA.

  15. CRECTJ: a computer program for compilation of evaluated nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1999-09-01

    In order to compile evaluated nuclear data in the ENDF format, the computer program CRECTJ has been developed. CRECTJ has two versions; CRECTJ5 treats the data in the ENDF/B-IV and ENDF/B-V format, and CRECTJ6 the data in the ENDF-6 format. These programs have been frequently used to make Japanese Evaluated Nuclear Data Library (JENDL). This report describes input data and examples of CRECTJ. (author)

  16. Industrial Assessment Center Program Impact Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Martin, M.A.

    2000-01-26

    This report presents the results of an evaluation of the U.S. Department of Energy's Industrial Assessment Center (IAC) Program. The purpose of this program is to conduct energy, waste, and productivity assessments for small to medium-sized industrial firms. Assessments are conducted by 30 university-based industrial assessment centers. The purpose of this project was to evaluate energy and cost savings attributable to the assessments, the trained alumni, and the Websites sponsored by this program. How IAC assessments, alumni, and Web-based information may influence industrial energy efficiency decision making was also studied. It is concluded that appreciable energy and cost savings may be attributed to the IAC Program and that the IAC Program has resulted in more active and improved energy-efficiency decision making by industrial firms.

  17. The Drivers of Indias Nuclear Weapons Program

    Science.gov (United States)

    2014-06-01

    of-nerves. 158 Dean Nelson and Tom Hussain, “Militants Attack Pakistan Nuclear Air Base,” The Telegraph, August 16, 2012, http...hermetically sealed for storage and transport,” a process only possible now that India has largely moved to solid-fueled ballistic missiles.273...have become more hands-off with nuclear policy, since achievements in that field do not translate into electoral success. The Indian population

  18. BNL325 - Nuclear reaction data display program

    International Nuclear Information System (INIS)

    Dunford, C.L.

    1994-01-01

    A computer code for the graphical display of nuclear reaction data is described. The code, which works on a computer with VMS operating system, can overlay experimental data from an EXFOR/CSISRS table-computation format with evaluated data from ENDF formatted data libraries. Originally, this code has been used at the U.S. National Nuclear Data Center to produce the well-known neutron cross-section atlas published as report BNL-325. (author). 3 tabs

  19. BNL325 - Nuclear reaction data display program

    Energy Technology Data Exchange (ETDEWEB)

    Dunford, C L

    1994-11-27

    A computer code for the graphical display of nuclear reaction data is described. The code, which works on a computer with VMS operating system, can overlay experimental data from an EXFOR/CSISRS table-computation format with evaluated data from ENDF formatted data libraries. Originally, this code has been used at the U.S. National Nuclear Data Center to produce the well-known neutron cross-section atlas published as report BNL-325. (author). 3 tabs.

  20. Canadian programs on understanding and managing aging degradation of nuclear power plant components

    International Nuclear Information System (INIS)

    Chadha, J.A.; Pachner, J.

    1989-06-01

    Maintaining adequate safety and reliability of nuclear power plants and nuclear power plant life assurance and life extension are growing in importance as nuclear plants get older. Age-related degradation of plant components is complex and not fully understood. This paper provides an overview of the Canadian approach and the main activities and their results towards understanding and managing age-related degradation of nuclear power plant components, structures and systems. A number of pro-active programs have been initiated to anticipate, detect and mitigate potential aging degradation at an early stage before any serious impact on plant safety and reliability. These programs include Operational Safety Management Program, Nuclear Plant Life Assurance Program, systematic plant condition assessment, refurbishment and upgrading, post-service examination and testing, equipment qualification, research and development, and participation in the IAEA programs on safety aspects of nuclear power plant aging and life extension. A regulatory policy on nuclear power plants is under development and will be based on the domestic as well as foreign and international studies and experience

  1. Human Resources Requirements for New Nuclear Power Programs

    International Nuclear Information System (INIS)

    Goodnight, Charles T.

    2014-01-01

    Summary: Planning to Meet HR Requirements for New Nuclear Power Programs Must Begin Early. Many years of preparation are required before the “Right Number of the Right People” … will be … “In the Right Place at the Right Time”. • Seven key steps which must be taken include: 1) Identify detailed Human Resources requirements, based on the selected site and reactor design; 2) Conduct an assessment of national capacity to develop and/or provide those resources; 3) Conduct a Gap Analysis to determine what additional steps will be needed to fill any capacity shortfalls; 4) Develop initial and recurring recruiting and training plans; 5) Begin recruiting and training; 6) Review and adjust as personnel move and/or leave; 7) Ensure adequate relationships are in place for sources of future recruiting

  2. Nuclear-fuel-cycle costs. Consolidated Fuel-Reprocessing Program

    International Nuclear Information System (INIS)

    Burch, W.D.; Haire, M.J.; Rainey, R.H.

    1981-01-01

    The costs for the back-end of the nuclear fuel cycle, which were developed as part of the Nonproliferation Alternative Systems Assessment Program (NASAP), are presented. Total fuel-cycle costs are given for the pressurized-water reactor once-through and fuel-recycle systems, and for the liquid-metal fast-breeder-reactor system. These calculations show that fuel-cycle costs are a small part of the total power costs. For breeder reactors, fuel-cycle costs are about half that of the present once-through system. The total power cost of the breeder-reactor system is greater than that of light-water reactor at today's prices for uranium and enrichment

  3. Scenario-based roadmapping assessing nuclear technology development paths for future nuclear energy system scenarios

    International Nuclear Information System (INIS)

    Van Den Durpel, Luc; Roelofs, Ferry; Yacout, Abdellatif

    2009-01-01

    Nuclear energy may play a significant role in a future sustainable energy mix. The transition from today's nuclear energy system towards a future more sustainable nuclear energy system will be dictated by technology availability, energy market competitiveness and capability to achieve sustainability through the nuclear fuel cycle. Various scenarios have been investigated worldwide each with a diverse set of assumptions on the timing and characteristics of new nuclear energy systems. Scenario-based roadmapping combines the dynamic scenario-analysis of nuclear energy systems' futures with the technology roadmap information published and analysed in various technology assessment reports though integrated within the nuclear technology roadmap Nuclear-Roadmap.net. The advantages of this combination is to allow mutual improvement of scenario analysis and nuclear technology roadmapping providing a higher degree of confidence in the assessment of nuclear energy system futures. This paper provides a description of scenario-based roadmapping based on DANESS and Nuclear-Roadmap.net. (author)

  4. Angra nuclear plant - environmental control program

    International Nuclear Information System (INIS)

    Kircher, E.; Cruz, E.S. da

    1989-01-01

    The pre-operational studies, that were elaborated before the beginning of Angra I Power Plant operation, are described in particular the environmental radiological safety area till the fuel loading in the core reactor. Several aspects are included, as socio-economic survey, seismological analysis, Meteorological Program, marine biology, water cooling system, exposure measures of natural radiation, marine sediments characterization in the effluent dispersion area and Environmental Radiological Monitoring Program. The main environmental programs developed for the operational phase of the Angra I Plant are also presented, citing some considerations about the Meteorological Program, Marine Biology Control Program, Temperature and Chlorine Control in Piraquara de Fora Bay, Radiological Environmental Monitoring Program, Sanitary Effluent Control Program and Radiological Emergency Program. (C.G.C.). 2 refs

  5. Compartment modelling in nuclear medicine: a new program for the determination of transfer coefficients

    International Nuclear Information System (INIS)

    Hallstadius, L.

    1986-01-01

    In many investigations concerning transport/exchange of matter in a natural system, e.g. functional studies in nuclear medicine, it is advantageous to relate experimental results to a model of the system. A new computer program is presented for the determination of linear transfer coefficients in a compartment model from experimentally observed time-compartment content curves. The program performs a least-square fit with the specified precision of the observed values as weight factors. The resulting uncertainty in the calculated transfer coefficients may also be assessed. The application of the program in nuclear medicine is demonstrated and discussed. (author)

  6. Program management plan for the conduct of a research, development, and demonstration program for improving the safety of nuclear powerplants

    International Nuclear Information System (INIS)

    1981-12-01

    Congress passed Public Law 96-567, Nuclear Safety Research, Development, and Demonstration Act of 1980, (hereafter referred to as the Act) to provide for an accelerated and coordinated program of light water reactor safety research, development, and demonstration to be carried out by the Department of Energy. In order to assure that this program would be compatible with the needs of Nuclear Regulatory Commission (NRC) and industry, the Department of Energy (DOE) initiated its response to Section 4 of the Act by conducting individual information gathering meetings with NRC and a wide cross section of the nuclear industry. The Department received recommendations on needs of what type of activities would and would not be appropriate for the Department to assist in satisfying these needs. Based on the evaluation of these inputs, it is concluded that the Department's ongoing Light Water Reactor (LWR) safety program is responsive to the Act. Specifically, the Department's ongoing program includes tasks in the areas of regulatory assessment, risk assessment, fission product source term, and emergency preparedness as well as providing technical assistance to the Institute of Nuclear Power Operations (INPO) to improve training of nuclear power personnel. These were among the very high priority efforts that were identified as necessary and appropriate for support by the Department

  7. Outcomes Assessment in Dental Hygiene Programs.

    Science.gov (United States)

    Grimes, Ellen B.

    1999-01-01

    A survey of 22 dental-hygiene-program directors found that programs routinely and effectively assess student outcomes and use the information for program improvements and to demonstrate accountability. Both policy and faculty/administrative support were deemed important to implementation. Time constraints were a major barrier. Outcomes-assessment…

  8. ESP and NOAH: computer programs for flood-risk analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Wagner, D.P.; Montague, D.F.; Rooney, J.J.; Fussell, J.B.; Baker, L.S.

    1982-06-01

    This report describes a computer program package that aids in assessing the impact of floods on risk from nuclear power plants. The package consists of two distinct computer programs: ESP and NOAH. The ESP program improves the efficiency of a flood analysis by screening accident sequences and identifying accident sequences that are potentially significant contributors to risk in the event of a flood. Input to ESP includes accident sequences from an existing risk assessment and flood screening criteria. The NOAH program provides detailed qualitative analysis of the plant systems identified by ESP. NOAH performs a qualitative flood simulation of the fault tree

  9. Overview of the US spent nuclear fuel program

    International Nuclear Information System (INIS)

    Hurt, W.L.

    1999-01-01

    This report, Overview of the United States Spent Nuclear Fuel Program, December, 1997, summarizes the U.S. strategy for interim management and ultimate disposition of spent nuclear fuel from research and test reactors. The key elements of this strategy include consolidation of this spent nuclear fuel at three sites, preparation of the fuel for geologic disposal in road-ready packages, and low-cost dry interim storage until the planned geologic repository is opened. The U.S. has a number of research programs in place that are intended to Provide data and technologies to support both characterization and disposition of the fuel. (author)

  10. Matching grant program for university nuclear engineering education

    International Nuclear Information System (INIS)

    Bajorek, Stephen M.

    2002-01-01

    The grant augmented funds from Westinghouse Electric Co. to enhance the Nuclear Engineering program at KSU. The program was designed to provide educational opportunities and to train engineers for careers in the nuclear industry. It provided funding and access to Westinghouse proprietary design codes for graduate and undergraduate studies on topics of current industrial importance. Students had the opportunity to use some of the most advanced nuclear design tools in the industry and to work on actual design problems. The WCOBRA/TRAC code was used to simulate loss of coolant accidents (LOCAs)

  11. USA program on the waste disposal of nuclear military complexes

    International Nuclear Information System (INIS)

    Vinogradova, I.

    1992-01-01

    The USA program on the nuclear military complex waste disposal which focuses on the problems of environment protection and recovery is briefly considered. A group of works on the updating of the existing and on the construction of new nuclear weapon undustries is chosen to be the priority direction. The problem of radioactive waste burial in the Hunford nuclear complex is discussed. Total expenses for military enterprise purification from radioactive wastes are estimated as 91.2-129 billion dollars, and expenses for realization of the whole program are estimated as 180 billion dollars for 50 years

  12. EPRI Guide to Managing Nuclear Utility Protective Clothing Programs

    International Nuclear Information System (INIS)

    Kelly, J.J.; Kelly, D.M.

    1993-10-01

    The Electric Power Research Institute (EPRI) commissioned a radioactive waste related project (RP2414-34) in 1989 to produce a guide for developing and managing nuclear plant protective clothing programs. Every nuclear facility must coordinate some type of protective clothing program for its radiation workers to ensure proper and safe protection for the wearer and to maintain control over the spread of contamination. Yet, every nuclear facility has developed its own unique program for managing such clothing. Accordingly, a need existed for a reference guide to assist with standardizing protective clothing programs and in controlling the potentially escalating economics of such programs. The initial Guide to Managing Nuclear Utility Protective Clothing Programs, NP-7309, was published in May 1991. Since that time, a number of utilities have reviewed and/or used the report to enhance their protective clothing programs. Some of these utilities requested that a computer program be developed to assist utilities in evaluating the economics of protective clothing programs consistent with the guidance in NP-7309. The PCEVAL computer code responds to that industry need. This report, the PCEVAL User's Manual, provides detailed instruction on use of the software

  13. Aging assessment of large electric motors in nuclear power plants

    International Nuclear Information System (INIS)

    Villaran, M.; Subudhi, M.

