WorldWideScience

Sample records for program assessing nuclear

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  2. 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.

  3. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    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.

  5. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VIII. Advanced concepts

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    The goal of the Nonproliferation Alternative Systems Assessment Program has been to provide recommendations for the development and deployment of more proliferation-resistant civilian nuclear-power systems without jeopardizing the development of nuclear energy. In principle, new concepts for nuclear-power systems could be designed so that materials and facilities would be inherently more proliferation-resistant. Such advanced, i.e., less-developed systems, are the subject of this volume. Accordingly, from a number of advanced concepts that were proposed for evaluation, six representative concepts were selected: the fast mixed-spectrum reactor; the denatured molten-salt reactor; the mixed-flow gaseous-core reactor; the linear-accelerator fuel-regenerator reactor; the ternary metal-fueled electronuclear fuel-producer reactor; and the tokamak fusion-fission hybrid reactor.

  6. 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.

  7. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume VIII. Advanced concepts

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    The six advanced concepts for nuclear power systems that were selected for evaluation are: the fast mixed-spectrum reactor; the denatured molten-salt reactor; the mixed-flow gaseous-core reactor; the linear-accelerator fuel-regenerator reactor; the ternary metal-fueled electronuclear fuel-producer reactor; and the tokamak fusion-fission hybrid reactor. The design assessment was performed by identifying needs in six specific areas: conceptual plant design; reactor-physics considerations; fuel cycle alternatives; mechanical and thermal-hydraulic considerations; selection, development, and availability of materials; and engineering and operability. While none of the six concepts appears to be a credible commercial alternative to the liquid-metal fast-breeder within the Nonproliferation Alternative Systems Assessment Program horizon of 2025, there are a number of reasons for continued interest in the fast mixed-spectrum reactor: it is a once-through cycle fast reactor with proliferation risk characteristics similar to those of the light-water reactor; only about one-third as much uranium is required as for the once-through light-water reactor; the system will benefit directly from fast-breeder development programs; and, finally, the research and development required to develop the high-burnup metal fuel could benefit the on-going liquid-metal fast-breeder reactor program. Accordingly, a limited research and development effort on the high-burnup fuel seems justified, at present.

  8. 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)

  9. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume II. Proliferation resistance

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    Volume II assesses proliferation resistance. Chapters are devoted to: assessment of civilian nuclear systems (once-through fuel-cycle systems, closed fuel cycle systems, research reactors and critical facilities); assessment of associated sensitive materials and facilities (enrichment, problems with storage of spent fuel and plutonium content, and reprocessing and refabrication facilities); and safeguards for alternative fuel cycles.

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    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.

  11. Preliminary results 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.; Twitchell, David C.; Geist, Eric L.; Chaytor, Jason D.; Locat, J.; Lee, H.J.; Buczkowski, Brian J.; Sansoucy, M.

    2008-01-01

    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 other key researchers for the purpose of assessing tsunami hazard on the Atlantic and Gulf Coasts of the United States. The initial phase of this work consisted principally of collection, interpretation, and analysis of available offshore data and information. 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 over the long time periods of interest to the US NRC is a key difference between this program and most other tsunami hazard assessment programs. Although only a few years old, this program is already producing results that both support current US NRC activities and look toward the long-term goal of probabilistic tsunami hazard assessment. This paper provides a summary of results from several areas of current research. An overview of the broader US NRC research program is provided in a companion paper in this conference.

  12. 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.

  13. 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.

  14. 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".

  15. 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.

  16. 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.

  17. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  19. LASL nuclear rocket propulsion program

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, R.E.

    1956-04-01

    The immediate objective of the LASL nuclear propulsion (Rover) program is the development of a heat exchanger reactor system utilizing uranium-graphite fuel elements and ammonia propellant. This program is regarded as the first step in the development of nuclear propulsion systems for missiles. The major tasks of the program include the investigation of materials at high temperatures, development of fuel elements, investigation of basic reactor characteristics, investigation of engine control problems, detailed engine design and ground testing. The organization and scheduling of the initial development program have been worked out in some detail. Only rather general ideas exist concerning the projection of this work beyond 1958.

  20. 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

  1. 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.

  2. Environmental Detection of Clandestine Nuclear Weapon Programs

    Science.gov (United States)

    Kemp, R. Scott

    2016-06-01

    Environmental sensing of nuclear activities has the potential to detect nuclear weapon programs at early stages, deter nuclear proliferation, and help verify nuclear accords. However, no robust system of detection has been deployed to date. This can be variously attributed to high costs, technical limitations in detector technology, simple countermeasures, and uncertainty about the magnitude or behavior of potential signals. In this article, current capabilities and promising opportunities are reviewed. Systematic research in a variety of areas could improve prospects for detecting covert nuclear programs, although the potential for countermeasures suggests long-term verification of nuclear agreements will need to rely on methods other than environmental sensing.

  3. Status of Iran's nuclear program and negotiations

    Science.gov (United States)

    Albright, David

    2014-05-01

    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.

  4. DoD Theater Nuclear Forces Survivability and Security (TNFSS): Compendium of Assessments Related to TNFSSCCC Program. Volume I.

    Science.gov (United States)

    1979-12-31

    intergration with the existing TNF S2 Compendium. 1.2 ORGANIZATION OF THE COMPENDIUM Each assessment and document which has been identified and included in this...of TNF S2 C3 Program concern: (1) Threat to C3 CODE NUMBER: 1 (2) Security of C3 facilities * 2 (3) Survivability of C3 facilities 3 (4) C3...to the general C3 area and in particular to 10 I the modeling and simulation of C3 systems or networks . Similarly, a B.3.4 entry would indicate a

  5. 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

  6. 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.

  7. 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.

  8. NASA program planning on nuclear electric propulsion

    Science.gov (United States)

    Bennett, Gary L.; Miller, Thomas J.

    1992-01-01

    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.

  9. Nuclear Structure Data Evaluation and the US Nuclear Data Program

    Science.gov (United States)

    Helmer, Richard G.

    2001-10-01

    The United States Nuclear Data Program and the Nuclear Structure and Decay Data network of the International Atomic Energy Agency work in collaboration to provide recommended nuclear structure and decay data for use in basic and applied research. Data are evaluted for nuclear levels and for various types of radiation. In addition, an extensive bibliographic database of nuclear structure, reaction, and decay data references is maintained. The databases maintained by the National Nuclear Data Center at Brookhaven National Laboratory include the Evaluated Nuclear Structure Data File (ENSDF), the Experimental Unevaluated Nuclear Data Library (XUNDL), and the Nuclear Sciences References (NSR). These data are all available via the Internet and some are available in hard-copy. Although the data in the ENSDF database for a particular nucleus has often not been updated in the last few fears, XUNDL provides compiled experimental data from papers with a delay of only about one month. Also, the NSR bibliographic database is current for the many journals that are monitored regularly.

  10. Update on DOE's Nuclear Energy University Program

    Science.gov (United States)

    Lambregts, Marsha J.

    2009-08-01

    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&D) Grants, (2) Infrastructure improvement, and (3) Scholarships and Fellowships. NEUP will also host periodic reviews of university mission-specific R&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&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.

  11. Review of EPRI Nuclear Human Factors Program

    Energy Technology Data Exchange (ETDEWEB)

    Hanes, L.F.; O`Brien, J.F. [Electric Power Research Institute, Palo Alto, CA (United States)

    1996-03-01

    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.

  12. 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.

  13. Nuclear Energy Readiness Indicator Index (NERI): A benchmarking tool for assessing nuclear capacity in developing countries

    Energy Technology Data Exchange (ETDEWEB)

    Saum-Manning,L.

    2008-07-13

    Declining natural resources, rising oil prices, looming climate change and the introduction of nuclear energy partnerships, such as GNEP, have reinvigorated global interest in nuclear energy. The convergence of such issues has prompted countries to move ahead quickly to deal with the challenges that lie ahead. However, developing countries, in particular, often lack the domestic infrastructure and public support needed to implement a nuclear energy program in a safe, secure, and nonproliferation-conscious environment. How might countries become ready for nuclear energy? What is needed is a framework for assessing a country's readiness for nuclear energy. This paper suggests that a Nuclear Energy Readiness Indicator (NERI) Index might serve as a meaningful basis for assessing a country's status in terms of progress toward nuclear energy utilization under appropriate conditions. The NERI Index is a benchmarking tool that measures a country's level of 'readiness' for nonproliferation-conscious nuclear energy development. NERI first identifies 8 key indicators that have been recognized by the International Atomic Energy Agency as key nonproliferation and security milestones to achieve prior to establishing a nuclear energy program. It then measures a country's progress in each of these areas on a 1-5 point scale. In doing so NERI illuminates gaps or underdeveloped areas in a country's nuclear infrastructure with a view to enable stakeholders to prioritize the allocation of resources toward programs and policies supporting international nonproliferation goals through responsible nuclear energy development. On a preliminary basis, the indicators selected include: (1) demonstrated need; (2) expressed political support; (3) participation in nonproliferation and nuclear security treaties, international terrorism conventions, and export and border control arrangements; (4) national nuclear-related legal and regulatory mechanisms; (5

  14. 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)

  15. 75 FR 11205 - Entergy Nuclear Operations, Inc; Pilgrim Nuclear Power Station Environmental Assessment and...

    Science.gov (United States)

    2010-03-10

    ... COMMISSION Entergy Nuclear Operations, Inc; Pilgrim Nuclear Power Station Environmental Assessment and... Nuclear Operations, Inc. (Entergy or the licensee), for operation of Pilgrim Nuclear Power Station... Nuclear Power Station,'' NUREG-1437, Supplement 29, published in July 2007 (ADAMS Accession No...

  16. 76 FR 66089 - Access Authorization Program for Nuclear Power Plants

    Science.gov (United States)

    2011-10-25

    ... COMMISSION Access Authorization Program for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission... revision to Regulatory Guide 5.66, ``Access Authorization Program for Nuclear Power Plants.'' This guide... Authorization Requirements for Nuclear Power Plants,'' and 10 CFR part 26, ``Fitness for Duty Programs.'' The RG...

  17. 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.

  18. 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.

  19. 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.

  20. 75 FR 11575 - James A. Fitzpatrick Nuclear Power Plant Environmental Assessment and Finding of No Significant...

    Science.gov (United States)

    2010-03-11

    ... COMMISSION James A. Fitzpatrick Nuclear Power Plant Environmental Assessment and Finding of No Significant... Program for Nuclear Power Facilities Operating Prior to January 1, 1979,'' issued to Entergy Nuclear Operations, Inc. (the licensee), for the operation of the James A. FitzPatrick Nuclear Power Plant (JAFNPP...

  1. 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…

  2. The Bioscience Nuclear Microscopy Program at LLNL

    Energy Technology Data Exchange (ETDEWEB)

    Bench, G.; Freeman, S.; Roberts, M.; Sideras-Haddad, E.

    1996-12-31

    Since initiation in mid 1994, a bioscience nuclear microscopy program at Livermore has enabled collaboration with bio-scientists on a variety of projects requiring quantitative elemental microanalysis. For microprobe analysis a combination of PIXE and STIM are typically used; respectively generating element distribution maps with micron scale spatial resolution, and projected densities and histological information with sub-micron spatial resolution. Current studies demonstrate the applicability of nuclear microscopy (particularly when combined with other analysis techniques) in environmental tracing, toxicology, carcinogenesis, and structural biology. The program currently uses {approximately}10 percent of the available time on a 10 MV tandem accelerator that is also applied to a variety of Accelerator Mass Spectrometry and other microprobe programs. The completion of a dedicated nuclear microprobe system, using a 5 SDH NEC 1.7 MV tandem accelerator and employing several energy dispersive x-ray detectors to improve x-ray counting rates, promises increased accelerator access, greater sample throughput and continued expansion of the program.