    1996-03-01

    Large electric motors serve as the prime movers to drive high capacity pumps, fans, compressors, and generators in a variety of nuclear plant systems. This study examined the stressors that cause degradation and aging in large electric motors operating in various plant locations and environments. The operating history of these machines in nuclear plant service was studied by review and analysis of failure reports in the NPRDS and LER databases. This was supplemented by a review of motor designs, and their nuclear and balance of plant applications, in order to characterize the failure mechanisms that cause degradation, aging, and failure in large electric motors. A generic failure modes and effects analysis for large squirrel cage induction motors was performed to identify the degradation and aging mechanisms affecting various components of these large motors, the failure modes that result, and their effects upon the function of the motor. The effects of large motor failures upon the systems in which they are operating, and on the plant as a whole, were analyzed from failure reports in the databases. The effectiveness of the industry's large motor maintenance programs was assessed based upon the failure reports in the databases and reviews of plant maintenance procedures and programs

  14. Review of world nuclear power programs

    International Nuclear Information System (INIS)

    Rippon, S.

    1978-01-01

    Political, economic and environmental decisions are still affecting the growth of nuclear power generation throughout the world, but there are signs that proven past performance and increasing prices of energy from conventional sources are becoming overriding factors. In the USA, some uncertainty has been created by the moratorium on reprocessing enacted by the 1978 Non-Proliferation Act. The uncertainty has spread to importers of nuclear fuel and technology, but there is increasing international acceptance of the International Nuclear Fuel Cycle Evaluation. Isotope separation capacity to be installed by the US government, by the joint European organization Urenco and by the French Eurodif should ease the supply of fuel. There is little progress on waste-management policy in the USA, but in Germany a company (DWK) has been formed and a site for a rocksalt repository has been designated at Gorleben. In the UK the Windscale inquiry has a positive significance for nuclear energy generally as well as for reprocessing. An inquiry in Sweden has also come to positive conclusions. The status of nuclear energy in these and a number of other countries is discussed in terms of political and national policies. (N.D.H.)

  15. Defense Acquisitions: Assessments of Selected Weapon Programs

    Science.gov (United States)

    2017-03-01

    Figure 17: Examples of Knowledge Scorecards 61 Page vi GAO-17-333SP Assessments of Selected Weapon Programs...programs. Page 61 GAO-17-333SP Assessments of Selected Weapon Programs Figure 17: Examples of Knowledge Scorecards Pursuant to a...had direct access to the USD AT&L and other senior acquisition officials, and some approval authorities were delegated to lower levels. For example

  16. The Off-Site Plowshare and Vela Uniform Programs: Assessing Potential Environmental Liabilities through an Examination of Proposed Nuclear Projects,High Explosive Experiments, and High Explosive Construction Activities Volume 1 of 3

    Energy Technology Data Exchange (ETDEWEB)

    Beck Colleen M,Edwards Susan R.,King Maureen L.

    2011-09-01

    This document presents the results of nearly six years (2002-2008) of historical research and field studies concerned with evaluating potential environmental liabilities associated with U.S. Atomic Energy Commission projects from the Plowshare and Vela Uniform Programs. The Plowshare Program's primary purpose was to develop peaceful uses for nuclear explosives. The Vela Uniform Program focused on improving the capability of detecting, monitoring and identifying underground nuclear detonations. As a result of the Project Chariot site restoration efforts in the early 1990s, there were concerns that there might be other project locations with potential environmental liabilities. The Desert Research Institute conducted archival research to identify projects, an analysis of project field activities, and completed field studies at locations where substantial fieldwork had been undertaken for the projects. Although the Plowshare and Vela Uniform nuclear projects are well known, the projects that are included in this research are relatively unknown. They are proposed nuclear projects that were not executed, proposed and executed high explosive experiments, and proposed and executed high explosive construction activities off the Nevada Test Site. The research identified 170 Plowshare and Vela Uniform off-site projects and many of these had little or no field activity associated with them. However, there were 27 projects that merited further investigation and field studies were conducted at 15 locations.

  17. The Off-Site Plowshare and Vela Uniform Programs: Assessing Potential Environmental Liabilities through an Examination of Proposed Nuclear Projects,High Explosive Experiments, and High Explosive Construction Activities Volume 2 of 3

    Energy Technology Data Exchange (ETDEWEB)

    Beck Colleen M.,Edwards Susan R.,King Maureen L.

    2011-09-01

    This document presents the results of nearly six years (2002-2008) of historical research and field studies concerned with evaluating potential environmental liabilities associated with U.S. Atomic Energy Commission projects from the Plowshare and Vela Uniform Programs. The Plowshare Program's primary purpose was to develop peaceful uses for nuclear explosives. The Vela Uniform Program focused on improving the capability of detecting, monitoring and identifying underground nuclear detonations. As a result of the Project Chariot site restoration efforts in the early 1990s, there were concerns that there might be other project locations with potential environmental liabilities. The Desert Research Institute conducted archival research to identify projects, an analysis of project field activities, and completed field studies at locations where substantial fieldwork had been undertaken for the projects. Although the Plowshare and Vela Uniform nuclear projects are well known, the projects that are included in this research are relatively unknown. They are proposed nuclear projects that were not executed, proposed and executed high explosive experiments, and proposed and executed high explosive construction activities off the Nevada Test Site. The research identified 170 Plowshare and Vela Uniform off-site projects and many of these had little or no field activity associated with them. However, there were 27 projects that merited further investigation and field studies were conducted at 15 locations.

  18. The Off-Site Plowshare and Vela Uniform Programs: Assessing Potential Environmental Liabilities through an Examination of Proposed Nuclear Projects,High Explosive Experiments, and High Explosive Construction Activities Volume 3 of 3

    Energy Technology Data Exchange (ETDEWEB)

    Beck Colleen M.,Edwards Susan R.,King Maureen L.

    2011-09-01

    This document presents the results of nearly six years (2002-2008) of historical research and field studies concerned with evaluating potential environmental liabilities associated with U.S. Atomic Energy Commission projects from the Plowshare and Vela Uniform Programs. The Plowshare Program's primary purpose was to develop peaceful uses for nuclear explosives. The Vela Uniform Program focused on improving the capability of detecting, monitoring and identifying underground nuclear detonations. As a result of the Project Chariot site restoration efforts in the early 1990s, there were concerns that there might be other project locations with potential environmental liabilities. The Desert Research Institute conducted archival research to identify projects, an analysis of project field activities, and completed field studies at locations where substantial fieldwork had been undertaken for the projects. Although the Plowshare and Vela Uniform nuclear projects are well known, the projects that are included in this research are relatively unknown. They are proposed nuclear projects that were not executed, proposed and executed high explosive experiments, and proposed and executed high explosive construction activities off the Nevada Test Site. The research identified 170 Plowshare and Vela Uniform off-site projects and many of these had little or no field activity associated with them. However, there were 27 projects that merited further investigation and field studies were conducted at 15 locations.

  19. Virginia power nuclear power station engineer training program

    International Nuclear Information System (INIS)

    Williams, T.M.; Haberstroh-Timpano, S.

    1987-01-01

    In response to the Institute of Nuclear Power Operations (INPO) accreditation requirements for technical staff and manager, Virginia Power developed the Nuclear Power Station Engineer Training Programs (NPSETP). The NPSETP is directed toward enhancing the specific knowledge and skills of company engineers, especially newly hired engineers. The specific goals of the program are to promote safe and reliable plant operation by providing engineers and appropriate engineering technicians with (1) station-specific basic skills; (2) station-specific specialized skills in the areas of surveillance and test, plant engineering, nuclear safety, and in-service inspection. The training is designed to develop, maintain, and document through demonstration the required knowledge and skills of the engineers in the identified groups at North Anna and Surry Power Stations. The program responds to American National Standards Institute, INPO, and US Nuclear Regulatory Commission standards

  20. A History of the International Agreement on Iran's Nuclear Program

    International Nuclear Information System (INIS)

    Fabius, Laurent

    2016-01-01

    In May 2012, in the aftermath of the French presidential election, Iranian nuclear program posed a major challenge concerning both regional security questions and global efforts to prevent nuclear proliferation. The situation was characterized by a diplomatic stalemate, sanctions and the concerning development of Iran's nuclear program. Many fear that Iran's current program development will warrant military intervention in an effort to prevent further success. France therefore decided to implement a policy of 'constructive firmness' in the hope of reaching a robust and verifiable agreement that shows real progress in the international effort to prevent Iran from acquiring nuclear weapons. The following text is an accurate account of the process leading up to this major agreement by one of its main actors

  1. Code assessment and applications program

    International Nuclear Information System (INIS)

    Chapman, R.L.; Hanner, O.M. Jr.; Wells, M.E.

    1979-09-01

    This document presents the results of a review and evaluation of actual and potential water hammer events in both BWR and PWR power plants. Known or suspected water hammer events were reviewed and tabulated. Possible scenarios for potentially damaging water hammer occurrences in safety-related systems were developed. The effectiveness of subsystems and design features used to prevent water hammer and the potential for water hammer in certain systems due to various initiating mechanisms were also addressed. Specific recommendations on design, operational and testing criteria, and applicant/station operator requirements were made to prevent and avoid damaging water hammer in the design of future nuclear plants

  2. The United States Naval Nuclear Propulsion Program - Over 151 Million Miles Safely Steamed on Nuclear Power

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-03-01

    NNSA’s third mission pillar is supporting the U.S. Navy’s ability to protect and defend American interests across the globe. The Naval Reactors Program remains at the forefront of technological developments in naval nuclear propulsion and ensures a commanding edge in warfighting capabilities by advancing new technologies and improvements in naval reactor performance and reliability. In 2015, the Naval Nuclear Propulsion Program pioneered advances in nuclear reactor and warship design – such as increasing reactor lifetimes, improving submarine operational effectiveness, and reducing propulsion plant crewing. The Naval Reactors Program continued its record of operational excellence by providing the technical expertise required to resolve emergent issues in the Nation’s nuclear-powered fleet, enabling the Fleet to safely steam more than two million miles. Naval Reactors safely maintains, operates, and oversees the reactors on the Navy’s 82 nuclear-powered warships, constituting more than 45 percent of the Navy’s major combatants.

  3. Applying QA to nuclear-development programs

    International Nuclear Information System (INIS)

    Caplinger, W.H.

    1981-12-01

    The application of quality assurance (QA) principles to developmental programs is usually accomplished by tailoring or selecting appropriate requirements from large QA systems. Developmental work at Westinghouse Hanford Company (WHC) covers the complete range from basic research to in-core reactor tests. Desired requirements are selected from the 18 criteria in ANSI/ASME NQA Standard 1 by the cognizant program engineer in conjunction with the quality engineer. These referenced criteria assure that QA for the program is planned, implemented, and maintained. In addition, the WHC QA Manual provides four categories or levels of QA that are assigned to programs or components within the program. These categories are based on safety, reliability, and consequences of failure to provide a cost effective program

  4. Risk assessment and nuclear insurance: an overview

    International Nuclear Information System (INIS)

    Deitchman, J.V.; King, W.T. Jr.; Olding, R.P.

    1976-01-01

    In the nascent years of commercial nuclear power, the insurance industry expressed confidence in the safety of nuclear operations by committing unprecedented insurance capacity to nuclear risks. As the nuclear industry has developed, it has compiled an enviable safety record. The initial confidence of the insurance industry has thus been justified and an ever-increasing portion of the financial liability associated with nuclear operations has been accepted by the world-wide insurance markets. This increasing acceptance and understanding of nuclear risks by the insurance industry has resulted in significantly reduced rates and large premium refunds for nuclear operators

  5. Nuclear Engineering Academic Programs Survey, 2002 Data

    International Nuclear Information System (INIS)

    Oak Ridge Institute for Science and Education

    2003-01-01

    The survey includes degrees granted between July 1, 2001 and June 30, 2002. Enrollment information refers to the fall term 2002. Thirty-five academic programs were in the survey universe and all responded (100% response rate). One of the 35 programs reported that it was discontinued after the 2001-2002 academic year. Also, two programs were discontinued after the previous academic year (2000-2001) and were not included in 2002 survey

  6. Docritfab: A program to assess the radiological impact in accidental emissions of a nuclear fuel factory in real time; Docritfab: Un programa para evaluar en tiempo real el impacto radiologico en emisiones accidentales de una fabrica de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, J. G.; Ortiz, D.; Lopez, J.

    2014-07-01

    Docrit is a program developed for the manufacture of fuels of oxides of uranium Juzbado allowing an estimate in real time of the radiological impact in the case of accidental emissions from gaseous effluents (emissions of aerosols of UO{sub 2} and criticality accidents).