  3. 75 FR 2164 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Environmental Assessment and...

    Science.gov (United States)

    2010-01-14

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Environmental Assessment and...), for operation of Pilgrim Nuclear Power Station (Pilgrim), located in Plymouth County, MA. Therefore...

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  5. The nuclear data program at rensselaer

    Science.gov (United States)

    Danon, Y.; Blain, Z.; Bahran, R.; Rapp, M.; Thompson, J.; Williams, D.; Leinweber, G.; Barry, D.; Block, R.; Hoole, J.

    2010-10-01

    The nuclear data program at the Rensselaer Polytechnic Institute (RPI) is centered around a 60 MeV pulsed electron Linear Accelerator (LINAC) configured to deliver pulsed neutron beams. The LINAC electron pulse width can vary between 5 ns and 5 us, a repetition rate of 1-500 pulses per second and neutron yield of up to 1013 n/s. Over the years several experimental setups and techniques were developed to enable a variety of measurement capabilities. The experiments cover the energy range from 0.001 eV to 20 MeV and included neutron transmission, capture, scattering and fission measurements. The facility is also equipped with a Lead Slowing-Down Spectrometer (LSDS) producing a high neutron flux that is used for simultaneous measurements of the fission cross section and fission fragment mass and energy distributions. Detectors for (n, alpha) and (n, p) cross section measurements using the LSDS were also developed and measurements of (n, alpha) cross section were completed. The high neutron flux inside the LSDS enables measurements on small samples (sub micrograms) or samples with small cross section (sub millibarns). In order to fully utilize the capabilities of the facility, several measurement techniques were developed; high accuracy (modular detectors for both fast and resonance region neutron detection were developed and deployed. These developments result in numerous measurements on different materials and provide input to improved evaluated nuclear data libraries and thus help improve the accuracy of calculations of nuclear reactors and other nuclear systems.

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

    Energy Technology Data Exchange (ETDEWEB)

    BRADY RAAP, M.C.

    1999-06-24

    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.

  7. 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).

  8. Nuclear Technology Series. Nuclear Reactor (Plant) Operator Trainee. A Suggested Program Planning Guide. Revised June 80.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This program planning guide for a two-year postsecondary nuclear reactor (plant) operator trainee program is designed for use with courses 1-16 of thirty-five in the Nuclear Technology Series. The purpose of the guide is to describe the nuclear power field and its job categories for specialists, technicians and operators; and to assist planners,…

  9. Nuclear power plant security assessment technical manual.

    Energy Technology Data Exchange (ETDEWEB)

    O' Connor, Sharon L.; Whitehead, Donnie Wayne; Potter, Claude S., III

    2007-09-01

    This report (Nuclear Power Plant Security Assessment Technical Manual) is a revision to NUREG/CR-1345 (Nuclear Power Plant Design Concepts for Sabotage Protection) that was published in January 1981. It provides conceptual and specific technical guidance for U.S. Nuclear Regulatory Commission nuclear power plant design certification and combined operating license applicants as they: (1) develop the layout of a facility (i.e., how buildings are arranged on the site property and how they are arranged internally) to enhance protection against sabotage and facilitate the use of physical security features; (2) design the physical protection system to be used at the facility; and (3) analyze the effectiveness of the PPS against the design basis threat. It should be used as a technical manual in conjunction with the 'Nuclear Power Plant Security Assessment Format and Content Guide'. The opportunity to optimize physical protection in the design of a nuclear power plant is obtained when an applicant utilizes both documents when performing a security assessment. This document provides a set of best practices that incorporates knowledge gained from more than 30 years of physical protection system design and evaluation activities at Sandia National Laboratories and insights derived from U.S. Nuclear Regulatory Commission technical staff into a manual that describes a development and analysis process of physical protection systems suitable for future nuclear power plants. In addition, selected security system technologies that may be used in a physical protection system are discussed. The scope of this document is limited to the identification of a set of best practices associated with the design and evaluation of physical security at future nuclear power plants in general. As such, it does not provide specific recommendations for the design and evaluation of physical security for any specific reactor design. These best practices should be applicable to the design and

  10. The TRIUMF nuclear structure program and TIGRESS

    Energy Technology Data Exchange (ETDEWEB)

    Garrett, P E; Andreyev, A; E.Austin, R A; Ball, G C; Bandyopadhyay, D; Becker, J A; Boston, A; Boston, H; Charkrawarthy, 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 T; Subramanian, M; Svensson, C E; Waddington, J C; Wan, J; Whitebeck, A; Williams, S J; Wood, J L; Wong, J C; Wu, C Y; Zganjar, E F

    2006-08-30

    The Isotope Separator and Accelerator (ISAC) facility located at the TRIUMF laboratory in Vancouver, Canada, is one of the world's most advanced ISOL-type radioactive ion beam facilities. An extensive {gamma}-ray spectroscopy program at ISAC is centered around two major research facilities: (1) the 8{pi} {gamma}-ray spectrometer for {beta}-delayed {gamma}-ray spectroscopy experiments with the low-energy beams from ISAC-I, and (2) 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 program of nuclear structure and fundamental interaction studies they support is presented.

  11. The nuclear data program at rensselaer

    Directory of Open Access Journals (Sweden)

    Barry D.

    2010-10-01

    Full Text Available The nuclear data program at the Rensselaer Polytechnic Institute (RPI is centered around a 60 MeV pulsed electron Linear Accelerator (LINAC configured to deliver pulsed neutron beams. The LINAC electron pulse width can vary between 5 ns and 5 us, a repetition rate of 1–500 pulses per second and neutron yield of up to 1013 n/s. Over the years several experimental setups and techniques were developed to enable a variety of measurement capabilities. The experiments cover the energy range from 0.001 eV to 20 MeV and included neutron transmission, capture, scattering and fission measurements. The facility is also equipped with a Lead Slowing-Down Spectrometer (LSDS producing a high neutron flux that is used for simultaneous measurements of the fission cross section and fission fragment mass and energy distributions. Detectors for (n, alpha and (n, p cross section measurements using the LSDS were also developed and measurements of (n, alpha cross section were completed. The high neutron flux inside the LSDS enables measurements on small samples (sub micrograms or samples with small cross section (sub millibarns. In order to fully utilize the capabilities of the facility, several measurement techniques were developed; high accuracy (<1% total cross sections were measured using iron and uranium filtered neutron beams. A system for fast neutron scattering measurements using an array of liquid scintillators and a digital data acquisition system was recently developed and used for several measurements and is now being adapted for fission neutron studies. Methods for simultaneous measurements of fission and capture cross sections using the RPI multiplicity detector are under development and new modular detectors for both fast and resonance region neutron detection were developed and deployed. These developments result in numerous measurements on different materials and provide input to improved evaluated nuclear data libraries and thus help

  12. Nuclear engine system simulation (NESS) program update

    Science.gov (United States)

    Scheil, Christine M.; Pelaccio, Dennis G.; Petrosky, Lyman 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. Key code outputs include reactor operating charactertistics and weights and well as engine system parameters such as performance, weights, dimensions, pressures, temperatures, mass flows and turbopump operating characteristics for both design and off-design operating conditions. Representative NTP engine system designs are also shown. An overview of NESS methodology and capabilities is presented in this paper, with special emphasis being placed on recent code developments.

  13. Potential criminal adversaries of nuclear programs: a portrait

    Energy Technology Data Exchange (ETDEWEB)

    Jenkins, B.M.

    1980-07-01

    This paper examines the possibility that terrorists or other kinds of criminals might attempt to seize or sabotage a nuclear facility, steal nuclear material, or carry out other criminal activities in the nuclear domain which has created special problems for the security of nuclear programs. This paper analyzes the potential threat. Our tasks was to describe the potential criminal adversary, or rather the spectrum of potential adversaries who conceivably might carry out malevolent criminal actions against nuclear programs and facilities. We were concerned with both the motivations as well as the material and operational capabilities likely to be displayed by various categories of potential nuclear adversaries.

  14. 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.

  15. 75 FR 12311 - Entergy Nuclear Operations, Inc; Vermont Yankee Nuclear Power Station Environmental Assessment...

    Science.gov (United States)

    2010-03-15

    ... COMMISSION Entergy Nuclear Operations, Inc; Vermont Yankee Nuclear Power Station Environmental Assessment and... Nuclear Operations, Inc. (Entergy or the licensee), for operation of Vermont Yankee Nuclear Power Station... Statement for Vermont Yankee Nuclear Power Station, Docket No. 50-271, dated July 1972, as supplemented...

  16. 75 FR 14638 - FirstEnergy Nuclear Operating Company; Perry Nuclear Power Plant; Environmental Assessment and...

    Science.gov (United States)

    2010-03-26

    ... COMMISSION FirstEnergy Nuclear Operating Company; Perry Nuclear Power Plant; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of...Energy Nuclear Operating Company (FENOC, the licensee), for operation of the Perry Nuclear Power Plant...

  17. 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.

  18. Developmentally programmed nuclear destruction during yeast gametogenesis.

    Science.gov (United States)

    Eastwood, Michael D; Cheung, Sally W T; Lee, Kwan Yin; Moffat, Jason; Meneghini, Marc D

    2012-07-17

    Autophagy controls cellular catabolism in diverse eukaryotes and modulates programmed cell death in plants and animals. While studies of the unicellular yeast Saccharomyces cerevisiae have provided fundamental insights into the mechanisms of autophagy, the roles of cell death pathways in yeast are less well understood. Here, we describe widespread developmentally programmed nuclear destruction (PND) events that occur during yeast gametogenesis. PND is executed through apoptotic-like DNA fragmentation in coordination with an unusual form of autophagy that is most similar to mammalian lysosomal membrane permeabilization and mega-autophagy, a form of plant autophagic cell death. Undomesticated strains execute gametogenic PND broadly in maturing colonies to the apparent benefit of sibling cells, confirming its prominence during the yeast life cycle. Our results reveal that diverse cell-death-related processes converge during gametogenesis in a microbe distantly related to plants or animals, highlighting gametogenesis as a process during which programmed cell death mechanisms may have evolved. Copyright © 2012 Elsevier Inc. All rights reserved.

  19. Irans Nuclear Program: Tehrans Compliance with International Obligations

    Science.gov (United States)

    2016-04-07

    issue of concern directly affecting fulfilment of JCPOA commitments. 14 Iran has a plant for producing heavy water. Iran’s Nuclear Program: Tehran’s...U.S. official statements have consistently reiterated that Tehran has not yet decided to build nuclear weapons. 58 British Foreign Secretary...Iran’s Nuclear Program: Tehran’s Compliance with International Obligations Paul K. Kerr Analyst in Nonproliferation April 7, 2016

  20. Public Risk Assessment Program

    Science.gov (United States)

    Mendeck, Gavin

    2010-01-01

    The Public Entry Risk Assessment (PERA) program addresses risk to the public from shuttle or other spacecraft re-entry trajectories. Managing public risk to acceptable levels is a major component of safe spacecraft operation. PERA is given scenario inputs of vehicle trajectory, probability of failure along that trajectory, the resulting debris characteristics, and field size and distribution, and returns risk metrics that quantify the individual and collective risk posed by that scenario. Due to the large volume of data required to perform such a risk analysis, PERA was designed to streamline the analysis process by using innovative mathematical analysis of the risk assessment equations. Real-time analysis in the event of a shuttle contingency operation, such as damage to the Orbiter, is possible because PERA allows for a change to the probability of failure models, therefore providing a much quicker estimation of public risk. PERA also provides the ability to generate movie files showing how the entry risk changes as the entry develops. PERA was designed to streamline the computation of the enormous amounts of data needed for this type of risk assessment by using an average distribution of debris on the ground, rather than pinpointing the impact point of every piece of debris. This has reduced the amount of computational time significantly without reducing the accuracy of the results. PERA was written in MATLAB; a compiled version can run from a DOS or UNIX prompt.