  7. Environmental impact assessment of nuclear desalination plant at KANUPP

    International Nuclear Information System (INIS)

    Sleem, M.

    2010-01-01

    A Nuclear Desalination Demonstration Plant (NDDP) of 1600 m/sup 3//d capacity is being installed at Karachi Nuclear Power Plant (KANUPP). A Nuclear Desalination Plant (NDP) can impact the aquatic environment mainly by subjecting the aquatic life to possible temperature increase and salinity changes in the vicinity of the cooling water and brine discharges. Any wastewater effluent, which will be discharged from the NDDP, may have some adverse effects on the marine life and general environment. In order to protect the environment and comply with the requirement of the Pakistan Environmental Protection Agency (PEPA) an Environmental Impact Assessment (EIA) for the discharged effluent from NDDP was carried out. In the present work baseline study was carried out for project location, climate, water resources, and ecology. Checklist has been prepared for identification of possible environmental impacts of the project and marked as insignificant, small, moderate or major impact. Appropriate mitigation measures have been recommended that can be incorporated into the intended program to minimize environmental impacts identified during the assessment. Specific conclusions of the study and recommendations have also been provided in this paper.

  8. Spanish program of advanced Nuclear Power Plants

    International Nuclear Information System (INIS)

    Marco, M.; Redon, R.

    1993-01-01

    The energy Spanish Plan is promoting some actions within the area of advanced reactors. Efforts are focussed onto the European Program of Advanced Reactors, the Program of Passive Plants (EPRI), European Fast Reactor Project and the APWR-1000 Program of INI. Electrical sector utilities and industrial partners supported by the Administration have organized an steering committee. The program of Passive Plants includes activities on Qualification, design and detailed engineering (Qualification project, SBWR project of G.E. and AP600 Project of Westinghouse. The european project on advanced plants has the following Spanish contribution: Analysis of alternative Dossier on European requisites (EUR) and Design of an European Reactor (EPR)

  9. Major accomplishments of America's nuclear rocket program (ROVER)

    International Nuclear Information System (INIS)

    Finseth, J.L.

    1991-01-01

    The United States embarked on a program to develop nuclear rocket engines in 1955. This program was known as project Rover. Initially nuclear rockets were considered as a potential backup for intercontinental ballistic missile propulsion but later proposed applications included both a lunar second stage as well as use in manned-Mars flights. Under the Rover program, 19 different reactors were built and tested during the period of 1959-1969. Additionally, several cold flow (non-fuelled) reactors were tested as well as a nuclear fuels test cell. The Rover program was terminated in 1973, due to budget constraints and an evolving political climate. The Rover program would have led to the development of a flight engine had the program continued through a logical continuation. The Rover program was responsible for a number of technological achievements. The successful operation of nuclear rocket engines on a system level represents the pinnacle of accomplishment. This paper will discuss the engine test program as well as several subsystems

  10. Safety program considerations for space nuclear reactor systems

    International Nuclear Information System (INIS)

    Cropp, L.O.

    1984-08-01

    This report discusses the necessity for in-depth safety program planning for space nuclear reactor systems. The objectives of the safety program and a proposed task structure is presented for meeting those objectives. A proposed working relationship between the design and independent safety groups is suggested. Examples of safety-related design philosophies are given

  11. US Department of Energy Nuclear Research and Development Program

    International Nuclear Information System (INIS)

    Griffith, J.D.

    1989-01-01

    The presentation includes a discussion of nuclear power in the United States with respect to public opinion, energy consumption, economics, technology, and safety. The focus of the presentation is the advanced light water reactor strategy, liquid metal cooled reactor program, the modular high temperature gas cooled reactor program, and DOE research and test reactor facilities utilization. The discussion includes programmatic status and planning

  12. Program strategy document for the Nuclear Materials Transportation Technology Center

    International Nuclear Information System (INIS)

    Jefferson, R.M.

    1979-07-01

    A multiyear program plan is presented which describes the program of the Nuclear Materials Transportation Technology Center (TIC) at Sandia Laboratories. The work element plans, along with their corresponding work breakdown structures, are presented for TTC activities in the areas of Technology and Information Center, Systems Development, Technology, and Institutional Issues for the years from 1979 to 1985

  13. Second Line of Defense Spares Program Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Henderson, Dale L.; Muller, George; Mercier, Theresa M.; Brigantic, Robert T.; Perkins, Casey J.; Cooley, Scott K.

    2012-11-20

    The Office of the Second Line of Defense (SLD) is part of the Department of Energy‘s (DOE) National Nuclear Security Administration (NNSA). The SLD Program accomplishes its critical global security mission by forming cooperative relationships with partner countries to install passive radiation detection systems that augment traditional inspection and law enforcement measures by alerting border officials to the presence of special nuclear or other radiological materials in cross-border traffic. An important tenet of the program is to work collaboratively with these countries to establish the necessary processes, procedures, infrastructure and conditions that will enable them to fully assume the financial and technical responsibilities for operating the equipment. As the number of operational deployments grows, the SLD Program faces an increasingly complex logistics process to promote the timely and efficient supply of spare parts.

  14. USNRC severe core damage assessment program

    Energy Technology Data Exchange (ETDEWEB)

    Hanson, J E [EG and G Idaho, Inc., Idaho Falls (USA); Johnston, W V; Kelber, C N [Nuclear Regulatory Commission, Washington, DC (USA)

    1981-01-01

    The accident at the Three Mile Island nuclear power station has significantly altered the perception of the importance of beyond-design-basis accidents in licensing and safety reviews of light-water reactors in the USA. Increased consideration will be given by the United States Nuclear Regulatory Commission to low-probability, high-risk core melt accidents in future licensing proceedings. To this end, the USNRC is mounting experimental and analytic methods development programs to provide the technical basis for future LWR design and licensing criteria related to class-9 accidents. The scope, objectives, and content of five major new programs addressing safety and licensing issues for beyond-design-basis accidents are reviewed and the rationale and logic for formulation of the programs is discussed.

  15. A frequent flyer program for nuclear mythology

    International Nuclear Information System (INIS)

    Robertson, J.A.L.

    1997-01-01

    The anti-nuclear literature contains many erroneous and misleading allegations, collectively constituting a mythology. These are repeated endlessly, however often they are refuted, and are quoted uncritically by the media. Many are collected here, together with my rebuttals. For an explanation of the use here of the term 'frequent flyers', read on... (author)

  16. Programmed system for nuclear power plant protection

    International Nuclear Information System (INIS)

    Jover, Pierre.

    1980-06-01

    The progress in the field of microprocessors and large scale integration circuits, have incited to introduce this new technologies into nuclear power plant protection system. The hardware and software design principles are briefly listed; then, a quad-redundant protection system for 1300 MWe PWR, developed in France is described [fr

  17. Dose assessments in nuclear power plant siting

    International Nuclear Information System (INIS)

    1988-03-01

    This document is mainly intended to provide information on dose estimations and assessments for the purpose of nuclear power plant (NPP) siting. It is not aimed at giving radiation protection guidance, criteria or procedures to be applied during the process of NPP siting nor even to provide recommendations on this subject matter. The document may however be of help for implementing some of the Nuclear Safety Standards (NUSS) documents on siting. The document was prepared before April 26, 1986, when a severe accident at the Unit 4 of Chernobyl NPP in the USSR had occurred. It should be emphasized that this document does not bridge the gap which exists in the NUSS programme as far as radiation protection guidance for the specific case of siting of NPP is concerned. The Agency will continue to work on this subject with the aim to prepare a safety series document on radiation protection requirements for NPP siting. This document could serve as a working document for this purpose. Refs, figs and tabs

  18. Organization and development of the Brazilian nuclear program

    International Nuclear Information System (INIS)

    Pinto, C. Syllus M.; Alves, R. Nazare; Lepecki, W.; Costa, H.M. da; Grinberg, M.; Grimberg, M.

    1977-01-01

    The paper presents the Brazilian Nuclear Energy Program: its development until the present stage, as well as the organizations and the distribution of responsibilities involved in its execution at the present time. The nuclear power policy is established at the Presidency of the Republic and is planned, executed and controlled through the Ministry of Mines and Energy. Directly subject to the Ministry is the Brazilian Nuclear Energy Commission (CNEN), which has regulatory, standardization, licensing, planning and surveillance functions. The nuclear fundamental research and manpower formation are also under CNEN responsibility. Also subject to the Ministry are two companies responsible for the execution of the Programme: the Centrais Eletricas Brasileiras S.A. - ELETROBRAS, which advises on the granting of permits for the construction and operation of nuclear power plants, and the Empresas Nucleares Brasileiras S.A. - NUCLEBRAS, which holds the monopoly of the nuclear fuel cycle in the country, designs and builds nuclear power plants and provides assistance to the electric utilities as well as promotes the participation of the Brazilian industry in the nuclear field. Besides describing the new distribution of regulatory functions given by law to the CNEN, this paper gives special emphasis to the large industrial complex which is in the process of being established with the setting-up of the many NUCLEBRAS subsidiaries in joint-venture with German firms in the nuclear field, as a consequence of the Industrial Cooperation between Brazil and the Federal Republic of Germany in the Field of the Peaceful Uses of Nuclear Energy signed between the two countries on June 27, 1975. The programs for these subsidiaries are presented and their participation in the Brazilian Nuclear Energy Programme is discussed. The technology transfer aspects of the industrial activities are also discussed, based on the Government's policy on the subject [es

  19. Impact evaluation of the nuclear training program of the Philippine Nuclear Research Institute

    International Nuclear Information System (INIS)

    Relunia, Estrella D.

    2000-01-01

    This study attempted to determine the factors that influenced the impact of the institute's training program in nuclear science and technology to the institution where the trainee works and to the trainee himself and this study involved engineers, scientists, teachers, medical doctor, technologist and professionals who have successfully completed the PNRI nuclear science and technology training courses

  20. Nuclear data needs within the U. S. Nuclear Criticality Safety program

    International Nuclear Information System (INIS)

    McKnight, R.D.; Dunn, M.E.; Little, R.C.; Felty, J.R.; McKamy, J.N.

    2008-01-01

    This paper will present the nuclear data needs currently identified within the US Nuclear Criticality Safety Program (NCSP). It will identify the priority data needs; it will describe the process of prioritizing those needs; and it will provide brief examples of recent data advances which have successfully addressed some of the priority criticality safety data needs.

  1. Nonproliferation of Nuclear Weapons and the Nuclear Program of the DPRK

    Directory of Open Access Journals (Sweden)

    - Park Sang Hoon

    2012-09-01

    Full Text Available The article analyzes the contemporary aspects of the nuclear weapon nonproliferation issue as exemplified by the international approaches to the DPRK nuclear weapons program, as well as the international community efforts to resolve it, in particular via the Six-Party Talks.

  2. Safety assessment for Generation IV nuclear systems

    International Nuclear Information System (INIS)

    Leahy, T.J.

    2012-01-01

    The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Recent RSWG work has focused on the definition of an integrated safety assessment methodology (ISAM) for evaluating the safety of Generation IV systems. ISAM is an integrated 'tool-kit' consisting of 5 analytical techniques that are available and matched to appropriate stages of Generation IV system concept development: 1) qualitative safety features review - QSR, 2) phenomena identification and ranking table - PIRT, 3) objective provision tree - OPT, 4) deterministic and phenomenological analyses - DPA, and 5) probabilistic safety analysis - PSA. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time

  3. Nuclear weapons modernization: Plans, programs, and issues for Congress

    Science.gov (United States)

    Woolf, Amy F.

    2017-11-01

    The United States is currently recapitalizing each delivery system in its "nuclear triad" and refurbishing many of the warheads carried by those systems. The plans for these modernization programs have raised a number of questions, both within Congress and among analysts in the nuclear weapons and arms control communities, about the costs associated with the programs and the need to recapitalize each leg of the triad at the same time. This paper covers four distinct issues. It begins with a brief review of the planned modernization programs, then addresses questions about why the United States is pursuing all of these modernization programs at this time. It then reviews the debate about how much these modernization programs are likely to cost in the next decade and considers possible changes that might reduce the cost. It concludes with some comments about congressional views on the modernization programs and prospects for continuing congressional support in the coming years.

  4. Interfaith Program for Public Awareness of Nuclear Issues

    International Nuclear Information System (INIS)

    1985-11-01

    Planning for the Interfaith Progam for Public Awareness of Nuclear Issues (IPPANI) began at the time of the Falkland Islands crisis. At that time representatives of certain of the faith groups in Toronto became concerned about the moral and ethical implications of Canada's export of fuel for a CANDU nuclear generating plant in Argentina. In order to accomplish its goals, the Planning Committee devised a program to provide unbiased input to the faith groups' deliberations on the ethical and moral issues involved in the nuclear debate. The development of a fair set of questions was aided by obtaining advice from the Canadian Nuclear Association (CNA), and from Energy Probe and others. The work of preparing a suitable agenda was completed early in 1984. Its result was embodied in appendices to the public document promoting the program, which is appended to this report. Invitations were sent to over six hundred individuals and organizations to appear before the panelists as 'presenters'. The resulting invitation list included spokespeople for both 'pro' and 'anti' nuclear positions on each of the three topics, as well as some who were found to be 'in the middle'. The three major topics were domestic nuclear issues, international trade and military uses of nuclear materials and technology. The next task of the Planning Committee is that of embodying the process and its results in an educational program for the supplementary and parochial school systems. The production of this book is the first step in that task

  5. Assessment of RELAP5/MOD2 against a natural circulation experiment in Nuclear Power Plant Borssele

    International Nuclear Information System (INIS)

    Winters, L.

    1993-07-01

    As part of the ICAP (International Code Assessment and Applications Program) agreement between ECN (Netherlands Energy Research Foundation) and USNRC, ECN has performed a number of assessment calculations for the thermohydraulic system analysis code RELAP5/MOD2/36.05. This document describes the assessment of this computer program versus a natural circulation experiment as conducted at the Borssele Nuclear Power Plant. The results of this comparison show that the code RELAP5/MOD2 predicts well the natural circulation behaviour of Nuclear Power Plant Borssele

  6. Vinca institute nuclear decommissioning program - Establishment and initialisation

    International Nuclear Information System (INIS)

    Pesic, M.; Subotic, K.; Ljubenov, V.; Sotic, O.

    2003-01-01

    Present conditions in The Vinca Institute of Nuclear Sciences related to the nuclear and radiation safety, as result of ambitious nuclear program in the former Yugoslavia and strong economic crisis during the previous decade, have to be improved as soon as possible. RA research reactor, which extended shutdown stage took almost 18 years, spent nuclear fuel from the RA operation in the water pools within the reactor building and inadequate storage facilities for the low and intermediate radioactive wastes at the Vinca site are the main safety problems that have to be solved. To solve the problems mentioned above, a new 'Vinca Nuclear Decommissioning (VIND) Program' is initiated in the Vinca Institute during 2002. The Program team is assembled from about 60 experts from the Institute and relevant organisations. The Program, known also as the G reen Vinca , will be supported, besides the government funding and expected donation from foreign institutions, by experts' help from the IAEA. The necessary equipment will be obtained through the technical assistance from the IAEA. Close co-operation of the team members with experts and relevant companies from nuclear developed countries is expected. (author)

  7. Program of radiological monitoring environmental a nuclear facility in latency

    International Nuclear Information System (INIS)

    Blas, A. de; Riego, A.; Batalla, E.; Tapia, C.; Garcia, R.; Sanchez, J.; Toral, J.

    2013-01-01

    This paper presents the Radiological Environmental Monitoring program of the Vandellos I nuclear power plant in the latency period. This facility was dismantled to level 2, as defined by the International Atomic Energy Agency. The program is an adaptation of the implanted one during the dismantling, taking into account the isotopes that may be present, as well as the main transfer routes. Along with the description of the program the results obtained in the latent period from 2005 until 2012 are presented.

  8. Application of Nuclear Application Programs to APR1400 Simulator

    International Nuclear Information System (INIS)

    Hwang, Do Hyun; Lee, Myeong Soo; Hong, Jin Hyuk

    2012-01-01

    Advanced Power Reactor 1400MWe (APR1400) simulator has been developed and installed at Kori Training Center for operators of ShinKori no.3, 4 nuclear power plant by Korea Hydro and Nuclear Power,s Central Research Institute (KHNP CRI). NAPS (Nuclear Application Programs) is a computerbased system which provides operators with past and real-time information for monitoring and controlling NSSS (Nuclear Steam Supply System), BOP (Balance Of Plant) and Electric system. NAPS consists of several programs such as COLSS (Core Operating Limit Supervisory System), SPADES+ (Safety Parameter Display and Evaluation System), CEA (Control Element Assembly) Application Program, and so on. Each program makes calculations based on its own algorithm and provides information available for operation. In order to use NAPS programs with a simulator even though they are being used in a real plant, they should be modified to add several simulation functions such as reset, snap, run/freeze and backtrack required by ANSI/ANS-3.5 to the original NAPS functionality. On top of that, interfacing programs should be developed for the data communication between respective NAPS programs and simulator sever. The purpose of this paper is to provide the overall architecture of the communication system between NAPS and simulator model, and to describe the method to apply NAPS to APR1400 simulator

  9. Framework of nuclear safety and safety assessment

    International Nuclear Information System (INIS)

    Furuta, Kazuo

    2007-01-01

    Since enormous energy is released by nuclear chain reaction mainly as a form of radiation, a great potential risk accompanies utilization of nuclear energy. Safety has been continuously a critical issue therefore from the very beginning of its development. Though the framework of nuclear safety that has been established at an early developmental stage of nuclear engineering is still valid, more comprehensive approaches are required having experienced several events such as Three Mile Island, Chernobyl, and JCO. This article gives a brief view of the most basic principles how nuclear safety is achieved, which were introduced and sophisticated in nuclear engineering but applicable also to other engineering domains in general. (author)

  10. Status of nuclear power programs in South America

    International Nuclear Information System (INIS)

    Spitalnik, J.

    2010-10-01

    Analysis of nuclear power plants construction in four South American countries - Argentina, Brazil, Chile and Uruguay - is made based on programs set up by government specialized agencies. In Argentina, in a time-span up to 2023, the nuclear power program considers a five-fold increase of the current installed capacity reaching some 5,000 M We. The Brazilian reference scenario will install additional 4,000 M We, up to 2030, to reach a total installed capacity of about 6,000 M We. Other scenarios could bring this total to some 8,000 - 10,000 M We. Chile and Uruguay have started strategic studies to place the nuclear power option in the future energy matrix of the country. The government of Chile set up, in 2007, a Task Group to determine whether nuclear power could be considered a viable option. This Group concluded that nuclear power is a mature, safe competitive, and low carbon emitter technology that could be considered a viable option. A Nuclear Advisory Group was created who made studies to install a nuclear power plant in the 2016-2021 time-span. In December 2008, the Uruguayan Government created a high level Working Group to establish the feasibility conditions for Nuclear Power Generation in the country. (Author)

  11. Assessment of control rooms of nuclear power plants

    International Nuclear Information System (INIS)

    Norros, L.; Ranta, J.; Wahlstroem, B.

    1983-05-01

    To identify and correct the lacks in control rooms of operating power plants and plants under construction an extensive program has been started in the USA. In Finland as in other countries using nuclear power, the development in the USA particularly with regard to the requirements imposed on nuclear power plants is carefully followed. The changes in these requirements are sooner or later also reflected in the guidelines given by the Finnish authorities. It is therefore important to be able to form a notion of how the new requirements apply to Finnish conditions. Especially it is important to review the latest assessment guidelines for control room implementation (NUREG-0700). Thus we can avoid possible over hasty conclusions. The aim of the analysis of the method and experiments presented in NUREG 0700 report was to create a basis for assessment of the suitability of the method for Finnish control room implementation. The task group has made a general methodical analysis of the method, and partly tried it in assessment of the TVO2 control room. It is obvious that direct conclusions from the American situation are misleading. It can be considered unfeasible to follow the American requirements as such, because they can lead to unwanted results. If the review is limited to control room details, the NRC program (checklist) can be considered successful. It can also be used during planning to observation of small discrepancies. However, we can question the applicability of some requirements. It is, though, more essential that the control room entity has neither in this nor in several other programs been reached or standardized. In spite of the difficulties we should try to reach this most important goal. (author)

  12. Next Generation Nuclear Plant Methods Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-12-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  13. Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

    Energy Technology Data Exchange (ETDEWEB)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-09-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  14. Program nuclear safety research: report 2000

    International Nuclear Information System (INIS)

    Muehl, B.

    2001-09-01

    The reactor safety R and D work of forschungszentrum karlsruhe (FZK) had been part of the nuclear safety research project (PSF) since 1990. In 2000, a new organisational structure was introduced and the Nuclear Safety Research Project was transferred into the nuclear safety research programme (NUKLEAR). In addition to the three traditional main topics - Light Water Reactor safety, Innovative systems, Studies related to the transmutation of actinides -, the new Programme NUKLEAR also covers Safety research related to final waste storage and Immobilisation of HAW. These new topics, however, will only be dealt with in the next annual report. Some tasks related to the traditional topics have been concluded and do no longer appear in the annual report; other tasks are new and are described for the first time. Numerous institutes of the research centre contribute to the work programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2001. (orig.)

  15. Nuclear energy and Indian society: Public engagement, risk assessment and legal frameworks - Summary of the proceedings

    International Nuclear Information System (INIS)

    Kini, Els Reynaers; Dipankar Bandyopadhyay, I.; Kanwar, Bhanudey

    2014-01-01

    The Nuclear Law Association (NLA) has organised its 3. Annual Meeting with the specific aim to deliberate on public engagement, consultation and acceptance of nuclear energy projects. The meeting further aimed to seek a better understanding of the necessary legal framework for a safe nuclear energy program in India. The themes covered by the conference were: Public engagement, consultation and acceptance; Nuclear energy safety and public discourse; Case studies from India on public engagement; Land acquisition and EIA in India; Safety regulations and its enforcement; Nuclear regulatory institutions; Siting, consent and project execution; Nuclear liability and compensation. The meeting was organised in 3 sessions dealing with: 1 - Public engagement, consultation and acceptance of nuclear projects: - Sociological context of public engagement and consultation, - Current state of affairs and new approaches to public consultation, - Case studies from new green field nuclear project sites, - Public opinion and acceptability for nuclear energy projects, - Role of State, NGOs and Public; 2 - Vales, Attitudes and Acceptability - Lessons from other countries: - Fukushima and nuclear energy choices, - Social dimensions of nuclear power, - Public engagement, acceptance and regulatory process, - Management of HLW. 3 - Legal Framework for a Safe and Secure Nuclear Energy Program: - Safety regulations and its enforcement, - Nuclear regulatory institutions, - Siting, consent and project execution, - Environmental impact assessments and plans, - Nuclear liability and compensation. Several of the papers presented will be published in the Journal of Risk Research in early 2015 as part of the Special Issue on Nuclear Energy and Indian Society: Public Engagement, Risk Assessment and Legal Frameworks. This article is the summary of the proceedings

  16. The Maryland nuclear science baccalaureate degree program: The utility perspective

    International Nuclear Information System (INIS)

    Mueller, J.R.

    1989-01-01

    In the early 1980s, Wisconsin Public Service Corporation (WPSC) made a firm commitment to pursue development and subsequent delivery of an appropriate, academically accredited program leading to a baccalaureate degree in nuclear science for its nuclear operations personnel. Recognizing the formidable tasks to be accomplished, WPSC worked closely with the University of Maryland University College (UMUC) in curriculum definition, specific courseware development for delivery by computer-aided instruction, individual student evaluation, and overall program implementation. Instruction began on our nuclear plant site in the fall of 1984. The university anticipates conferring the first degrees from this program at WPSC in the fall of 1989. There are several notable results that WPSC achieved from this degree program. First and most importantly, an increase in the level of education of our employees. It should be stated that this program has been well received by WPSC operator personnel. These employees, now armed with plant experience, a formal degree in nuclear science, and professional education in management are real candidates for advancement in our nuclear organization

  17. Nuclear criticality safety program at the Fuel Cycle Facility

    International Nuclear Information System (INIS)

    Lell, R.M.; Fujita, E.K.; Tracy, D.B.; Klann, R.T.; Imel, G.R.; Benedict, R.W.; Rigg, R.H.

    1994-01-01

    The Fuel Cycle Facility (FCF) is designed to demonstrate the feasibility of a novel commercial-scale remote pyrometallurgical process for metallic fuels from liquid metal-cooled reactors and to show closure of the Integral Fast Reactor (IFR) fuel cycle. Requirements for nuclear criticality safety impose the most restrictive of the various constraints on the operation of FCF. The upper limits on batch sizes and other important process parameters are determined principally by criticality safety considerations. To maintain an efficient operation within appropriate safety limits, it is necessary to formulate a nuclear criticality safety program that integrates equipment design, process development, process modeling, conduct of operations, a measurement program, adequate material control procedures, and nuclear criticality analysis. The nuclear criticality safety program for FCF reflects this integration, ensuring that the facility can be operated efficiently without compromising safety. The experience gained from the conduct of this program in the Fuel cycle Facility will be used to design and safely operate IFR facilities on a commercial scale. The key features of the nuclear criticality safety program are described. The relationship of these features to normal facility operation is also described

  18. Nuclear plant aging research program activities

    International Nuclear Information System (INIS)

    Eissenberg, D.M.

    1986-01-01

    The objective of this program is to provide recommendations for use by NRC regarding the availability and capability of diagnostic methods for assuring the operational readiness of NPP safety systems and components

  19. Quality assurance in the nuclear test program

    International Nuclear Information System (INIS)

    Shearer, J.N.