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

    Energy Technology Data Exchange (ETDEWEB)

    Bingham, Michelle [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bala, Marsha [Idaho National Lab. (INL), Idaho Falls, ID (United States); Beierschmitt, Kelly [Idaho National Lab. (INL), Idaho Falls, ID (United States); Steele, Carolyn [Argonne National Lab. (ANL), Argonne, IL (United States); Sattelberger, Alfred P. [Argonne National Lab. (ANL), Argonne, IL (United States); Bruozas, Meridith A. [Argonne National Lab. (ANL), Argonne, IL (United States)

    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.

  2. Major accomplishments of America's nuclear rocket program (Rover)

    Science.gov (United States)

    Finseth, J. L.

    The United States embarked on a program called Rover to develop nuclear rocket engines in 1955. Initially, nuclear rockets were considered as a potential backup for intercontinental ballistic missile propulsion, but later proposed applications included both a lunar second stage and 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 author reviews the engine test program and discusses several subsystems.

  3. 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.

  4. Redesigning an educational assessment program.

    Science.gov (United States)

    Al Kadri, Hanan M F

    2009-05-01

    Changing educational assessment program represent a challenge to any organization. This change usually aims to achieve reliable and valid tests and assessment program that make a shift from individual assessment method to an integral program intertwined with the educational curriculum. This paper examines critically the recent developments in the assessment theory and practice, and establishes practical advices for redesigning educational assessment programs. Faculty development, availability of resources, administrative support, and competency based education are prerequisites to an effective successful change. Various elements should be considered when re-designing assessment program such as curriculum objectives, educational activities, standard settings, and program evaluation. Assessment programs should be part of the educational activities rather than being a separate objective on its own, linked to students' high quality learning.

  5. 75 FR 14473 - Entergy Nuclear Operations, Inc., Palisades Nuclear Plant; Environmental Assessment and Finding...

    Science.gov (United States)

    2010-03-25

    ... COMMISSION Entergy Nuclear Operations, Inc., Palisades Nuclear Plant; Environmental Assessment and Finding of... protection of plants and materials,'' for Facility Operating License No. DPR-20, issued to Entergy Nuclear Operations, LLC (ENO) (the licensee), for operation of the Palisades Nuclear Plant (PNP), located in Van...

  6. 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.

  7. 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

  8. 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

  9. 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.

  10. 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...

  11. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  13. 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.

  14. 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)

  15. 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.

  16. 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)

  17. (Coordinated research programs in nuclear medicine)

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.

    1990-10-03

    The traveler visited the Clinic for Nuclear Medicine at the University of Bonn, West Germany, to review, organize, and plan collaborative studies. He also met with the editorial board of the journal NucCompact -- European/American Communications in Nuclear Medicine, on which he serves as US editor. He also visited colleagues at the Cyclotron Research Center (CRC) at the University of Liege, Belgium, to coordinate clinical applications of the ultrashort-lived iridium-191m radionuclide obtained from the osmium-190/iridium-191m generator system. The traveler planned and coordinated continuing collaboration with colleagues at the CRC for further applications of this generator system. He also visited the University of Metz, Metz, France, to organize a three-center project for the synthesis and evaluation of various receptor-specific cerebral imaging agents, involving the Oak Ridge National Laboratory (ORNL), CRC, and the University of Metz.

  18. Status of nuclear power programs in South America

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-10-15

    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)

  19. Update on the U.S. Nuclear Structure and Decay Data Evaluation Program*

    Science.gov (United States)

    Baglin, Coral M.

    2000-04-01

    The U.S. Nuclear Data Program (USNDP) maintains and provides easy access to several large databases to assist scientists to sift through and assess the vast quantity of published nuclear structure and decay data. The Evaluated Nuclear Structure Data File (ENSDF) presents evaluated experimental nuclear data; the Nuclear Structure Reference (NSR) database provides bibliographic information; an Experimental Unevaluated Data Listing (XUNDL)has also recently been established to provide rapid access to data from the most recent publications (primarily in high-spin physics). In addition to the ongoing revision of data in ENSDF, information from the latest evaluations for A=21-44 by Endt[1] and evaluated data for recently-discovered heavy elements (up to Z=118) are currently being incorporated into ENSDF. An overview of nuclear structure and decay data available through the USNDP will be presented, with emphasis on recent and forthcoming additions to the material available. Feedback concerning the extent to which users' nuclear structure and decay data needs are being met by this data program will be welcomed. 1. P.M. Endt, Nucl. Phys. A521, 1 (1998). *On behalf of the U.S. Nuclear Data Program

  20. NP2010: An Assessment and Outlook for Nuclear Physics

    Energy Technology Data Exchange (ETDEWEB)

    Lancaster, James [National Academy of Sciences, Washington, DC (United States). Div. of Engineering and Physical Sciences

    2014-05-22

    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.

  1. An assessment of seismic margins in nuclear plant piping

    Energy Technology Data Exchange (ETDEWEB)

    Chen, W.P.; Jaquay, K.R. [Energy Technology Engineering Center, Canoga Park, CA (United States); Chokshi, N.C.; Terao, D. [Nuclear Regulatory Commission, Washington DC (United States)

    1996-03-01

    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: (1) reviews of seismic testing of piping components performed as part of the Electric Power Research Institute (EPRI)/NRC Piping and Fitting Dynamic Reliability (PFDR) Program, and (2) assessments of safety margins inherent in the ASME Code, Section III, piping seismic design criteria as revised by the 1994 Addenda are reported. The reviews indicate that the margins inherent in the revised criteria may be less than acceptable and that modifications to these criteria may be required.

  2. Sister Lab Program Prospective Partner Nuclear Profile: Malaysia

    Energy Technology Data Exchange (ETDEWEB)

    Bissani, M; Tyson, S

    2006-12-14

    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

  3. 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.

  4. Industrial Assessment Center Program

    Energy Technology Data Exchange (ETDEWEB)

    Kolarik, William J.

    2007-02-26

    Over the five-year period (2002-2006) the Oklahoma State University Industrial Assessment Center (IAC) performed energy assessments for 106 different clients, writing 835 recommendations, for a total of $23,937,099 in potential estimated annual savings. IAC clients served consisted of small and medium-sized manufacturers ranging from food manufactures to foundries. The OSU IAC served clients in Oklahoma, Kansas, Missouri, Arkansas, and Texas. In addition to client service, student training and instruction was a major accomplishment. The OSU IAC employed (and trained) 12 baccalaureate-level students, 17 masters-level graduate students, and 7 doctoral-level graduate students. Most are practicing in the energy management area. Training was focused on both energy assessment and safety. Safety training was both center-based training as well as on-site training. Energy management related training was focused on classroom (for academic credit) work at both the undergraduate and graduate level. IEM 4923 (Energy and Water Management) was developed to serve both the IAC as well as non-IAC students. It was delivered once per year, with enrollments of typically 10 to 20 students. This course was required for IAC student employees, both undergraduate and graduate. This course was patterned after the AEE CEM (five-day) course for practicing professionals. IEM 4923 required each student to attend at least one on-site assessment and write at least one recommendation for their client’s report. Hence, a hands-on approach was practiced. Advance level courses were used to train graduate students. Two courses played major roles here: IEM 5923 (Advanced Energy and Water Management) and IEM 5943 (Hazardous Material and Waste). Graduate student participation in these courses helped the IAC to gain additional perspectives in on-site assessment and resulting recommendations. Numerous hands-on demonstration/training was conducted by directors and graduate students in order to gain

  5. 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.

  6. An introduction to using the FORTRAN programs provided with Computational Nuclear Physics 1 Nuclear Structure

    Science.gov (United States)

    Boytos, Matthew A.; Norbury, John W.

    1992-01-01

    The authors of this paper have provided a set of ready-to-run FORTRAN programs that should be useful in the field of theoretical nuclear physics. The purpose of this document is to provide a simple synopsis of the programs and their use. A separate section is devoted to each program set and includes: abstract; files; compiling, linking, and running; obtaining results; and a tutorial.

  7. 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.

  8. Immunohistochemical Assessment of Proliferating Cell Nuclear ...

    African Journals Online (AJOL)

    Background: Proliferating cell nuclear antigen (PCNA) is a nuclear protein synthesized in the late G1 and S‑phase of the cell cycle. ... Two sections were taken from each one for H and E. Other sections were stained according to super sensitive polymer horseradish peroxidase method for identifying PCNA expression.

  9. 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.

  10. 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.

  11. Risk-Assessment Computer Program

    Science.gov (United States)

    Dias, William C.; Mittman, David S.

    1993-01-01

    RISK D/C is prototype computer program assisting in attempts to do program risk modeling for Space Exploration Initiative (SEI) architectures proposed in Synthesis Group Report. Risk assessment performed with respect to risk events, probabilities, and severities of potential results. Enables ranking, with respect to effectiveness, of risk-mitigation strategies proposed for exploration program architecture. Allows for fact that risk assessment in early phases of planning subjective. Although specific to SEI in present form, also used as software framework for development of risk-assessment programs for other specific uses. Developed for Macintosh(TM) series computer. Requires HyperCard(TM) 2.0 or later, as well as 2 Mb of random-access memory and System 6.0.8 or later.

  12. Integrated Safety Program for the Nuclear Electric Propulsion Space Test Program

    Science.gov (United States)

    Marshall, Albert C.; Mehlman, William F.; Kompanietz, G.

    1994-07-01

    The Nuclear Electric Propulsion Space Test Program (NEPSTP) is sponsored by the Ballistic Missile Defense Office (BMDO) to demonstrate and evaluate the Russian-built TOPAZ II nuclear reactor as a power source for an electric propulsion system in space. From its inception, safety has been a central feature of the NEPSTP program. This paper addresses the work done to define the safety organizational relationships, responsibilities, management, engineering requirements, and documentation to assure an integrated safety program that coordinates the various safety activities in Mission Safety, Range Safety and Nuclear Safety. Because the United States has not launched a nuclear reactor since 1965, much of the focus of the safety program has been directed toward the unique safety considerations of using a nuclear reactor in space. Our preliminary findings indicate that the safe use of the TOPAZ II for the NEPSTP space mission is feasible.

  13. 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.

  14. 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.

  15. 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.

  16. 78 FR 35330 - Initial Test Programs for Water-Cooled Nuclear Power Plants

    Science.gov (United States)

    2013-06-12

    ... COMMISSION Initial Test Programs for Water-Cooled Nuclear Power Plants AGENCY: Nuclear Regulatory Commission... revision to Regulatory Guide (RG), 1.68, ``Initial Test Programs for Water-Cooled Nuclear Power Plants... Initial Test Programs (ITPs) for light water cooled nuclear power plants. ADDRESSES: Please refer to...

  17. Nuclear Command and Control: Current Programs and Issues

    Science.gov (United States)

    2006-05-03

    Altitude Electromagnetic Pulse ( HEMP ) and High Power Microwave (HPM) Devices: Threat Assessments, by Clay Wilson. 54 Dee Ann Divis, “Protection Not in...Some analysts argue that detonating a high altitude nuclear burst to generate EMP against the U.S. critical infrastructure might be one way that China...infrastructure, including command and control systems, through an electromagnetic pulse (EMP).53 A high altitude nuclear explosion generates an electrical

  18. U.S. Nuclear Regulatory Commission natural analogue research program

    Energy Technology Data Exchange (ETDEWEB)

    Kovach, L.A.; Ott, W.R. [Nuclear Regulatory Commission, Washington, DC (United States)

    1995-09-01

    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.