    1979-01-01

    In February 1979 Test Program laid the ground work for a new quality assurance structure. The new approach was based on the findings and recommendations of the Ad Hoc QA Program Review panel, which are summarized in this report. The new structure places the responsibility for quality assurance in the hands of the line organizations, both in the programmatic and functional elements of the LLL matrix

  20. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Summary description

    International Nuclear Information System (INIS)

    Gertman, D.I.; Gilmore, W.E.; Galyean, W.J.; Groh, M.R.; Gentillon, C.D.; Gilbert, B.G.; Reece, W.J.

    1990-05-01

    The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automate data base management system for storing and processing human error probability and hardware component failure rate data. The NUCLARR system software resides on an IBM (or compatible) personal microcomputer. NUCLARR can be accessed by the end user to furnish data suitable for input in human and/or hardware reliability analysis to support a variety of risk assessment activities. The NUCLARR system is documented in a five-volume series of reports. This document Volume 1, of this series is the Summary Description, which presents an overview of the data management system, including a description of data collection, data qualification, data structure, and taxonomies. Programming activities, procedures for processing data, a user's guide, and hard copy data manual are presented in Volumes 2 through 5, NUREG/CR-4639

  1. NP2010: An Assessment and Outlook for Nuclear Physics

    International Nuclear Information System (INIS)

    Lancaster, James

    2014-01-01

    This grant provided partial support for the National Research Council's (NRC) decadal survey of nuclear physics. This is part of NRC@s larger effort to assess and discuss the outlook for different fields in physics and astronomy, Physics 2010, which takes place approximately every ten years. A report has been prepared as a result of the study that is intended to inform those who are interested about the current status of research in this area and to help guide future developments of the field. A pdf version of the report is available for download, for free, at http://www.nap.edu/catalog.php?record_id=13438. Among the principal conclusions reached in the report are that the nuclear physics program in the United States has been especially well managed, principally through a recurring long-range planning process conducted by the community, and that current opportunities developed pursuant to that planning process should be exploited. In the section entitled @Building the Foundation for the Future,@ the report notes that attention needs to be paid to certain elements that are essential to the continued vitality of the field. These include ensuring that education and research at universities remain a focus for funding and that a plan be developed to ensure that forefront-computing resources, including exascale capabilities when developed, be made available to nuclear science researchers. The report also notes that nimbleness is essential for the United States to remain competitive in a rapidly expanding international nuclear physics arena and that streamlined and flexible procedures should be developed for initiating and managing smaller-scale nuclear science projects.

  2. Technology assessment Jordan Nuclear Power Plant Project

    International Nuclear Information System (INIS)

    2010-01-01

    Preliminary regional analysis was carried out for identification of potential sites for NPP, followed by screening of these sites and selecting candidate sites. Aqaba sites are proposed, where it can use the sea water for cooling: i.Site 1; at the sea where it can use the sea water for direct cooling. ii.Site 2; 10 km to the east of Gulf of Aqaba shoreline at the Saudi Arabia borders. iii.Site 3, 4 km to the east of Gulf of Aqaba shoreline. Only the granitic basement in the east of the 6 km²site should be considered as a potential site for a NPP. Preliminary probabilistic seismic hazard assessment gives: Operating-Basis Earthquake-OBE (475 years return period) found to be in the range of 0.163-0.182 g; Safe Shutdown Earthquake-SSE (10,000 years return period) found to be in the range of 0.333-0.502g. The process include also setting up of nuclear company and other organizational matters. Regulations in development are: Site approval; Construction permitting; Overall licensing; Safety (design, construction, training, operations, QA); Emergency planning; Decommissioning; Spent fuel and RW management. JAEC's technology assessment strategy and evaluation methodology are presented

  3. Possible research program on a large scale nuclear pressure vessel

    International Nuclear Information System (INIS)

    1983-01-01

    The nuclear pressure vessel structural integrity is actually one of the main items in the nuclear plants safety field. An international study group aimed at investigating the feasibility of a ''possible research program'' on a scale 1:1 LWR pressure vessel. This report presents the study group's work. The different research programs carried out or being carried out in various countries of the European Community are presented (phase I of the study). The main characteristics of the vessel considered for the program and an evaluation of activities required for making them available are listed. Research topic priorities from the different interested countries are summarized in tables (phase 2); a critical review by the study group of the topic is presented. Then, proposals for possible experimental programs and combination of these programs are presented, only as examples of possible useful research activities. The documents pertaining to the results of phase I inquiry performed by the study group are reported in the appendix

  4. Sister Lab Program Prospective Partner Nuclear Profile: Malaysia

    International Nuclear Information System (INIS)

    Bissani, M; Tyson, S

    2006-01-01

    The Malaysian Deputy Prime Minister Tun Dr Ismail Abdul Rahman suggested in the early 1970s that Malaysia should have a role in the development of nuclear science and technology for peaceful purposes. Accordingly, the Center for the Application of Nuclear Energy (CRANE) was established, with a focus on the development of a scientific and technical pool critical to a national nuclear power program. The Malaysian Cabinet next established the Tun Ismail Atomic Research Center (TIARC) under the Ministry of Science, Technology and the Environment on 19 September 1972, at a site in Bangi, about 35 km south of Kuala Lampur. On 28 June 1982, the PUSPATI reactor, a 1-MW TRIGA MK-II research reactor, first reached criticality. On 10 August 1994, TIARC was officially renamed as the Malaysian Institute for Nuclear Technology Research (MINT). In addition to radioisotope production and neutron radiography conducted at the PUSPATI research reactor, MINT also supports numerous programs employing nuclear technology for medicine, agriculture and industry, and has been involved in both bilateral and multilateral technical cooperation to extend its capabilities. As an energy exporting country, Malaysia has felt little incentive to develop a nuclear energy program, and high level opposition within the government discouraged it further. A recent statement by Malaysia's Science, Technology and Innovation Minister supported this view, indicating that only a near-catastrophic jump in world oil prices might change the government's view. However, the rate at which Malaysia is using its natural gas and oil reserves is expected to force it to reassess the role of nuclear energy in the near future. In addition, the government does intend to construct a radioactive waste repository to dispose of naturally occurring radioactive materials (extracted during tin mining, in particular). Also, Malaysia's growing economy could encourage expansion in Malaysia's existing nuclear-applications programs

  5. Nuclear Waste Treatment Program: Annual report for FY 1986

    International Nuclear Information System (INIS)

    Burkholder, H.C.; Brouns, R.A.; Powell, J.A.

    1987-09-01

    To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs

  6. Nuclear Waste Treatment Program: Annual report for FY 1986

    Energy Technology Data Exchange (ETDEWEB)

    Burkholder, H.C.; Brouns, R.A. (comps.); Powell, J.A. (ed.)

    1987-09-01

    To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs.

  7. Safety research programs sponsored by Office of Nuclear Regulatory Research

    International Nuclear Information System (INIS)

    Weiss, A.J.; Azarm, A.; Baum, J.W.

    1989-07-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through September 30, 1988

  8. Assessment of elementary school safety restraint programs.

    Science.gov (United States)

    1985-06-01

    The purpose of this research was to identify elementary school (K-6) safety belt : education programs in use in the United States, to review their development, and : to make administrative and impact assessments of their use in selected States. : Six...

  9. Colon Cancer Risk Assessment - Gauss Program

    Science.gov (United States)

    An executable file (in GAUSS) that projects absolute colon cancer risk (with confidence intervals) according to NCI’s Colorectal Cancer Risk Assessment Tool (CCRAT) algorithm. GAUSS is not needed to run the program.

  10. Iraq's shop-till-you-drop nuclear program

    International Nuclear Information System (INIS)

    Albright, D.; Hibbs, M.

    1992-01-01

    In a series of articles that began in March 1991, the authors have tried to separate fact from fiction about Iraq's ability to build nuclear weapons and to produce material to fuel them. After exposing Iraq's efforts to enrich uranium and design an atomic bomb, UN and IAEA experts zeroed in on how Iraq put its program together. The basic answer is that along with determination and persistence, Iraq had a great deal of foreign help. Iraq's 'Petrochemical Three,' the secret nuclear program conducted under the authority of its Atomic Energy Commission with links to the Defense Ministry and the Ministry of Industry and Military Industrialization, received massive infusions of money and resources. Like the Manhattan Project that built the first atomic bombs in the United States, Iraq's program simultaneously pursued a number of different technical avenues to the bomb. Not knowing which efforts would succeed, Iraq poured billions of dollars into its multifaceted quest. Providing for these programs required the establishment of elaborate procurement networks in Europe, North America, and Asia. Like the technical quest, the procurement effort was carried out on many fronts at once. Diplomacy and secrecy were required, because few companies would knowingly supply a nuclear weapons program, or even a secret nuclear program that was ostensibly for civil purposes. Iraq showed great ingenuity in hiding its purchases behind such innocuous pursuits as automobile manufacturing, dairy production, and oil refining

  11. Kinematical program package for nuclear reaction

    International Nuclear Information System (INIS)

    Dai Nengxiong; Xie Ying

    1988-01-01

    A FORTRAN package is designed to provide users as many conveniences as possible. Besides adopting man-machine interaction mode and setting nuclide mass file, there are still some other features which are, for examples, the functions of offering the initial values for some transcendental equations and evaluating all the kinematic variables in nuclear reactions at low energies of the form of T (p,1)2, T (p,12)3 and T (p,12)34. All these make the users much easier to use the package

  12. Developing engineering capabilities as a support to a nuclear program

    International Nuclear Information System (INIS)

    Rodriguez, A.G.

    1986-04-01

    The performance of a nuclear program needs a quite substantial and diversified volume of technological resources. Its integrated management is one of the basic aspects to be settled. In this regard, the creation of strong engineering organizations with the ability to develop management of the project technical activities as a whole has had success in various countries. These organizations should be provided with suitable means to rapidly assimilate the technology and should serve as a channel and support to local industry in general. The development of a nuclear program also requires the collaboration of other institutions, such as universities and research and development centers. In this sense, engineer and technician training necessities are important both in number and technological qualification, as is the availability of capacities in such different areas as simulation and advanced calculation, geology and soil mechanics, materials, fabrication processes, test laboratories, etc. The volume of technological activities to be developed in relation to a stable, although not necessarily large, nuclear program justifies in itself the assigning of important resources to all the above mentioned activities. However, it should be noted that it has been proved that the nuclear industry is completely pervious as regards other fields of activity. In fact, the more stringent quality requirements are quickly transmitted to other industrial processes, and the engineers trained in this area undergo a far from contemptible turnover towards non-nuclear activities. The basic research area in the nuclear field is not in itself a requirement that has to be in parallel with the development of a nuclear program. However, on medium and long-term bases, it may be interesting for a well balanced commercial program that research activities be established realistically and sensibly, even though short-term practical applications are not necessarily derived from this

  13. Programming for a nuclear reactor instrument simulator

    International Nuclear Information System (INIS)

    Cohn, C.E.

    1989-01-01

    A new computerized control system for a transient test reactor incorporates a simulator for pre-operational testing of control programs. The part of the simulator pertinent to the discussion here consists of two microprocessors. An 8086/8087 reactor simulator calculates simulated reactor power by solving the reactor kinetics equations. An 8086 instrument simulator takes the most recent power value developed by the reactor simulator and simulates the appropriate reading on each of the eleven reactor instruments. Since the system is required to run on a one millisecond cycle, careful programming was required to take care of all eleven instruments in that short time. This note describes the special programming techniques used to attain the needed performance

  14. Assessing a GTA professional development program

    OpenAIRE

    Alicea-Muñoz, Emily; Masip, Joan Espar; Sullivan, Carol Subiño; Schatz, Michael F.

    2018-01-01

    For the last four years, the School of Physics at Georgia Tech have been preparing new Graduate Teaching Assistants (GTAs) through a program that integrates pedagogy, physics content, and professional development strategies. Here we discuss various assessments we have used to evaluate the program, among them surveys, GTA self-reporting, and end-of-semester student evaluations. Our results indicate that GTAs who participate in the program find its practical activities useful, feel better prepa...

  15. Human factors engineering plan for reviewing nuclear plant modernization programs

    International Nuclear Information System (INIS)

    O'Hara, John; Higgins, James

    2004-12-01

    The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation

  16. Nuclear Criticality Safety Organization qualification program. Revision 4

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1997-01-01

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSO technical and managerial qualification as required by the Y-12 Training Implementation Matrix (TIM). It is implemented through a combination of LMES plant-wide training courses and professional nuclear criticality safety training provided within the organization. This Qualification Program is applicable to technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who perform the NCS tasks or serve NCS-related positions as defined in sections 5 and 6 of this program

  17. The American Nuclear Society's international student exchange program

    International Nuclear Information System (INIS)

    Bornstein, I.