  19. A Program for Cultivating Nuclear Talent at Engineering Educational Institute in a Remote Area from Nuclear Power Plants

    Science.gov (United States)

    Takahashi, Tsuyoshi

    Recently, in Japan, the number of students who hope for finding employment at the nuclear power company has decreased as students‧ concern for the nuclear power industry decreases. To improve the situation, Ministry of Education, Culture, Sports, Science and Technology launched the program of cultivating talent for nuclear power which supports research and education of nuclear power in the academic year of 2007. Supported by the program, Kushiro College of Technology conducted several activities concerning nuclear power for about a year. The students came to be interested in nuclear engineering through these activities and its results.

  20. Sacred values and conflict over Iran's nuclear program

    Directory of Open Access Journals (Sweden)

    Morteza Dehghani

    2010-12-01

    Full Text Available Conflict over Iran's nuclear program, which involves a US-led policy to impose sanctions on Iran, is perceived by each side as a preeminent challenge to its own national security and global peace. Yet, there is little scientific study or understanding of how material incentives and disincentives, such as economic sanctions, psychologically affect the targeted population and potentially influence behaviour. Here we explore the Iranian nuclear program within a paradigm concerned with sacred values. We integrate experiments within a survey of 1997 Iranians. We find that a relatively small but politically significant portion of the Iranian population believes that acquiring nuclear energy has become a sacred value, in the sense that proposed economic incentives and disincentives result in a ``backfire effect'' in which offers of material rewards or punishment lead to increased anger and greater disapproval. This pattern was specific to nuclear energy and did not hold for acquiring nuclear weapons. The present study is the first demonstration of the backfire effect for material disincentives as well as incentives, and on an issue whose apparent sacred nature is recent rather than longstanding.

  1. Comprehensive Auditing in Nuclear Medicine Through the International Atomic Energy Agency Quality Management Audits in Nuclear Medicine (QUANUM) Program. Part 1: the QUANUM Program and Methodology.

    Science.gov (United States)

    Dondi, Maurizio; Torres, Leonel; Marengo, Mario; Massardo, Teresa; Mishani, Eyal; Van Zyl Ellmann, Annare; Solanki, Kishor; Bischof Delaloye, Angelika; Lobato, Enrique Estrada; Miller, Rodolfo Nunez; Paez, Diana; Pascual, Thomas

    2017-11-01

    An effective management system that integrates quality management is essential for a modern nuclear medicine practice. The Nuclear Medicine and Diagnostic Imaging Section of the International Atomic Energy Agency (IAEA) has the mission of supporting nuclear medicine practice in low- and middle-income countries and of helping them introduce it in their health-care system, when not yet present. The experience gathered over several years has shown diversified levels of development and varying degrees of quality of practice, among others because of limited professional networking and limited or no opportunities for exchange of experiences. Those findings triggered the development of a program named Quality Management Audits in Nuclear Medicine (QUANUM), aimed at improving the standards of NM practice in low- and middle-income countries to internationally accepted standards through the introduction of a culture of quality management and systematic auditing programs. QUANUM takes into account the diversity of nuclear medicine services around the world and multidisciplinary contributions to the practice. Those contributions include clinical, technical, radiopharmaceutical, and medical physics procedures. Aspects of radiation safety and patient protection are also integral to the process. Such an approach ensures consistency in providing safe services of superior quality to patients. The level of conformance is assessed using standards based on publications of the IAEA and the International Commission on Radiological Protection, and guidelines from scientific societies such as Society of Nuclear Medicine and Molecular Imaging (SNMMI) and European Association of Nuclear Medicine (EANM). Following QUANUM guidelines and by means of a specific assessment tool developed by the IAEA, auditors, both internal and external, will be able to evaluate the level of conformance. Nonconformances will then be prioritized and recommendations will be provided during an exit briefing. The

  2. Radiation environment assessment for nuclear inspection

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Lee, Jung Hoh; Lee, Hyun Duk; Kim, Sam Lang; Choi, Yong Hoh; Lee, Myung Hoh; Hong, Kwang Heui; Lee, Won Yoon; Park, Doo Won; Lee, Yung Bok; Han, Moon Heui; Kim, Eun Han; Suh, Kyung Suk; Hwang, Won Tae; Yoon, Suk Chul; Yoon, Yu Chang; Lee, Sang Yoon; Kim, Jong Soo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-05-01

    Environmental monitoring technology was established to trace the nuclear activities. The signature sample and nuclides around reprocessing plant were reviewed and the procedure of sampling and analyzing environmental samples were set up to detect the signatures. Alpha-spectrometry method for plutonium analysis in environmental samples was discussed. Field Trial was carried out around KAERI site to evaluate the potential of environmental method in support of safeguard activities. The results of KAERI Field Trial showed that environmental monitoring technique would be a powerful tool for nuclear inspection. 14 figs, 36 tabs, 38 refs. (Author).

  3. Advanced gas cooled nuclear reactor materials evaluation and development program

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    Results of work performed from January 1, 1977 through March 31, 1977 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Process Heat and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (impure Helium), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes progress to date on alloy selection for VHTR Nuclear Process Heat (NPH) applications and for DCHT applications. The present status on the simulated reactor helium loop design and on designs for the testing and analysis facilities and equipment is discussed.

  4. Sister Lab Program Prospective Partner Nuclear Profile: Indonesia

    Energy Technology Data Exchange (ETDEWEB)

    Bissani, M; Tyson, S

    2006-12-14

    Indonesia has participated in cooperative technical programs with the IAEA since 1957, and has cooperated with regional partners in all of the traditional areas where nuclear science is employed: in medicine, public health (such as insect control and eradication programs), agriculture (e.g. development of improved varieties of rice), and the gas and oil industries. Recently, Indonesia has contributed significantly to the Reduced Enrichment Research and Training Reactor (RERTR) Program by conducting experiments to confirm the feasibility of Mo-99 production using high-density low enriched uranium (LEU) fuel, a primary goal of the RERTR Program. Indonesia's first research reactor, the TRIGA Mark II at Bandung, began operation in 1964 at 250 kW and was subsequently upgraded in 1971 to 1 MW and further upgraded in 2000 to 2 MW. This reactor was joined by another TRIGA Mark II, the 100-kW Kartini-PPNY at Yogyakarta, in 1979, and by the 30-MW G.A. Siwabessy multipurpose reactor in Serpong, which achieved criticality in July 1983. A 10-MW radioisotope production reactor, to be called the RPI-10, also was proposed for construction at Serpong in the late 1990s, but the project apparently was not carried out. In the five decades since its nuclear research program began, Indonesia has trained a cadre of scientific and technical staff who not only operate and conduct research with the current facilities, but also represent the nucleus of a skilled labor pool to support development of a nuclear power program. Although Indonesia's previous on-again, off-again consideration of nuclear power has not gotten very far in the past, it now appears that Indonesia again is giving serious consideration to beginning a national nuclear energy program. In June 2006, Research and Technology Minister Kusmayanto Kadiman said that his ministry was currently putting the necessary procedures in place to speed up the project to acquire a nuclear power plant, indicating that, &apos

  5. Study on Nuclear Facility Cyber Security Awareness and Training Programs

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-10-15

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

  6. Seismic risk assessment as applied to the Zion Nuclear Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Wells, J.

    1984-08-01

    To assist the US Nuclear Regulatory Commission (NRC) in its licensing and evaluation role, the NRC funded the Seismic Safety Margins Research Program (SSMRP) at Lawrence Livermore National Laboratory (LLNL) with the goal of developing tools and data bases to evaluate the risk of earthquake caused radioactive release from a commercial nuclear power plant. This paper describes the SSMRP risk assessment methodology and the results generated by applying this methodology to the Zion Nuclear Generating Station. In addition to describing the failure probabilities and risk values, the effects of assumptions about plant configuration, plant operation, and dependence will be given.

  7. Commercial Nuclear Power Industry: Assessing and Meeting the Radiation Protection Workforce Needs.

    Science.gov (United States)

    Hiatt, Jerry W

    2017-02-01

    This paper will provide an overview of the process used by the commercial nuclear power industry in assessing the status of existing industry staffing and projecting future supply demand needs. The most recent Nuclear Energy Institute-developed "Pipeline Survey Results" will be reviewed with specific emphasis on the radiation protection specialty. Both radiation protection technician and health physicist specialties will be discussed. The industry-initiated Nuclear Uniform Curriculum Program will be reviewed as an example of how the industry has addressed the need for developing additional resources. Furthermore, the reality of challenges encountered in maintaining the needed number of health physicists will also be discussed.

  8. Evaluation of Haddam Neck (Connecticut Yankee) Nuclear Power Plant, environmental impact prediction, based on monitoring programs

    Energy Technology Data Exchange (ETDEWEB)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Mahaffey, J.A.; Waton, D.G.

    1976-12-01

    A study was undertaken by the U.S. Nuclear Regulatory Commission (NRC) to evaluate the nonradiological environmental data obtained from three nuclear power plants operating for a period of one year or longer. The document presented reports the second of three nuclear power plants to be evaluated in detail by Battelle, Pacific Northwest Laboratories. Haddam Neck (Connecticut Yankee) Nuclear Power Plant nonradiological monitoring data were assessed to determine their effectiveness in the measurement of environmental impacts. Efforts were made to determine if: (1) monitoring programs, as designed, can detect environmental impacts, (2) appropriate statistical analyses were performed and if they were sensitive enough to detect impacts, (3) predicted impacts could be verified by monitoring programs, and (4) monitoring programs satisfied the requirements of the Environmental Technical Specifications. Both preoperational and operational monitoring data were examined to test the usefulness of baseline information in evaluating impacts. This included an examination of the methods used to measure ecological, chemical, and physical parameters, and an assessment of sampling periodicity and sensitivity where appropriate data sets were available. From this type of analysis, deficiencies in both preoperational and operational monitoring programs may be identified and provide a basis for suggested improvement.

  9. 77 FR 73056 - Initial Test Programs for Water-Cooled Nuclear Power Plants

    Science.gov (United States)

    2012-12-07

    ... COMMISSION Initial Test Programs for Water-Cooled Nuclear Power Plants AGENCY: Nuclear Regulatory Commission...-Cooled Nuclear Power Plants.'' This guide describes the general scope and depth that the staff of the NRC considers acceptable for Initial Test Programs (ITPs) for light water cooled nuclear power plants. DATES...

  10. Assessment of nuclear power plant siting methods

    Energy Technology Data Exchange (ETDEWEB)

    Rowe, M.D.; Hobbs, B.F.; Pierce, B.L.; Meier, P.M.

    1979-11-01

    Several different methods have been developed for selecting sites for nuclear power plants. This report summarizes the basic assumptions and formal requirements of each method and evaluates conditions under which each is correctly applied to power plant siting problems. It also describes conditions under which different siting methods can produce different results. Included are criteria for evaluating the skill with which site-selection methods have been applied.

  11. Price-Anderson Nuclear Safety Enforcement Program. 1997 annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    This report summarizes activities in the Department of Energy's Price-Anderson Amendments Act (PAAA) Enforcement Program in calendar year 1997 and highlights improvements planned for 1998. The DOE Enforcement Program involves the Office of Enforcement and Investigation in the DOE Headquarters Office of Environment, Safety and Health, as well as numerous PAAA Coordinators and technical advisors in DOE Field and Program Offices. The DOE Enforcement Program issued 13 Notices of Violation (NOV`s) in 1997 for cases involving significant or potentially significant nuclear safety violations. Six of these included civil penalties totaling $440,000. Highlights of these actions include: (1) Brookhaven National Laboratory Radiological Control Violations / Associated Universities, Inc.; (2) Bioassay Program Violations at Mound / EG and G, Inc.; (3) Savannah River Crane Operator Uptake / Westinghouse Savannah River Company; (4) Waste Calciner Worker Uptake / Lockheed-Martin Idaho Technologies Company; and (5) Reactor Scram and Records Destruction at Sandia / Sandia Corporation (Lockheed-Martin).

  12. Nuclear waste treatment program: Annual report for FY 1987

    Energy Technology Data Exchange (ETDEWEB)

    Brouns, R.A.; Powell, J.A. (comps.)

    1988-09-01

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the 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 assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs.

  13. Accidental nuclear war--a post-cold war assessment.

    Science.gov (United States)

    Forrow, L; Blair, B G; Helfand, I; Lewis, G; Postol, T; Sidel, V; Levy, B S; Abrams, H; Cassel, C

    1998-04-30

    In the 1980s, many medical organizations identified the prevention of nuclear war as one of the medical profession's most important goals. An assessment of the current danger is warranted given the radically changed context of the post-Cold War era. We reviewed the recent literature on the status of nuclear arsenals and the risk of nuclear war. We then estimated the likely medical effects of a scenario identified by leading experts as posing a serious danger: an accidental launch of nuclear weapons. We assessed possible measures to reduce the risk of such an event. U.S. and Russian nuclear-weapons systems remain on a high-level alert status. This fact, combined with the aging of Russian technical systems, has recently increased the risk of an accidental nuclear attack. As a conservative estimate, an accidental intermediate-sized launch of weapons from a single Russian submarine would result in the deaths of 6,838,000 persons from firestorms in eight U.S. cities. Millions of other people would probably be exposed to potentially lethal radiation from fallout. An agreement to remove all nuclear missiles from high-level alert status and eliminate the capability of a rapid launch would put an end to this threat. The risk of an accidental nuclear attack has increased in recent years, threatening a public health disaster of unprecedented scale. Physicians and medical organizations should work actively to help build support for the policy changes that would prevent such a disaster.

  14. The Nuclear Astrophysics program at n_TOF (CERN

    Directory of Open Access Journals (Sweden)

    Colonna N.

    2017-01-01

    Full Text Available An important experimental program on Nuclear Astrophysics is being carried out at the n_TOF since several years, in order to address the still open issues in stellar and primordial nucleosynthesis. Several neutron capture reactions relevant to s-process nucleosynthesis have been measured so far, some of which on important branching point radioisotopes. Furthermore, the construction of a second experimental area has recently opened the way to challenging measurements of (n, charged particle reactions on isotopes of short half-life. The Nuclear Astrophysics program of the n_TOF Collaboration is here described, with emphasis on recent results relevant for stellar nucleosynthesis, stellar neutron sources and primordial nucleosynthesis.

  15. Development of an automated fracture assessment system for nuclear structures (appendix 1/1)

    Science.gov (United States)

    Mikkola, Timo P. J.; Raiko, Heikki

    1992-10-01

    A program system for fracture assessment of nuclear power plant structures was developed. The system consists of a program for engineering analysis and an automated finite element program system for accurate analysis with solid three dimensional models. The VTTSIF (Technical Research Center of Finland Stress Intensity Factor) program for engineering fracture assessment applies either the weight function method or superposition method in calculating the stress intensity factor. The fatigue crack growth analysis is based on the Paris equation. The generation of a three dimensional finite element model of a cracked structure is automated by the ACR (automatic finite element model generation for part through cracks) program. The finite element analyses are created with commercial programs. The virtual crack extension method is used for fracture parameter evaluation by the VTTVIRT postprocessor program (program for J-integral evaluation using virtual crack extension method). The test cases demonstrated that the accuracy of the system is satisfactory.

  16. The J-PARC project-strangeness nuclear physics programs

    CERN Document Server

    Nagae, T

    2005-01-01

    Since Japanese fiscal year JFY01, which started on April 1, 2001, the Japan Proton Accelerator Research Complex (J-PARC) has been in construction under a cooperation of two institutions, KEK and Japan Atomic Energy Research Institute (JAERI). After a short introduction of the whole project, I will report on the current status of the construction. Then, I describe the initial programs on strangeness nuclear physics at J-PARC, in detail.

  17. Occupational exposure assessment: Practices in Malaysian nuclear agency

    Energy Technology Data Exchange (ETDEWEB)

    Sarowi, S. Muhd, E-mail: suzie@nuclearmalaysia.gov.my; Ramli, S. A.; Kontol, K. Mohamad [Radiation Safety & Health Division, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia); Rahman, N. A. H. Abd. [Faculty of Science & Mathematics, Sultan Idris of Education Universit, 35900, Tanjong Malim, Perak Darul Ridzuan (Malaysia)

    2016-01-22

    Malaysian Nuclear Agency (Nuclear Malaysia) is the leading agency in introducing and promoting the application of nuclear science technology in Malaysia. The agency provides major nuclear facilities purposely for research and commercialisation such as reactor, irradiation plants and radioisotope production laboratory. When dealing with ionizing radiation, there is an obligatory requirement to monitor and assess the radiation exposure to the workers. The personal dose of radiation workers were monitored monthly by assessing their Thermoluminescence Dosimeter (TLD) dose reading. This paper will discuss the current practice in managing, assessing, record keeping and reporting of the occupational exposure in Nuclear Malaysia including the Health Physic Group roles and challenges. The statistics on occupational radiation exposure of monitored workers working in different fields in Nuclear Malaysia from 2011 - 2013 will also be presented. The results show that the null hypothesis (H{sub 0}) was accepted which the means of every populations are all equal or not differ significantly. This hypothesis states that the dose exposure received by the radiation workers in Nuclear Malaysia is similar and there were no significant changes from 2011 to 2013. The radiation monitoring programme correlate with the requirement of our national law, the Atomic Energy Licensing Act 1984 (Act 304)

  18. Occupational exposure assessment: Practices in Malaysian nuclear agency

    Science.gov (United States)

    Sarowi, S. Muhd; Ramli, S. A.; Kontol, K. Mohamad; Rahman, N. A. H. Abd.

    2016-01-01

    Malaysian Nuclear Agency (Nuclear Malaysia) is the leading agency in introducing and promoting the application of nuclear science technology in Malaysia. The agency provides major nuclear facilities purposely for research and commercialisation such as reactor, irradiation plants and radioisotope production laboratory. When dealing with ionizing radiation, there is an obligatory requirement to monitor and assess the radiation exposure to the workers. The personal dose of radiation workers were monitored monthly by assessing their Thermoluminescence Dosimeter (TLD) dose reading. This paper will discuss the current practice in managing, assessing, record keeping and reporting of the occupational exposure in Nuclear Malaysia including the Health Physic Group roles and challenges. The statistics on occupational radiation exposure of monitored workers working in different fields in Nuclear Malaysia from 2011 - 2013 will also be presented. The results show that the null hypothesis (H₀) was accepted which the means of every populations are all equal or not differ significantly. This hypothesis states that the dose exposure received by the radiation workers in Nuclear Malaysia is similar and there were no significant changes from 2011 to 2013. The radiation monitoring programme correlate with the requirement of our national law, the Atomic Energy Licensing Act 1984 (Act 304).

  19. Nuclear Safety Culture Assessment for a Newcomer Country: Case Study of Jordan

    Energy Technology Data Exchange (ETDEWEB)

    Khasawneh, Khalid; Park, Yun Woon [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    For countries initiating or considering to start their nuclear power programs; developing a successful safety culture is of a great challenge, owing to lack of experience and the sensitive nature of the nuclear industry in general. The Jordanian case was chosen since Jordan is in the early stages of its nuclear program and the establishment of an effective safety culture is crucial to guarantee the safe operation of its future nuclear facilities. It also should be noted that Fukushima accident has adversely affected the progress of the Jordanian nuclear program driven by the negative public opinion. The government shifts the policies toward enhancing the nuclear safety by enforcing the communication between the engaged parties and openness and transparency with public. In the wake of Fukushima accident the Jordanian government reassured the appropriate siting criteria and siting review, the leadership and the organizations commitment to nuclear safety by adopting advanced reactor technology, the consideration of modern operator accident mitigation strategies and the increased and close cooperation with IAEA and adherence to evolving international safety standards. The progress in the Jordanian nuclear power project in order to satisfy the IAEA requirements was quantified and ranked. A good progress was shown in some aspects, for example in the multicultural and multi-national elements and the establishment of an independent and effective regulatory body. However, some elements, concerning the understanding of the safety culture, management system of the regulatory body and the cultural assessment was not satisfied and an urgent need to focus on and enhance those aspects are required by the Jordanian government. Some elements, for example the leadership, communication and competence, have partial fulfillment of the IAEA requirements. However enhancing those aspects is required in the short and the mid-term in order to guarantee a well-established nuclear power

  20. Reliability program requirements for Space and Terrestrial Nuclear Power Systems

    Energy Technology Data Exchange (ETDEWEB)

    1982-10-01

    The objectives of the reliability program requirements described in this report are (1) to provide contractors with an outline of the reliability requirements established by the Department of Energy (DOE) in the areas of design, development, production, testing, and acceptance of space and terrestrial nuclear systems hardware, and (2) to guide the contractor in meeting these requirements. This publication or particular portions of it is applicable as specified in the contract. Whether the contractors/subcontractors are subject to all the requirements or only to part of them will be specified by contract, program letter, or by the contract statement-of-work.

  1. Seismic Qualification Program Plan for continued operation at DOE-SRS Nuclear Material Processing facilities

    Energy Technology Data Exchange (ETDEWEB)

    Talukdar, B.K.; Kennedy, W.N.

    1991-12-31

    The Savannah River Facilities for the most part were constructed and maintained to standards that were developed by Du Pont and are not rigorously in compliance with the current General Design Criteria (GDC); DOE Order 6430.1A requirements. In addition, any of the facilities were built more than 30 years ago, well before DOE standards for design were issued. The Westinghouse Savannah River Company (WSRC) has developed a program to address the evaluation of the Nuclear Material Processing (NMP) facilities to GDC requirements. The program includes a facility base-line review, assessment of areas that are not in compliance with the GDC requirements, planned corrective actions or exemptions to address the requirements, and a safety assessment. The authors from their direct involvement with the Program, describe the program plan for seismic qualification including other natural phenomena hazards for existing NMP facility structures to continue operation. Professionals involved in similar effort at other DOE facilities may find the program useful.

  2. Seismic Qualification Program Plan for continued operation at DOE-SRS Nuclear Material Processing facilities

    Energy Technology Data Exchange (ETDEWEB)

    Talukdar, B.K.; Kennedy, W.N.

    1991-01-01

    The Savannah River Facilities for the most part were constructed and maintained to standards that were developed by Du Pont and are not rigorously in compliance with the current General Design Criteria (GDC); DOE Order 6430.1A requirements. In addition, any of the facilities were built more than 30 years ago, well before DOE standards for design were issued. The Westinghouse Savannah River Company (WSRC) has developed a program to address the evaluation of the Nuclear Material Processing (NMP) facilities to GDC requirements. The program includes a facility base-line review, assessment of areas that are not in compliance with the GDC requirements, planned corrective actions or exemptions to address the requirements, and a safety assessment. The authors from their direct involvement with the Program, describe the program plan for seismic qualification including other natural phenomena hazards for existing NMP facility structures to continue operation. Professionals involved in similar effort at other DOE facilities may find the program useful.

  3. Final report to DOE: Matching Grant Program for the Penn State University Nuclear Engineering Program

    Energy Technology Data Exchange (ETDEWEB)

    Jack S. Brenizer, Jr.

    2003-01-17

    The DOE/Industry Matching Grant Program is designed to encourage collaborative support for nuclear engineering education as well as research between the nation's nuclear industry and the U.S. Department of Energy (DOE). Despite a serious decline in student enrollments in the 1980s and 1990s, the discipline of nuclear engineering remained important to the advancement of the mission goals of DOE. The program is designed to ensure that academic programs in nuclear engineering are maintained and enhanced in universities throughout the U.S. At Penn State, the Matching Grant Program played a critical role in the survival of the Nuclear Engineering degree programs. Funds were used in a variety of ways to support both undergraduate and graduate students directly. Some of these included providing seed funding for new graduate research initiatives, funding the development of new course materials, supporting new teaching facilities, maintenance and purchase of teaching laboratory equipment, and providing undergraduate scholarships, graduate fellowships, and wage payroll positions for students.