    1988-01-01

    The American Nuclear Society's (ANS's) International Student Exchange Program sponsors bilateral exchanges of students form graduate schools in American universities with students from graduate schools in France, the Federal Republic of Germany (FRG), and Japan. The program, now in its 12th year, was initiated in response to an inquiry to Argonne National Laboratory (ANL) from the director of the Centre d'Etudes Nucleaires de Saclay proposing to send French nuclear engineering students to the United States for summer jobs. The laboratory was asked to accept two students to work on some nuclear technology activity and ANS was invited to send American students to France on an exchange basis. To date, 200 students have taken part in the program. It has been a maturing and enriching experience for them, and many strong and enduring friendships have been fostered among the participants, many of whom will become future leaders in their countries

  18. Human factors engineering plan for reviewing nuclear plant modernization programs

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, John; Higgins, James [Brookhaven National Laboratory, Upton, NY (United States)

    2004-12-01

    The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation.

  19. Nuclear power programs in the world's developed and developing countries

    International Nuclear Information System (INIS)

    Czibolya, L.

    1983-01-01

    The significance of nuclear power in the world's energy balance related to fossile energy sources is discussed. The general trend of declination of the national power programs could be observed from the seventies as a result of the oil crisis and the economic recession. The main features of the national energy programs including the ratio of the different energy sources in the power supply, the distribution of power production among the different types of nuclear reactors, the time schedules of the national nuclear power programs are reviewed through the examples of some developed and developing countries: USA, FRG, Canada, Japan, France, Sweden, the Soviet Union, Czechoslovakia, Bulgaria, Hungary, Romania, India, and the Republic of Korea. (V.N.)

  20. Nuclear criticality safety specialist training and qualification programs

    International Nuclear Information System (INIS)

    Hopper, C.M.

    1993-01-01

    Since the beginning of the Nuclear Criticality Safety Division of the American Nuclear Society (ANS) in 1967, the nuclear criticality safety (NCS) community has sought to provide an exchange of information at a national level to facilitate the education and development of NCS specialists. In addition, individual criticality safety organizations within government contractor and licensed commercial nonreactor facilities have developed training and qualification programs for their NCS specialists. However, there has been substantial variability in the content and quality of these program requirements and personnel qualifications, at least as measured within the government contractor community. The purpose of this paper is to provide a brief, general history of staff training and to describe the current direction and focus of US DOE guidance for the content of training and qualification programs designed to develop NCS specialists

  1. UTAP, U Tailings Assessment Program

    International Nuclear Information System (INIS)

    Holmes, Ron

    1998-01-01

    1 - Description of program or function: UTAP carries out probabilistic analyses of the behaviour and environmental effects of uranium mill tailings, following close-out of milling operations. The models have been designed to allow predictions to be made for distances up to 50 kilometers in all directions from the tailings area. The models include features which include the ability to incorporate different receptors and site characteristics and to deal with input parameters which vary with time. 2 - Method of solution: UTAP is composed of a number of modules. These may be classified as either component or control modules. Component modules (or models) are the programs directly concerned with the simulation of a uranium tailings physical system; that is the computer implementation of the mathematical models representing the uranium tailings pile and surrounding environment. Control modules provide the infrastructure for probabilistic analysis using the component modules. These functions include probabilistic sampling of input parameters such as constant, normal, log-normal, uniform, log-uniform, triangular, Weibull, Beta, arbitrary and correlated. The sampling method used is straight Monte Carlo. The radionuclides modelled are: natural uranium, total thorium, radium-226, radon-222 and lead-210. The pH of the reference uranium tailings site and a chained river-lake system are also modelled. For the afore- mentioned radionuclides the following pathways of dose to the receptors modelled: water consumption, fish consumption, radon inhalation, dust inhalation, vegetable consumption, animal produce consumption and ground-shine. 3 - Restrictions on the complexity of the problem: The maximum number of steps through time allowed is 300

  2. Assessing an Academic Library Professional Development Program

    Science.gov (United States)

    Harker, Karen R.; O'Toole, Erin; Sassen, Catherine

    2018-01-01

    Professional development programs have been established in many academic libraries to support the research and scholarly activities of librarians. Continuous assessment can contribute to the sustainability and effectiveness of these programs. This study describes how measures of need, participation, satisfaction, and impact were employed to assess…

  3. Argonne program to assess superconducting stability

    International Nuclear Information System (INIS)

    Wang, S.T.; Turner, L.R.; Huang, Y.C.; Dawson, J.W.; Harrang, J.; Hilal, M.A.; Lieberg, M.; Gonczy, J.D.; Kim, S.H.

    1978-01-01

    To assess superconductor stability, a complete program is developed to obtain basic information on the effects of local mechanical perturbations on the cryostatic stability. An analytical model for computing the transient recovery following the mechanical perturbation is developed. A test program is undertaken to develop data needed to verify the conclusions reached through the analytical studies

  4. BNFL nuclear decommissioning liabilities management program

    International Nuclear Information System (INIS)

    Colquhoun, A.P.

    1995-01-01

    The objective of this paper is to describe BNFL's policy and strategy for decommissioning and also to summarize the overall scope of nuclear liabilities in the wider field of waste retrieval and storage, as well as the dismantling and demolition aspects of decommissioning. BNFL's recently established organisational arrangements for discharging all types of these liabilities are explained, together with a review of practical progress in dealing with them. Organisational changes in recent years have amalgamated decommissioning work with operations covering waste storage and retrieval operations. A strategy of minimising residual activity in shutdown plants is pursued, followed by dismantling and demolition on appropriate time scales to minimise risk and cost. Since April 1995, a new BNFL subsidiary, Nuclear Liabilities Management Company Limited has taken responsibility for discharge of BNFL's Waste Retrieval and Decommissioning liabilities on all BNFL sites. NLM has the objectives of optimal and lowest cost management of liabilities and much clearer segregation of physical operations from project specification and planning. The Ministry of Defense (MoD) policy, strategy, work programmes and progress for the Atomic Weapons Establishment (AWE) are also outlined. MoD/AEA has established an equivalent strategy for dealing with its liabilities. (J.S.). 5 refs., 2 figs., 4 appends

  5. A package for environmental impact assessment of nuclear installations (NGLAR)

    International Nuclear Information System (INIS)

    Yang Yin; Chen Xiaoqiu; Ding Jinhou; Zhao Hui; Xi Xiaojun; Li Hongsheng

    1996-09-01

    The main contents, designing strategies and properties of the microcomputer-based software package NGLAR are described for environmental impact assessment of nuclear installations. The package consists of the following components: NGAS and NACC, the codes for routine and accidental airborne releases respectively; NLIQ, the code for both routine and accidental liquid releases; and NRED, environmental database system of nuclear installations. NGAS and NACC are used for evaluating atmosphere dispersion and doses to public of radioactive materials released from nuclear facilities, giving the concentrations around the facilities of radionuclides in air, on ground surface, and in varieties of animal foods and farm produces, and further estimating collective doses and doses to critical group around the facilities. NLIQ is suitable for liquid effluence released to non-tide rivers, and is modelled to calculate firstly the concentration of radionuclides concerned in the polluted rivers, and then to estimate the resulting doses to public. Under routine releases, the doses obtained from NGAS and NLIQ can be appropriately categorized and summed up together. NRED can be run independently, also used to provide some input data for above programs and save data permanently for them. Having both English and Chinese versions, the package, which was fabricated of multiple functions can be run on IBM 386 or higher and its compatible microcomputers. (3 figs., 1 tabs)

  6. The U.S. Nuclear Regulatory Commission seismic safety research program

    International Nuclear Information System (INIS)

    Kenneally, R.M.; Guzy, D.J.; Murphy, A.J.

    1988-01-01

    The seismic safety research program sponsored by the U.S. Nuclear Regulatory Commission is directed toward improving the evaluation of potential earthquake effects on nuclear power plant operations. The research has been divided into three major program areas: earth sciences, seismic design margins, and fragilities and response. A major thrust of this research is to assess plant behavior for seismic events more severe and less probable than those considered in design. However, there is also research aimed at improving the evaluation of earthquake input and plant response at plant design levels

  7. Operating experience review for nuclear power plants in the Systematic Evaluation Program

    International Nuclear Information System (INIS)

    Mays, G.T.; Harrington, K.H.

    1982-01-01

    The Systematic Evaluation Program Branch (SEPB) of the Nuclear Regulatory Commission (NRC) is conducting the Systematic Evaluation Program (SEP) whose purpose is to determine the safety margins of the design and operation of the eleven oldest operating commercial nuclear power plants in the United States. This paper describes the methodology and results of the operational experience review portion of the SEP evaluation. SEPB will combine the results from these operational reviews with other safety topic evaluations to perform an integrated assessment of the SEP plants

  8. Research on seal control systems for international nuclear safeguard and the vulnerability assessment on the seals

    International Nuclear Information System (INIS)

    Zhang Hongjian; Liu Tianshu; Cao Fangfang; Xu Chunyan

    2014-01-01

    Safeguard seals, also called Tamper-indicating devices (TIDs), are widely used to detect tampering or unauthorized entry in the international safeguard and security systems, Seal control systems consist of seal implementing plan, seal development and the vulnerability assessment on tbe seals, effective implementing procedures and methods of the seals. The vulnerability assessment contents of safeguard seals, thermo-shrinked film seals being as an example, and seals control systems in the implementation program are researched. The seal control systems discuss task assignment, seals management flow and seals program data flow to promote applying effectively seals. The vulnerability assessment program of seals studies assurance level to some different tampering techniques and measures. The researches must promote utilizing seals effectively for nuclear security, non-proliferation of nuclear weapons, radioactive waste management, and the nuclear material accounting and control. (authors)

  9. Criteria for safety-related nuclear plant operator actions: a preliminary assessment of available data

    International Nuclear Information System (INIS)

    Haas, P.M.; Bott, T.F.

    1980-01-01

    In the US, an effort has been underway for a number of years to develop a design standard to define when required manual operator action can be accepted as part of a nuclear plant design basis. Insufficient data are available to provide quantitative guidelines for the standard. To provide the necessary data base to support such standards and the necessary quantitative assessment of operator reliability, the US Nuclear Regulatory Commission is sponsoring a study at Oak National Laboratory to develop the data base. A preliminary assessment completed in April, 1979 concluded that sufficient data from US operating experience did not exist to provide an adequate data base. A program of research using full-scope nuclear plant simulators and results that are correlated to field data was suggested. That program was recently initiated. The approach, results and conclusions of the preliminary assessment are reviewed and the planned research program of simulator studies is summarised. (author)

  10. Nuclear Computerized Library for Assessing Reactor Risk (NUCLARR)

    International Nuclear Information System (INIS)

    Gilmore, W.E.; Blackman, H.S.; Ryan, T.G.

    1986-01-01

    The Nuclear Computerized Library for Assessing Reactor Risk (NUCLARR) program is a multiyear effort sponsored by the NRC and is being conducted at the Idaho National Engineering Laboratory (INEL). The goal of this program is to establish and operate computerized data base management tools for the human reliability data bank specification developed by Comer and Donovan. The NRC and the risk analysis community recognized that implementing a fully functional library would not be feasible, or practical, without the aid of computerized tools for management and manipulation of its data sources. The end users of the NUCLARR can be classified into three categories according to specific needs. The first category is those users interested in reviewing individual data sources for a given situation. The second category of users selects multiple data sources for a specific case, summarizing the information, and performing comparative studies. The last category of users interfaces the NUCLARR with other programming applications, such as other data banks, and simulation models of risk assessment. Project status is provided in the paper

  11. Development of Intelligent Database Program for PSI/ISI Data Management of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Park, Un Su; Park, Ik Keun; Um, Byong Guk; Park, Yun Won; Kang, Suk Chul

    1998-01-01

    For an effective and efficient management of large amounts of preservice/inservice inspection(PSI/ISI) data in nuclear power plants, an intelligent Windows 95-based data management program was developed. This program enables the prompt extraction of previously conducted PSI/ISI conditions and results so that the time-consuming data management, painstaking data processing and analysis in the past are avoided. The program extracts, and the associated remedies. Furthermore, additional inspection data and comments can be easily added or deleted for subsequent PSI/ISI operation. Although the initial version of the program was applied to Kori nuclear power plant, this program can be equally applied to other nuclear power plant. And also this program can be used to offer the fundamental data for application of evaluation data related to fracture mechanics analysis(FMA), probabilistic reliability assessment(PRA) of PSI/ISI results, performance demonstration initiative(PDI) and risk-informed ISI based on probability of detection(POD) information of ultrasonic examination. Besides, the program can be further developed as a unique PSI/ISI data management expert system that can be apart of PSI/ISI data management expert system that can be a part of PSI/ISI Total Support System(TSS) for Korean nuclear power plants

  12. Transportation System Risk Assessment on DOE Defense Program shipments

    International Nuclear Information System (INIS)

    Brumburgh, G.P.; Kimura, C.Y.; Alesso, H.P.; Prassinos, P.G.