  4. Nuclear fuel cycle assessment of India: A technical study for U.S.-India cooperation

    Science.gov (United States)

    Krishna, Taraknath Woddi Venkat

    The recent civil nuclear cooperation proposed by the Bush Administration and the Government of India has heightened the necessity of assessing India's nuclear fuel cycle inclusive of nuclear materials and facilities. This agreement proposes to change the long-standing U.S. policy of preventing the spread of nuclear weapons by denying nuclear technology transfer to non-NPT signatory states. The nuclear tests in 1998 have convinced the world community that India would never relinquish its nuclear arsenal. This has driven the desire to engage India through civilian nuclear cooperation. The cornerstone of any civilian nuclear technological support necessitates the separation of military and civilian facilities. A complete nuclear fuel cycle assessment of India emphasizes the entwinment of the military and civilian facilities and would aid in moving forward with the separation plan. To estimate the existing uranium reserves in India, a complete historical assessment of ore production, conversion, and processing capabilities was performed using open source information and compared to independent reports. Nuclear energy and plutonium production (reactor- and weapons-grade) was simulated using declared capacity factors and modern simulation tools. The three-stage nuclear power program entities and all the components of civilian and military significance were assembled into a flowsheet to allow for a macroscopic vision of the Indian fuel cycle. A detailed view of the nuclear fuel cycle opens avenues for technological collaboration. The fuel cycle that grows from this study exploits domestic thorium reserves with advanced international technology and optimized for the existing system. To utilize any appreciable fraction of the world's supply of thorium, nuclear breeding is necessary. The two known possibilities for production of more fissionable material in the reactor than is consumed as fuel are fast breeders or thermal breeders. This dissertation analyzes a thermal

  5. Evaluation and assessment of nuclear power plant seismic methodology

    Energy Technology Data Exchange (ETDEWEB)

    Bernreuter, D.; Tokarz, F.; Wight, L.; Smith, P.; Wells, J.; Barlow, R.

    1977-03-01

    The major emphasis of this study is to develop a methodology that can be used to assess the current methods used for assuring the seismic safety of nuclear power plants. The proposed methodology makes use of system-analysis techniques and Monte Carlo schemes. Also, in this study, we evaluate previous assessments of the current seismic-design methodology.

  6. U.S. Nuclear Weapons Modernization - the Stockpile Life Extension Program

    Science.gov (United States)

    Cook, Donald

    2016-03-01

    Underground nuclear testing of U.S. nuclear weapons was halted by President George H.W. Bush in 1992 when he announced a moratorium. In 1993, the moratorium was extended by President Bill Clinton and, in 1995, a program of Stockpile Stewardship was put in its place. In 1996, President Clinton signed the Comprehensive Nuclear Test Ban Treaty (CTBT). Twenty years have passed since then. Over the same time, the average age of a nuclear weapon in the stockpile has increased from 6 years (1992) to nearly 29 years (2015). At its inception, achievement of the objectives of the Stockpile Stewardship Program (SSP) appeared possible but very difficult. The cost to design and construct several large facilities for precision experimentation in hydrodynamics and high energy density physics was large. The practical steps needed to move from computational platforms of less than 100 Mflops/sec to 10 Teraflops/sec and beyond were unknown. Today, most of the required facilities for SSP are in place and computational speed has been increased by more than six orders of magnitude. These, and the physicists and engineers in the complex of labs and plants within the National Nuclear Security Administration (NNSA) who put them in place, have been the basis for underpinning an annual decision, made by the weapons lab directors for each of the past 20 years, that resort to underground nuclear testing is not needed for maintaining confidence in the safety and reliability of the U.S stockpile. A key part of that decision has been annual assessment of the physical changes in stockpiled weapons. These weapons, quite simply, are systems that invariably and unstoppably age in the internal weapon environment of radioactive materials and complex interfaces of highly dissimilar organic and inorganic materials. Without an ongoing program to rebuild some components and replace other components to increase safety or security, i.e., life extending these weapons, either underground testing would again be

  7. Nuclear Technology Programs semiannual progress report, October 1988--March 1989

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, J.E. [ed.

    1990-12-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1988--March 1989. 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 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 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. 127 refs., 76 figs., 103 tabs.

  8. The Soviet Program for Peaceful Uses of Nuclear Explosions

    Energy Technology Data Exchange (ETDEWEB)

    Nordyke, M.D.

    2000-07-26

    During a period of some 23 years between 1965 and 1988, the Soviet Union's ''Program for the Utilization of Nuclear Explosions in the National Economy'' carried out 122 nuclear explosions to study and put into industrial use some 13 applications. In all, 128 explosives with yields ranging from 0.01 to 140 kt were used, with the vast majority being between 2 and 20 kt. Most peaceful applications of nuclear explosions in the Soviet PNE Program were explored in depth with a number of tests, but unfortunately little has been reported on the technical results other than general outcomes. Two applications, deep seismic sounding of the Earth's crust and upper mantle and the creation of underground cavities in salt for the storage of gas condensate, found widespread use, representing over 50% of all the explosions. Explosions to explore the technical possibilities of stimulating the production of oil and gas reservoirs accounted for an additional 17%.

  9. Nuclear technology programs; Semiannual progress report, October 1989--March 1990

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, J.E. [ed.

    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&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.

  10. Nuclear technology programs. Semiannual progress report, April--September 1991

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April through September 1991. 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 in a light water reactor, the thermophysical properties of the metal fuel in 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. 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.

  11. Nuclear Technology Programs semiannual progress report, April-- September 1990

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, J.E. (ed.)

    1992-06-01

    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 1990. 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 in a light water reactor, the thermophysical properties of the metal fuel in 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. 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.

  12. Nuclear Technology Programs semiannual progress report, April-- September 1990

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, J.E. [ed.

    1992-06-01

    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 1990. 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 in a light water reactor, the thermophysical properties of the metal fuel in 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. 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.

  13. Nuclear Technology Programs semiannual progress report, October 1990--March 1991

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-12-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1990--March 1991. 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 transpose of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in 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. 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.

  14. Assessment of government tribology programs

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, M.B.; Levinson, T.M.

    1985-09-01

    An assessment has been made to determine current tribology research and development work sponsored or conducted by the government. Data base surveys and discussions were conducted to isolate current projects sponsored primarily by 21 different government organizations. These projects were classified by subject, objective, energy relevance, type of research, phenomenon being investigated, variables being studied, type of motion, materials and application. An abstract of each project was prepared which included the classification, sponsor, performing organization and a project description. It was found that current work is primarily materials oriented to meet military requirements. Other than the high temperature programs very few of the tribology projects accomplish energy related objectives.

  15. Survey of Dynamic Simulation Programs for Nuclear Fuel Reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Troy J. Tranter; Daryl R. Haefner

    2008-06-01

    The absence of any industrial scale nuclear fuel reprocessing in the U.S. has precluded the necessary driver for developing the advanced simulation capability now prevalent in so many other industries. Modeling programs to simulate the dynamic behavior of nuclear fuel separations and processing were originally developed to support the US government’s mission of weapons production and defense fuel recovery. Consequently there has been little effort is the US devoted towards improving this specific process simulation capability during the last two or three decades. More recent work has been focused on elucidating chemical thermodynamics and developing better models of predicting equilibrium in actinide solvent extraction systems. These equilibrium models have been used to augment flowsheet development and testing primarily at laboratory scales. The development of more robust and complete process models has not kept pace with the vast improvements in computational power and user interface and is significantly behind simulation capability in other chemical processing and separation fields.

  16. The ENSDF_toolbox program package: tool for the evaluator of nuclear data

    OpenAIRE

    Shulyak, G. I.; A. A. Rodionov

    2010-01-01

    The program package for the work with the Evaluated Nuclear Structure Data File is discussed. The program shell designed for the unification of the process of the evaluation of the nuclear data is proposed. This program shell may be used in the regular work of the nuclear data evaluator and for common use by scientists and engineers who need the actual data about nuclear states and transitions from the ENSDF database.

  17. The Iranian Nuclear Crisis: An Assessment

    Science.gov (United States)

    2013-01-01

    weapons program which the Shah started before the revolution. His suc- cessor, Ayatollah Khamenei issued a fatwa (religious edict) in 1995 that considered...Eurodif was founded as a joint venture of Belgium, France, Iran, Italy, and Spain. The Shah invested $1 billion in the company. This invest- ment made...www.washingtonmonthly.com; and Reza Marashi, “America’s Real Iran Problem,” The New York Times, November 10, 2011. 8 Barack Obama, “Transcript of Obama’s

  18. Management of National Nuclear Power Programs for assured safety

    Energy Technology Data Exchange (ETDEWEB)

    Connolly, T.J. (ed.)

    1985-01-01

    Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

  19. On the pursuit of a nuclear development capability: The case of the Cuban nuclear program

    Science.gov (United States)

    Benjamin-Alvarado, Jonathan Calvert

    1998-09-01

    While there have been many excellent descriptive accounts of modernization schemes in developing states, energy development studies based on prevalent modernization theory have been rare. Moreover, heretofore there have been very few analyses of efforts to develop a nuclear energy capability by developing states. Rarely have these analyses employed social science research methodologies. The purpose of this study was to develop a general analytical framework, based on such a methodology to analyze nuclear energy development and to utilize this framework for the study of the specific case of Cuba's decision to develop nuclear energy. The analytical framework developed focuses on a qualitative tracing of the process of Cuban policy objectives and implementation to develop a nuclear energy capability, and analyzes the policy in response to three models of modernization offered to explain the trajectory of policy development. These different approaches are the politically motivated modernization model, the economic and technological modernization model and the economic and energy security model. Each model provides distinct and functionally differentiated expectations for the path of development toward this objective. Each model provides expected behaviors to external stimuli that would result in specific policy responses. In the study, Cuba's nuclear policy responses to stimuli from domestic constraints and intensities, institutional development, and external influences are analyzed. The analysis revealed that in pursuing the nuclear energy capability, Cuba primarily responded by filtering most of the stimuli through the twin objectives of economic rationality and technological advancement. Based upon the Cuban policy responses to the domestic and international stimuli, the study concluded that the economic and technological modernization model of nuclear energy development offered a more complete explanation of the trajectory of policy development than either the

  20. Sister Lab Program Prospective Partner Nuclear Profile: Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    Bissani, M; Tyson, S

    2006-12-14

    Vietnam's nuclear program began in the 1960s with the installation at Dalat of a 250 kW TRIGA Mk-II research reactor under the U.S. Atoms for Peace Program. The reactor was shut down and its core removed only a few years later, and the nuclear research program was suspended until after the end of the civil war in the late 1970s. The Soviet Union assisted Vietnam in restoring the Dalat reactor to an operational status in 1984, trained a cadre of scientific and technical staff in its operation, and contributed to the development of nuclear science for the medical and agricultural sectors. In the agricultural area in particular, Vietnamese experts have been very successful in developing mutant strains of rice, and continue to work with the IAEA to yield strains that have a shorter growing period, increased resistance to disease, and other desirable characteristics. Rice has always been the main crop in Vietnam, but technical cooperation with the IAEA and other states has enabled the country to become one of the top rice producers in the world, exporting much of its annual crop to over two dozen countries annually. More recently, Vietnam's government has shown increasing interest in developing a civil nuclear program to supplement its fossil fuel and other energy resources. Projections from a variety of open sources, ranging from the IAEA, the U.S. Department of Energy's Energy Information Administration (EIA), the Vietnamese government, energy corporations, and think tanks all predict a massive increase in energy consumption--especially electricity--within Vietnam and the region as a whole. This growth in consumption will require a corresponding increase in energy production, which in Vietnam is currently satisfied mainly by fossil fuels (coal) and renewable energy (hydropower and biomass); Vietnam has a refining capacity of about 800 barrels/day. Most of its crude oil is exported to generate export income, and is not used to generate electricity

  1. Auditing nuclear weapons quality programs at Los Alamos

    Energy Technology Data Exchange (ETDEWEB)

    Davis, A.H.

    1988-01-01

    Some of the problems involved in introducing quality assurance on a broad scale in a national laboratory are discussed. A philosophy of how QA can be utilized beneficially in research and development activities is described briefly, and our experiences at Los Alamos in applying QA to nuclear weapons activities are outlines. The important role of audits is emphasized; audits are used not merely to determine the effectiveness of QA programs but also to explain and demonstrate the usefulness of QA to a generally sceptical body of engineers and scientists. Finally, some ways of easing the application of QA in the future are proposed. 1 ref.

  2. Office of Nuclear Energy Knowledge Management Program Situational Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Kimberlyn C. Mousseau

    2011-12-01

    Knowledge management (KM) has been a high priority for the Department of Energy (DOE) Office of Nuclear Energy (NE) for the past several years. NE Programs are moving toward well-established knowledge management practices and a formal knowledge management program has been established. Knowledge management is being practiced to some level within each of the NE programs. Although it continues to evolve as NE programs evolve, a formal strategic plan that guides the implementation of KM has been developed. Despite the acceptance of KM within DOE NE, more work is necessary before the NE KM program can be considered fully successful. Per Dr. David J. Skyrme[1], an organization typically moves through the following evolutionary phases: (1) Ad-hoc - KM is being practiced to some level in some parts of the organization; (2) Formal - KM is established as a formal project or program; (3) Expanding - the use of KM as a discipline grows in practice across different parts of the organization; (4) Cohesive - there is a degree of coordination of KM; (5) Integrated - there are formal standards and approaches that give every individual access to most organizational knowledge through common interfaces; and (6) Embedded - KM is part-and-parcel of everyday tasks; it blends seamlessly into the background. According to the evolutionary phases, the NE KM program is operating at the two lower levels, Ad-hoc and Formal. Although KM is being practiced to some level, it is not being practiced in a consistent manner across the NE programs. To be fully successful, more emphasis must be placed on establishing KM standards and processes for collecting, organizing, sharing and accessing NE knowledge. Existing knowledge needs to be prioritized and gathered on a routine basis, its existence formally recorded in a knowledge inventory. Governance to ensure the quality of the knowledge being used must also be considered. For easy retrieval, knowledge must be organized according to a taxonomy that

  3. Current Status of the Cyber Threat Assessment for Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Doo [KINAC, Daejeon (Korea, Republic of)

    2016-05-15

    In December 2014, unknown hackers hacked internal documents sourced from Korea Hydro and Nuclear Power (KHNP) and those electronic documents were posted five times on a Social Network Service (SNS). The data included personal profiles, flow charts, manuals and blueprints for installing pipes in the nuclear power plant. Although the data were not critical to operation or sabotage of the plant, it threatened people and caused social unrest in Korea and neighboring countries. In December 2015, cyber attack on power grid caused a blackout for hundreds of thousands of people in Ukraine. The power outage was caused by a sophisticated attack using destructive malware called 'BlackEnergy'. Cyber attacks are reality in today's world and critical infrastructures are increasingly targeted. Critical infrastructures, such as the nuclear power plant, need to be proactive and protect the nuclear materials, assets and facilities from potential cyber attacks. The threat assessment document and its detailed procedure are confidential for the State. Nevertheless, it is easy to find cooperation on assessing and evaluating the threats of nuclear materials and facilities with other government departments or agencies including the national police. The NSSC and KINAC also cooperated with the National Intelligence Service (NIS) and National Security Research Institute (NSR). However, robust cyber threat assessment system and regular consultative group should be established with domestic and overseas organization including NIS, NSR, the National Police Agency and the military force to protect and ensure to safety of people, public and environment from rapidly changing and upgrading cyber threats.

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

    Energy Technology Data Exchange (ETDEWEB)

    Martha R. Finck Ph.D.

    2011-10-01

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

  5. Next Generation Nuclear Plant Materials Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for

  6. Structural Aging Program to evaluate continued performance of safety-related concrete structures in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Naus, D.J.; Oland, C.B. [Oak Ridge National Lab., TN (United States); Ellingwood, B.R. [Johns Hopkins Univ., Baltimore, MD (United States)

    1994-03-01

    This report discusses the Structural Aging (SAG) Program which is being conducted at the Oak Ridge National Laboratory (ORNL) for the United States Nuclear Regulatory commission (USNRC). The SAG Program is addressing the aging management of safety-related concrete structures in nuclear power plants for the purpose of providing improved technical bases for their continued service. The program is organized into three technical tasks: Materials Property Data Base, Structural Component Assessment/Repair Technologies, and Quantitative Methodology for continued Service Determinations. Objectives and a summary of recent accomplishments under each of these tasks are presented.

  7. In-field analysis and assessment of nuclear material

    Energy Technology Data Exchange (ETDEWEB)

    Morgado, R.E.; Myers, W.S.; Olivares, J.A.; Phillips, J.R.; York, R.L.

    1996-05-01

    Los Alamos National Laboratory has actively developed and implemented a number of instruments to monitor, detect, and analyze nuclear materials in the field. Many of these technologies, developed under existing US Department of Energy programs, can also be used to effectively interdict nuclear materials smuggled across or within national borders. In particular, two instruments are suitable for immediate implementation: the NAVI-2, a hand-held gamma-ray and neutron system for the detection and rapid identification of radioactive materials, and the portable mass spectrometer for the rapid analysis of minute quantities of radioactive materials. Both instruments provide not only critical information about the characteristics of the nuclear material for law-enforcement agencies and national authorities but also supply health and safety information for personnel handling the suspect materials.

  8. From Risk Analysis to the Safety Case. Values in Risk Assessments. A Report Based on Interviews with Experts in the Nuclear Waste Programs in Sweden and Finland. A Report from the RISCOM II Project

    Energy Technology Data Exchange (ETDEWEB)

    Drottz Sjoeberg, Britt-Marie [Norwegian Univ. of Science and Technology, Trondheim (Norway). Dept. of Psychology

    2004-06-01

    The report focuses on values in risk assessment, and is based on interviews with safety assessment experts and persons working at the national authorities in Sweden and Finland working in the area of nuclear waste management. The interviews contained questions related to definitions of risk and safety, standards, constraints and degrees of freedom in the work, data collections, reliability and validity of systems and the safety assessments, as well as communication between experts, and experts and non-experts. The results pointed to an increased amount of data and relevant factors considered in the analyses over time, changing the work content and process from one of risk analysis to a multifaceted teamwork towards the assessment of 'the safety case'. The multifaceted systems approach highlighted the increased importance of investigating assumptions underlying e.g. integration of diverse systems, and simplification procedures. It also highlighted the increased reliance on consensus building processes within the extended expert group, the importance of adequate communication abilities within the extended expert group, as well as the importance of transparency and communication relative the larger society. The results are discussed with reference to e.g. Janis 'groupthink' theory and Kuhns ideas of paradigmatic developments in science. It is concluded that it is well advised, in addition to the ordinary challenges of the work, to investigate also the implicit assumptions involved in the work processes to further enhance the understanding of safety assessments.

  9. Integrated safety assessment of Indian nuclear power plants for ...

    Indian Academy of Sciences (India)

    Classically the nuclear power reactor design and system evolution has been based on the logic of minimization of risk to an acceptable level and its quantification based on a deterministic approach and backed up by a further assessment based on the probabilistic methodology. However, in spite of minimization of risk, the ...

  10. Self-Reliability and Motivation in a Nuclear Security Culture Enhancement Program

    Energy Technology Data Exchange (ETDEWEB)

    Crawford,C.; de Boer,G.; De Castro, K; Landers, Ph.D., J; Rogers, E

    2009-10-19

    The threat of nuclear terrorism has become a global concern. Many countries continue to make efforts to strengthen nuclear security by enhancing systems of nuclear material protection, control, and accounting (MPC&A). Though MPC&A systems can significantly upgrade nuclear security, they do not eliminate the "human factor." This paper will describe some of the key elements of a comprehensive, sustainable nuclear security culture enhancement program and how implementation can mitigate the insider threat.

  11. Next Generation Nuclear Plant Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented

  12. National Nuclear Security Administration International Safeguards Education & Training Program(s)

    Energy Technology Data Exchange (ETDEWEB)

    Frazar, Sarah L.; McClelland-Kerr, John

    2009-10-06

    The introduction of nuclear power is a challenging, time-consuming and complex endeavor. After lengthy deliberations and research, some discover they are not prepared to take on the responsibilities or make the necessary investments to pursue nuclear power at this time. In particular, as countries begin to study their education systems with a critical eye, they discover they are unlikely to produce the requisite people to support the new plant they had hoped to introduce in the next ten to fifteen years. Without experienced personnel who can manage, operate, regulate and inspect the new plant, there is no point to building a plant in the first place. This paper will begin with an overview of various challenges associated with establishing and implementing a safe, secure and sustainable nuclear program and describe the some of the key issues that need to be addressed while planning to introduce nuclear power into an energy portfolio. Subsequent sections will describe how the United States is assisting countries in this planning process and in developing an effective workforce capable of supporting the nuclear program. Next, the paper will look at the key documents countries need to prepare in order to develop an effective workforce. The final section will offer some potential measures for success to ensure the long-term viability of the education system.

  13. Probabilistic safety assessment in the chemical and nuclear industries

    CERN Document Server

    Fullwood, Ralph R

    2000-01-01

    Probabilistic Safety Analysis (PSA) determines the probability and consequences of accidents, hence, the risk. This subject concerns policy makers, regulators, designers, educators and engineers working to achieve maximum safety with operational efficiency. Risk is analyzed using methods for achieving reliability in the space program. The first major application was to the nuclear power industry, followed by applications to the chemical industry. It has also been applied to space, aviation, defense, ground, and water transportation. This book is unique in its treatment of chemical and nuclear risk. Problems are included at the end of many chapters, and answers are in the back of the book. Computer files are provided (via the internet), containing reliability data, a calculator that determines failure rate and uncertainty based on field experience, pipe break calculator, event tree calculator, FTAP and associated programs for fault tree analysis, and a units conversion code. It contains 540 references and many...

  14. Development of Computer-Aided Learning Programs on Nuclear Nonproliferation and Control

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Chul [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2011-10-15

    The fulfillment of international norms for nuclear nonproliferation is indispensable to the promotion of nuclear energy. The education and training for personnel and mangers related to the nuclear material are one of crucial factors to avoid unintended non-compliance to international norms. Korea Institute of Nuclear Nonproliferation and Control (KINAC) has been providing education and training on nuclear control as its legal duty. One of the legally mandatory educations is 'nuclear control education' performed since 2006 for the observation of the international norms on nuclear nonproliferation and the spread of the nuclear control culture. The other is 'physical protection education' performed since 2010 for maintaining the national physical protection regime effectively and the spread of the nuclear security culture. The 2010 Nuclear Security Summit was held in Washington, DC to enhance international cooperation to prevent nuclear terrorism. During the Summit, the South Korea was chosen to host the second Nuclear Summit in 2012. South Korean President announced that South Korea would share its expertise and support the Summit's mission by setting up an international education and training center on nuclear security in 2014. KINAC is making a full effort to set up the center successfully. An important function of the center is education and training in the subjects of nuclear nonproliferation, nuclear safeguards, nuclear security, and nuclear export/import control. With increasing importance of education and training education on nuclear nonproliferation and control, KINAC has been developing computer-aided learning programs on nuclear nonproliferation and control to overcome the weaknesses in classroom educations. This paper shows two learning programs. One is an e-learning system on the nuclear nonproliferation and control and the other is a virtual reality program for training nuclear material accountancy inspection of light water

  15. Environmental assessment strategies in support of the Nonproliferation alternative systems assessment program (NASAP)

    Energy Technology Data Exchange (ETDEWEB)

    Emery, R.M.; Warner, M.L.; Meyer, H.R.; Little, C.A.; Till, J.E.