    1992-01-01

    Substantial effort has been expended concerning the level of safety provided to persons, property, and the environment from the hazards associated with transporting radioactive material. This work provided an impetus for the Department of Energy to investigate the use of probabilistic risk assessment techniques to supplement the deterministic approach to transportation safety. The DOE recently decided to incorporate the methodologies associated with PRAs in the process for authorizing the transportation of nuclear components, special assemblies, and radioactive materials affiliated with the DOE Defense Program. Accordingly, the LLNL, sponsored by the DOE/AL, is tasked with developing a safety guide series to provide guidance to preparers performing a transportation system risk assessment

  13. Status of U.S. nuclear waste disposal programs

    International Nuclear Information System (INIS)

    Eastering, J.B.

    1987-01-01

    Since the days of the Manhattan Project in the early 1940's, the United States has recognized the need for a system of effective nuclear waste management. The evolution of that system has been directed by a series of legislative actions to determine responsibilities and develop procedures. Under these laws, the U.S. Department of Energy (DOE), as the lead agency, is required to plan and implement the programs that will ensure safe and efficient management of nuclear wastes from both civilian and defense activities. This overview paper describes the organization of these programs

  14. Preliminary regulatory assessment of nuclear power plants vulnerabilities

    International Nuclear Information System (INIS)

    Kostadinov, V.; Petelin, S.

    2004-01-01

    Preliminary attempts to develop models for nuclear regulatory vulnerability assessment of nuclear power plants are presented. Development of the philosophy and computer tools could be new and important insight for management of nuclear operators and nuclear regulatory bodies who face difficult questions about how to assess the vulnerability of nuclear power plants and other nuclear facilities to external and internal threats. In the situation where different and hidden threat sources are dispersed throughout the world, the assessment of security and safe operation of nuclear power plants is very important. Capability to evaluate plant vulnerability to different kinds of threats, like human and natural occurrences and terrorist attacks and preparation of emergency response plans and estimation of costs are of vital importance for assurance of national security. On the basis of such vital insights, nuclear operators and nuclear regulatory bodies could plan and optimise changes in oversight procedures, organisations, equipment, hardware and software to reduce risks taking into account security and safety of nuclear power plants operation, budget, manpower, and other limitations. Initial qualitative estimations of adapted assessments for nuclear applications are shortly presented. (author)

  15. The TRIUMF nuclear structure program and TIGRESS

    Science.gov (United States)

    Garrett, P. E.; Andreyev, A.; Austin, R. A. E.; Ball, G. C.; Bandyopadhyay, D.; Becker, J. A.; Boston, A. J.; Boston, H. C.; Chakrawarthy, R. S.; Churchman, R.; Cline, D.; Cooper, R. J.; Cross, D.; Dashdorj, D.; Demand, G. A.; Dimmock, M. R.; Drake, T.; Finlay, P.; Gagnon, K.; Gallant, A. T.; Green, K. L.; Grint, A. N.; Grinyer, G. F.; Hackman, G.; Harkness, L. J.; Hayes, A. B.; Kanungo, R.; Kulp, W. D.; Leach, K. G.; Lee, G.; Leslie, J. R.; Maharaj, R.; Martin, J.-P.; Mattoon, C.; Mills, W. J.; Morton, A. C.; Nelson, L.; Newman, O.; Nolan, P. J.; Padilla-Rodal, E.; Pearson, C. J.; Phillips, A. A.; Porter-Peden, M.; Ressler, J. J.; Ruiz, C.; Sarazin, F.; Schumaker, M. A.; Scraggs, D. P.; Strange, M. D.; Subramanian, M.; Svensson, C. E.; Waddington, J. C.; Wan, J.; Whitbeck, A.; Williams, S. J.; Wood, J. L.; Wong, J. C.; Wu, C. Y.; Zganjar, E. F.

    2007-08-01

    The isotope separator and accelerator (ISAC) facility located at the TRIUMF laboratory in Vancouver, Canada, is one of the world's most advanced isotope separator on-line-type radioactive ion beam facilities. An extensive γ-ray spectroscopy programme at ISAC is centred around two major research facilities: (i) the 8π γ-ray spectrometer for β-delayed γ-ray spectroscopy experiments with the low-energy beams from ISAC-I, and (ii) the next generation TRIUMF-ISAC gamma-ray escape suppressed spectrometer (TIGRESS) for in-beam experiments with the accelerated radioactive-ion beams. An overview of these facilities and recent results from the diverse programme of nuclear structure and fundamental interaction studies they support is presented.

  16. Change of nuclear administrative system and long-term program for nuclear energy in Japan

    International Nuclear Information System (INIS)

    Yun, S. W.; Yang, M. H.; Jeong, H. S.

    2001-01-01

    Japanese new governmental adminstrative system was restructured and became in operation from January 1, 2001 including newly establishment of the Ministry of Cabinet. Accordingly, Japanese nuclear administrative system were also changed significantly, in order to reflect the changing policy environment and response to them more efficiently in the use and development of nuclear energy. Atomic Energy Commission, Nuclear Safety Commission administrated by Science and Technology Agency in the past, were moved to the Ministry of Cabinet, and Integrated Science and Technology Council was also newly established under the Ministry of Cabinet. And Ministry of Economy, Trade and Industry(METI) is in charge of nuclear energy policy and the Ministry of Education, Culture, Sports, Science and Technology(MEXT) is in charge of nuclear academic science consequently. At the same time, the revision work of 'Long-term Program for Research, Development and Utilization of Nuclear of Japan' established in 1994, has been carried out from 1999 in order to set up the long term based national nuclear policy towards the 21st century, and finally the results were open to the public in November 2000. Major changes of nuclear policy of Japan the will be good references in the establishing future national nuclear policy for the use and development of nuclear energy

  17. The U.S. program for fusion nuclear technology development

    International Nuclear Information System (INIS)

    Clarke, J.F.; Haas, G.M.

    1989-01-01

    The Fusion Nuclear Technology (FNT) research and development program in the United States is shaped by a hierarchy of documents and by the environment for nuclear energy existing in the United States. The fission nuclear industry in the United States has suffered problems with public perception of safety, waste disposal issues, and economics as influenced by safety and environmental issues. For fusion to be a viable energy alternative, it must offer significant improvements in these areas. The hierarchy of documents defining objectives, plans, and strategy of the U.S. FNT program consists of the Magnetic Fusion Program Plan (MFPP) (February 1985), the Technical Planning Activity Final Report (January 1987), the Finesse Program Report (January 1987), and the Blanket Comparison and Selection Study Final Report (September 1984). In addition, two other documents are also significant in shaping FNT policy. These are the IEA report on Material for Fusion (December 1986) and the Summary of the Report of the Senior Committee on Environmental, Safety, and Economic Aspects of Magnetic Fusion Energy (September 1987). The U.S. Magnetic Fusion Program Plan defines four key technical issues (magnetic confinement systems, properties of burning plasmas, fusion nuclear technology, and fusion materials). (orig./KP)

  18. Regulatory oversight strategy for chemistry program at Canadian nuclear power plants

    International Nuclear Information System (INIS)

    Kameswaran; Ram

    2012-09-01

    Chemistry program is one of the essential programs for the safe operation of a nuclear power plant. It helps to ensure the necessary integrity, reliability and availability of plant structures, systems and components important to safety. Additionally, the program plays an important role in asset preservation, limiting radiation exposure and environmental protection. A good chemistry program will minimize corrosion of materials, reduce activation products, minimize of the buildup of radioactive material leading to occupational radiation exposure and it helps limit the release of chemicals and radioactive materials to the environment. The legal basis for the chemistry oversight at Canadian NPPs is established by the Nuclear Safety and Control Act and its associated regulations. It draws on the Canadian Nuclear Safety Commission's regulatory framework and NPP operating license conditions that include applicable standards such as CAN/CSA N286-05 Management System Requirements for Nuclear Power Plants. This paper focuses on the regulatory oversight strategy used in Canada to assess the performance of chemistry program at the nuclear power plants (NPPs) licensed by CNSC. The strategy consists of a combination of inspection and performance monitoring activities. The activities are further supported from information gathered through staff inspections of cross-cutting areas such as maintenance, corrective-action follow-ups, event reviews and safety related performance indicators. (authors)

  19. Waste management in Canadian nuclear programs

    International Nuclear Information System (INIS)

    Dyne, P.J.

    The objectives of the Canadian radioactive waste management program are described. Recycling actinides through reactors is being studied. Low and medium level waste treatments such as reverse osmosis concentration, immobilization in bitumen and plastics, and incineration are under study. Spent fuel can be stored dry in concrete canisters above ground and ultimate storage of wastes in salt deposits or hard rock is appropriate to Canadian conditions. (E.C.B.)

  20. Automated Assessment in a Programming Tools Course

    Science.gov (United States)

    Fernandez Aleman, J. L.

    2011-01-01

    Automated assessment systems can be useful for both students and instructors. Ranking and immediate feedback can have a strongly positive effect on student learning. This paper presents an experience using automatic assessment in a programming tools course. The proposal aims at extending the traditional use of an online judging system with a…

  1. Environmental stress and assessment program

    International Nuclear Information System (INIS)

    Adriano, D.C.; Brisbin, I.L.; Gibbons, J.W.

    1981-01-01

    Research progress is reported in sections entitled: Savannah River Plant (SRP) studies provide general models for thermal research; in vivo studies of thermal stabilities of cattail isozymes reveal interspecific differences; thermal regimes in Par Pond have little effect on micronutrient uptake by cattails; continued tree kill in the SRP swamp may have an adverse impact on the swamp's cooling capabilities; Par Pond provides understanding of complexity of lake ecosystems affected by thermal effluents; temperature affects size, species distribution, and emergence date of dragonfly larvae; the midge subcommunity in Par Pond maintains relative integrity across a multi-faceted environmental gradient; temperature does not alter contribution of predators to community stability; habitat affects enzyme activity levels in natural populations of Gambusia affinis; studies of large-mouth bass in Par Pond system reveal lipid cycles; long-term turtle research provides information on survivorship and longevity; data on SRP watersnakes contribute to understanding of sexual dimorphism in animals; terrestrial drift fences and pitfall traps prove to be an effective technique for quantitative sampling of animal populations; and, Steel Creek targeted for environmental assessment

  2. Nuclear materials control and accountability internal audit program

    International Nuclear Information System (INIS)

    Barham, M.A.; Abbott, R.R.

    1991-01-01

    This paper reports that the Department of Energy Order (DOE) 5633.3, Control and Accountability for Nuclear Materials, includes several requirements for development and implementation of an internal audit program. Martin Marietta Energy System, Inc., manages five sites in Tennessee, Kentucky, and Ohio for the DOE Field Office, Oak Ridge and has a Central Nuclear Materials Control and Accountability (NMC and A) Manager with matrixed responsibility for the NMC and A program at the five sites. The Energy Systems Central NMC and A Manager has developed an NMC and A Internal Audit Handbook which defines the functional responsibilities, performance criteria, and reporting and documentation requirements for the Energy Systems NMC and A Internal Audit Program. The initial work to develop and implement these standards was tested at the K-25 Site when the site hired an internal auditor to meet the DOE requirements for an NMC and A Internal Audit program

  3. Sudan Country Profile - Human Resource Development (HRD) for the first Nuclear Power Program

    International Nuclear Information System (INIS)

    Yousif, Eltayeb H. Elneel

    2014-01-01

    Sudan has been decided to prepare a strategy plan for the first nuclear power plant for various reasons like production electricity and increase the national industries besides the capabilities to do the scientific and research activities. Sudan has been started to establish and develop a master plan for the human resource development and makes a comprehensive realistic assessment about the organizational, educational and industrial capabilities and determines the requirements for developing the quality and quantity of human resources needed. The national nuclear regulatory authority has been started to update all legislation and regulations and also reviews and evaluates the international agreements and conventions related to the nuclear energy. In this profile we used the methodology of the international atomic energy agency to assess and evaluate the capacity building in Sudan. The expected outcomes from this profile are identified the gaps regarding the strengthening the national infrastructure and nuclear regulatory framework and issuing regulations to met the requirements for safety and security of the nuclear power plant. The availability of the human resources skills are important for effectively monitors the activities of the companies and facilities involved in nuclear power plant. The new nuclear law and the new national policy of the nuclear program are now under the process of approval.(author)

  4. The program of reactors and nuclear power plants

    International Nuclear Information System (INIS)

    Calabrese, Carlos R.

    2001-01-01

    Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined

  5. Underlying chemistry research for the nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Torgerson, D.F.; Sagert, N.H.; Shoesmith, D.W.; Taylor, P.

    1984-04-01

    This document reviews the underlying chemistry research part of the Canadian Nuclear Fuel Waste Management Program, carried out in the Research Chemistry Branch. This research is concerned with developing the basic chemical knowledge and under-standing required in other parts of the Program. There are four areas of underlying research: Waste Form Chemistry, Solute and Solution Chemistry, Rock-Water-Waste Interactions, and Abatement and Monitoring of Gas-Phase Radionuclides

  6. Inpo programs for improvement of nuclear power plant operations

    International Nuclear Information System (INIS)

    Edward Moore, C.

    1989-01-01

    The talk shows how key INPO programs help foster improved nuclear power operations. The talk focuses on the results being seen from six key efforts: evaluations, training and accreditation, assistance, events analysis and information exchange, human performance and maintenance. The talk stresses that all INPO programs are geared toward enhanced performance and that progress in key performance areas since 1980 shows that INPO and U.S. industry efforts are achieving desired results

  7. U.S. Nuclear Regulatory Commission natural analogue research program

    International Nuclear Information System (INIS)

    Kovach, L.A.; Ott, W.R.

    1995-01-01

    This article describes the natural analogue research program of the U.S. Nuclear Regulatory Commission (US NRC). It contains information on the regulatory context and organizational structure of the high-level radioactive waste research program plan. It also includes information on the conditions and processes constraining selection of natural analogues, describes initiatives of the US NRC, and describes the role of analogues in the licensing process

  8. Iran's nuclear program - for power generation or nuclear weapons?; Irans kjernefysiske program - for kraftproduksjon eller kjernevaapen?

    Energy Technology Data Exchange (ETDEWEB)

    Kippe, Halvor

    2008-11-15

    This report addresses the development of a nuclear infrastructure in Iran, and assessments are made on the near-term potential this infrastructure might yield of either nuclear power or nuclear arms production. The most significant facilities are treated in a more elaborate fashion, as these are assumed to have key roles in either a true civilian programme, or in the prospect of weapons-grade fissile material production. The future potential capacity for the latter is calculated under certain presumptions, both in the case that Iran focuses its efforts on uranium-based nuclear weapons, and in the case that it should choose the plutonium path to nuclear weapons. All the conclusions and findings in this report are based on technological considerations. This means that social or political assessments have not prevailed, rather the picture of Iran's nuclear programme is drawn through descriptions and assessments of facilities and systems, and their role in the bigger context. Definite conclusions have not been made as to whether Iran's nuclear programme currently is aimed towards nuclear arms or nuclear power. The secrecy surrounding some of the most prominent nuclear sites together with more or less credible allegations of purely weapons-related activities in the past, make it hard not to conclude that Iran until the disclosures in 2002 made as great an effort as it could on its way on developing nuclear weapons covertly. The scope of today's nuclear programme seems, on the other hand, most likely to be in part to help relieve the ever-increasing need for energy, although considerable deficits to this strategy are identified, at the same time as the Iranian people are united in a giant, high-prestige project in defiance of massive international pressure. Adding to this is a much-feared ability to rapidly being able to redirect their nuclear efforts, and develop nuclear arms in perhaps as little as one year. This so-called break-out scenario, where Iran

  9. Development of Risk Assessment Methodology for State's Nuclear Security Regime

    International Nuclear Information System (INIS)

    Jang, Sung Soon; Seo, Hyung Min; Lee, Jung Ho; Kwak, Sung Woo

    2011-01-01

    Threats of nuclear terrorism are increasing after 9/11 terrorist attack. Treats include nuclear explosive device (NED) made by terrorist groups, radiological damage caused by a sabotage aiming nuclear facilities, and radiological dispersion device (RDD), which is also called 'dirty bomb'. In 9/11, Al Qaeda planed to cause radiological consequences by the crash of a nuclear power plant and the captured airplane. The evidence of a dirty bomb experiment was found in Afganistan by the UK intelligence agency. Thus, the international communities including the IAEA work substantial efforts. The leaders of 47 nations attended the 2010 nuclear security summit hosted by President Obama, while the next global nuclear summit will be held in Seoul, 2012. Most states established and are maintaining state's nuclear security regime because of the increasing threat and the international obligations. However, each state's nuclear security regime is different and depends on the state's environment. The methodology for the assessment of state's nuclear security regime is necessary to design and implement an efficient nuclear security regime, and to figure out weak points. The IAEA's INPRO project suggests a checklist method for State's nuclear security regime. The IAEA is now researching more quantitative methods cooperatively with several countries including Korea. In this abstract, methodologies to evaluate state's nuclear security regime by risk assessment are addressed

  10. Nuclear Power Plant Fire Protection Research Program

    International Nuclear Information System (INIS)

    Datta, A.

    1985-07-01

    The goal is to develop test data and analytical capabilities to support the evaluation of: (1) the contribution of fires to the risk from nuclear power plants; (2) the effects of fires on control room equipment and operations; and (3) the effects of actuation of fire suppression systems on safety equipment. A range of fire sources will be characterized with respect to their energy and mass evolution, including smoke, corrosion products, and electrically conductive products of combustion. An analytical method for determining the environment resulting from fire will be developed. This method will account for the source characteristics, the suppression action following detection of the fire, and certain parameters specific to the plant enclosure in which the fire originates, such as the geometry of the enclosure and the ventilation rate. The developing local environment in the vicinity of safety-related equipment will be expressed in terms of temperatures, temperature rise rates, heat fluxes, and moisture and certain species content. The response of certain safe shutdown equipment and components to the environmental conditions will be studied. The objective will be to determine the limits of environmental conditions that a component may be exposed to without impairment of its ability to function

  11. ASSESSING THE UNCERTAINTY OF NUCLEAR DETERRENCE

    Science.gov (United States)

    2017-04-22

    unlimited. Abstract Nuclear deterrence theory in its many forms arose as a theoretical architecture with the goal of preventing rather than winning a nuclear... Egyptians and Syrians advanced toward Israel.31 Finally, the Kargil war represents a particularly volatile situation where the world looked on in fear as

  12. Current emergency programs for nuclear installations in Japan

    International Nuclear Information System (INIS)

    Chino, Masamichi

    2007-01-01

    Large effort has been taken for nuclear emergency programs in Japan especially after the JCO accident. A special law for nuclear emergency was established after the accident. The law extended the scope of emergency preparedness to fuel cycle facilities, research reactors, etc. and clarified the roles and responsibilities of the national government, local governments and license holders. For initial responses, the action levels and action procedures are defined based on environmental doses and specific initial events of NPPs. A senior specialist was dispatched to each site for nuclear emergency and a facility 'Off-site center' to be used as the local emergency headquator was designated at each site. This paper describes the structure of emergency program, responsibility of related organizations and the definition of unusual events for notification and emergency. Emergency preparedness, emergency radiation monitoring and computer-based prediction of on- and off-site situation are also addressed. (author)

  13. Enhancing materials management programs in nuclear power plants

    International Nuclear Information System (INIS)

    Hassaballa, M.M.; Malak, S.M.

    1992-01-01

    Materials management programs for the nuclear utilities in the United States are continually being affected, concurrent with the gradual disappearance of qualified component and replacement parts vendors by regulatory concerns about procurement and materials management. In addition, current economic and competitive pressures are forcing utilities to seek avenues for reducing procurement costs for safety-related items. In response to these concerns, initiatives have been undertaken and engineering guidelines have been developed by the nuclear power industry-sponsored organizations, such as the Electric Power Research Institute and the Nuclear Management Resources Council. It is our experience that successful materials management programs require a multitude of engineering disciplines and experience and are composed of three major elements: strategic procurement plan, parts classification and procurement data base, and enhancement tools. This paper provides a brief description of each of the three elements

  14. Irans Nuclear Program: Tehrans Compliance with International Obligations

    Science.gov (United States)

    2016-04-07

    reactors. Iran also has a uranium conversion facility, which converts uranium oxide into several compounds, including uranium hexafluoride. Tehran claims... uranium .  The importation of natural uranium metal and its subsequent transfer for use in laser enrichment experiments, including the production of...investigation of its nuclear activities, suspend its uranium enrichment program, suspend its construction of a heavy-water reactor and related

  15. Nuclear Application Programs Development and Integration for a Simulator

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun-Joon; Lee, Tae-Woo [KEPCO Engineering and Construction Co., Deajeon (Korea, Republic of)

    2016-10-15

    KEPCO E and C participated in the NAPS (Nuclear Application Programs) development project for BNPP (Barakah Nuclear Power Plant) simulator. The 3KEY MASTER™ was adopted for this project, which is comprehensive simulation platform software developed by WSC (Western Services Corporation) for the development, and control of simulation software. The NAPS based on actual BNPP project was modified in order to meet specific requirements for nuclear power plant simulators. Considerations regarding software design for BNPP simulator and interfaces between the 3KM platform and application programs are discussed. The repeatability is one of functional requirements for nuclear power plant simulators. In order to migrate software from actual plants to simulators, software functions for storing and retrieving plant conditions and program variables should be implemented. In addition, software structures need to be redesigned to meet the repeatability, and source codes developed for actual plants would have to be optimized to reflect simulator’s characteristics as well. The synchronization is an important consideration to integrate external application programs into the 3KM simulator.

  16. The Nordic program for nuclear safety 1990-1993

    International Nuclear Information System (INIS)

    1991-02-01

    The status of ongoing projects under The Nordic Program for Nuclear Safety (NKS) 1990-1993, and the economy of the programme is presented. A review of projects, projects managers and coordinators, and a list of members of NKS and associated members is included. (CLS)

  17. BIBGTR: nuclear data libraries for the programs Unimug and Anisn

    International Nuclear Information System (INIS)

    Ono, S.; Caldeira, A.D.

    1989-11-01

    Nuclear data libraries generable by the NJOY for the programs UNIMUG and ANISN, using evaluated data from ENDF/B-IV and ENDF/B-V are described. These libraries will be used by Radioisotope Thermoelectric Generators Project of Instituto de Estudos Avancados. (author) [pt

  18. Space Nuclear Safety Program. Progress report, March 1984

    International Nuclear Information System (INIS)

    Zocher, R.W.; George, T.G.

    1985-08-01

    This technical monthly report covers studies related to the use of 238 PuO 2 in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos Laboratory. They are divided into: general-purpose heat source, lightweight radioisotope heater unit, and safety technology program. 43 figs., 2 tabs

  19. Nuclear plant analyzer program for Bulgaria

    International Nuclear Information System (INIS)

    Shier, W.; Kennett, R.

    1993-01-01

    An interactive nuclear plant analyzer(NPA) has been developed for use by the Bulgarian technical community in the training of plant personnel, the development and verification of plant operating procedures, and in the analysis of various anticipated operational occurrences and accident scenarios. The current NPA includes models for a VVER-440 Model 230 and a VVER-1000 Model 320 and is operational on an IBM RISC6000 workstation. The RELAP5/MOD2 computer code has been used for the calculation of the reactor responses to the interactive commands initiated by the NPA operator. The interactive capabilities of the NPA have been developed to provide considerable flexibility in the plant actions that can be initiated by the operator. The current capabilities for both the VVER-440 and VVER-1000 models include: (1) scram initiation; (2) reactor coolant pump trip; (3) high pressure safety injection system initiation; (4) low pressure safety injection system initiation; (5) pressurizer safety valve opening; (6) steam generator relief/safety valve opening; (7) feedwater system initiation and trip; (8) turbine trip; and (9) emergency feedwater initiation. The NPA has the capability to display the results of the simulations in various forms that are determined by the model developer. Results displayed on the reactor mask are shown through the user defined, digital display of various plant parameters and through color changes that reflect changes in primary system fluid temperatures, fuel and clad temperatures, and the temperature of other metal structures. In addition, changes in the status of various components and systems can be initiated and/or displayed both numerically and graphically on the mask. This paper provides a description of the structure of the NPA, a discussion of the simulation models used for the VVER-440 and the VVER-1000, and an overview of the NPA capabilities. Typical results obtained using both simulation models will be discussed

  20. Nuclear energy and public opinion. Chilean Nuclear Energy Commission (CCHEN) dissemination and extension program

    International Nuclear Information System (INIS)

    Oviedo, Gonzalo Torres; Quintana, Rosamel Mufioz

    2000-01-01

    In Chile, demand for electricity will soon exceed water resources. The country will then face severe energy dependence, with very little control over generation costs, and with increasing emission of contaminating gases into the atmosphere. Nuclear energy may be considered an appropriate and stabilizing alternative for the system in the medium term, the benefits of nuclear generation to be thus extended to a country which has a moderate demand for electricity. This new scenario will require an additional technical and regulating effort by CCHEN and by the state, as well as re-orientation of their activities in connection with public opinion. The Public Nuclear Energy Education Program, initiated in 1976 by CCHEN, has been developed for purposes of achieving public acceptance of nuclear energy as a way of facilitating development of various activities which pertain to CCHEN's scope of action, and of creating a climate which is favorable to acceptance of nuclear energy as an alternative source of energy. Thus, the object is that the public draw informed conclusions on the benefits and risks implicit in the use of isotopes, radiation, and nuclear power generation. The Program consists of activities for high school students aimed at vocational orientation of those who stand out in the science area, training and extension activities for teachers, journalists, and professionals, a program of guided tours of the nuclear centers, a publicity campaign conducted in the various media and, since 1980, massive distribution of brochures and magazines. There are no declared anti-nuclear movements in Chile. Nevertheless, there are opinions against nuclear power in different relevant sectors. Lately, the social communication media have preferred CCHEN as their source of information, a fact which makes it possible for the latter to have access to good coverage of its activities