    1977-10-01

    The U.S. Department of Energy (DOE) is currently conducting a Nonproliferation Alternative Systems Assessment Program (NASAP) to identify nuclear fuel cycle options that pose inherently low risks of nuclear weapons proliferation while retaining the major benefits of nuclear energy. During FY 1978, the desirability and effectiveness of alternative nuclear fuel cycles will be examined in terms of the cycles' proliferation risk, technical feasibility, economic feasibility, and potential environmental and health effects. Final recommendations based on these several assessments may be made late in FY 1978. Carefully planned, highly efficient research strategies will be required to complete the necessary assessments within the anticipated time frame. The purpose of this report is to identify and evaluate alternative strategies for organizing the environmental and health (E and H) effects assessment. Following a brief review of the range of alternative nuclear fuel cycles under consideration, the report consists of three major sections. A discussion of what presently appear to be the most significant environmental and health issues associated with alternative fuel cycles is presented in Section 2. Major choice points in developing an effective assessment strategy, and the range of options available at each, are identified and evaluated in Section 3. Section 4 summarizes conclusions and recommends courses of action for proceeding with the detailed NASAP environmental assessment.

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

    Energy Technology Data Exchange (ETDEWEB)

    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. (LEW)

  17. Basic data for integrated assessment of nuclear fuel cycle system

    Energy Technology Data Exchange (ETDEWEB)

    Nomura, Yasushi; Tamaki, Hitoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Ito, Chihiro; Saegusa, Toshiari [Central Research Inst. of Electric Power Industry, Tokyo (Japan)

    2001-03-01

    In our country, where natural energy resources such as oil and coal are scarce, it is vital to establish a nuclear fuel cycle to reprocess spent fuel and reuse valuable nuclear fuel in electric power generation reactors. However spent fuel is now being accumulated too much so that, for the time being, it is necessary to establish a system for tentatively storing spent fuel. In this report, in order to deal with these issues, evaluation methods, which were developed, prepared and discussed by Japan Atomic Energy Research Institute (JAERI) and Central Research Institute of Electric Power Industry (CRIEPI), are rendered together with sample results of their application. Also reported is some important information on the data and methods for the safety assessment of nuclear fuel cycle facilities, which have been surveyed by JAERI and CRIEPI. (author)

  18. The Soviet program for peaceful uses of nuclear explosions

    Energy Technology Data Exchange (ETDEWEB)

    Nordyke, M.D.

    1996-07-24

    The concept of utilizing the weapons of war to serve the peaceful pursuits of mankind is as old as civilization itself. Perhaps the most famous reference to this basic desire is recorded in the Book of Micah where the great prophet Isiah called upon his people `to turn your spears into pitchforks and your swords into plowshares.` As the scientists at Los Alamos worked on developing the world`s first atomic bomb, thoughts of how this tremendous new source of energy could be used for peaceful purposes generally focused on using the thermal energy generated by the slow fission of uranium in a reactor, such as those being used to produce Plutonium to drive electric power stations. However, being scientists in a new, exciting field, it was impossible to avoid letting their minds wander from the task at hand to other scientific or non-military uses for the bombs themselves. During the Manhattan Project, Otto Frisch, one of the pioneers in the development of nuclear fission process in the 1930s, first suggested using an atomic explosion as a source for a large quantities of neutrons which could used in scientific experiments designed to expand their understanding of nuclear physics. After the war was over, many grandiose ideas appeared in the popular press on how this new source of energy should be to serve mankind. Not to be left out of the growing enthusiasm for peaceful uses of atomic energy, the Soviet Union added their visions to the public record. This document details the Soviet program for using nuclear explosions in peacetime pursuits.

  19. Laboratory for Nuclear Science. High Energy Physics Program

    Energy Technology Data Exchange (ETDEWEB)

    Milner, Richard [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

    2014-07-30

    High energy and nuclear physics research at MIT is conducted within the Laboratory for Nuclear Science (LNS). Almost half of the faculty in the MIT Physics Department carry out research in LNS at the theoretical and experimental frontiers of subatomic physics. Since 2004, the U.S. Department of Energy has funded the high energy physics research program through grant DE-FG02-05ER41360 (other grants and cooperative agreements provided decades of support prior to 2004). The Director of LNS serves as PI. The grant supports the research of four groups within LNS as “tasks” within the umbrella grant. Brief descriptions of each group are given here. A more detailed report from each task follows in later sections. Although grant DE-FG02-05ER41360 has ended, DOE continues to fund LNS high energy physics research through five separate grants (a research grant for each of the four groups, as well as a grant for AMS Operations). We are pleased to continue this longstanding partnership.

  20. Position of the American Think Tanks on Iran's Nuclear Program

    Directory of Open Access Journals (Sweden)

    Natalia Viktorovna Ivkina

    2015-12-01

    Full Text Available The article examines the role of “analytical centers” in the US foreign policy agenda. From a variety of “think tanks” highlights those who have made the greatest impact on the foreign policy - the Heritage Foundation and the Center for American progress. They examine U.S. relations with other regions of the world. The marked correlation between the reports of these think tanks and the positions of the Democratic and Republican parties of the USA. Based on the publications of articles and reports from these centers, it is considered one of the directions of U.S. foreign policy. In the article there is the comparative analysis of the approaches of these centers to the problem of Iran's nuclear program. This question is particularly acute on the agenda in relations between Iran and the United States. In addition, in 2015, the negotiations between Iran and the Six mediators on the nuclear issue has entered a crucial stage, it makes this issue the most relevant. The author makes a conclusion about the extent of American influence of “think-tanks” on foreign policy decisions in general and on specific political situation.

  1. Computer program system for evaluation of FP nuclear data for JENDL. Smooth part

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Watanabe, Takashi; Iijima, Shungo

    1997-12-01

    This report describes computer programs used to evaluate nuclear data of fission product (FP) nuclides stored in an evaluated nuclear data library JENDL, especially in the smooth part above the resonance region. Many programs were used for determination of nuclear model parameters, calculation of nuclear data, handling of experimental and/or calculated data, and so on. Among them, reported here are programs for determination of level density parameters (ENSDFRET, LVLPLOT, LEVDES), for making sets of JCL and input data for the theoretical calculation program CASTHY (JOBSETTER, INDES/CASTHY), and for conversion of format of CASTHY output files to the ENDF format (CTOB2). (author). 51 refs.

  2. Japan`s international cooperation programs on seismic safety of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Sanada, Akira [Agency of Natural Resources and Energy, Tokyo (Japan)

    1997-03-01

    MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

  3. Study of the environmental costs to nuclear power plants using the SIMPACTS program

    Energy Technology Data Exchange (ETDEWEB)

    Menzel, Francine; Sabundjian, Gaiane; Mutarelli, Rita de Cassia, E-mail: fmenzel@ipen.b, E-mail: gdjian@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    The nuclear energy presents advantages in comparison with other kinds of energy sources, when their externalities are evaluated. Externality is a term that represents the side effects of production of goods or services on other people not directly involved in the activity. The externalities can be identified and related to the term environmental cost. The environmental cost is a externality that somehow affects the environment, converted into economic terms, to then be compared with other costs of an action or enterprise. The environmental cost can be calculated through programs for that purpose, however for the nuclear area is the most used SIMPACTS, developed by the International Atomic Energy Agency (IAEA). The motivation for this work arose from the need to have a complete assessment of environmental costs from nuclear power reactors, although it is known that this kind of form of energy generation show an advantage over others with regard to externalities. This work is the first step in implementing the program SIMPACTS in plant Angra 2 in order to calculate the environmental cost of their operation. The objective is to develop a methodology for calculating environmental cost for nuclear power reactors. SIMPACTS program will be used to identify the advantages and disadvantages of a cost analysis of environmental and perform the calculation of environmental costs for Angra 2, with the aim of minimizing the environmental impacts of its operation. From an extensive literature search, is presented in this paper the methodology for calculating the environmental cost of the program SIMPACTS and some results of calculations with the environmental cost in international power reactors other power generation plants. (author)

  4. An assessment on the applicability of licensing requirements for safety analysis of CANDU nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Jang, S. H. [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    1992-05-15

    The purpose of this project is to establish safety analysis requirements for CANDU nuclear power plants to be licensed for construction and operation in Korea. Main emphasis is given to assess the applicability of the Canada AECB consultant Document C-6 and to establish the method of application. Examination of the NPP regulation philosophy and safety analysis requirements in Canada. Assessment of the applicability of the C-6 requirements for CANDU plants to be built in Korea. Establishment of the method of application for C-6 requirements. Assessment of the PSA requirements for CANDU. Examination of the validity of computer programs used for CANDU safety analysis.

  5. Next Generation Nuclear Plant Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    P. E. MacDonald

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen

  6. 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.

  7. Probabilistic Risk Assessment on Maritime Spent Nuclear Fuel Transportation

    Energy Technology Data Exchange (ETDEWEB)

    Christian, Robby; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    Spent nuclear fuel (SNF) management has been an indispensable issue in South Korea. Before a long term SNF solution is implemented, there exists the need to distribute the spent fuel pool storage loads. Transportation of SNF assemblies from populated pools to vacant ones may preferably be done through the maritime mode since all nuclear power plants in South Korea are located at coastal sites. To determine its feasibility, it is necessary to assess risks of the maritime SNF transportation. This work proposes a methodology to assess the risk arising from ship collisions during the transportation of SNF by sea. Its scope is limited to the damage probability of SNF packages given a collision event. The effect of transport parameters' variation to the package damage probability was investigated to obtain insights into possible ways to minimize risks. A reference vessel and transport cask are given in a case study to illustrate the methodology's application.

  8. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Itti, Roland E-mail: roland.itti@univ-lyon1.fr; Merabet, Yasmina; Roca, Ramona; Bontemps, Laurence; Itti, Emmanuel

    2004-07-11

    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.

  10. Systems Thinking Safety Analysis: Nuclear Security Assessment of Physical Protection System in Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Tae Ho Woo

    2013-01-01

    Full Text Available The dynamical assessment has been performed in the aspect of the nuclear power plants (NPPs security. The physical protection system (PPS is constructed by the cyber security evaluation tool (CSET for the nuclear security assessment. The systems thinking algorithm is used for the quantifications by the Vensim software package. There is a period of 60 years which is the life time of NPPs' operation. The maximum possibility happens as 3.59 in the 30th year. The minimum value is done as 1.26 in the 55th year. The difference is about 2.85 times. The results of the case with time delay have shown that the maximum possibility of terror or sabotage incident happens as 447.42 in the 58th year and the minimum value happens as 89.77 in the 51st year. The difference is about 4.98 times. Hence, if the sabotage happens, the worst case is that the intruder can attack the target of the nuclear material in about one and a half hours. The general NPPs are modeled in the study and controlled by the systematic procedures.

  11. January 1978 monthly highlights for Office of Nuclear Regulatory Research Programs at Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Mynatt, F.R. (comp.)

    1978-02-10

    Highlights of technical progress during January 1978 are presented for sixteen separate program activities which comprise the ORNL research program for the Office of Nuclear Regulatory Research's Division of Reactor Safety Research.

  12. Uranium from Seawater Program Review; Fuel Resources Uranium from Seawater Program DOE Office of Nuclear Energy

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-07-01

    the rate-limiting step of uranium uptake from seawater is also essential in designing an effective uranium recovery system. Finally, economic analyses have been used to guide these studies and highlight what parameters, such as capacity, recyclability, and stability, have the largest impact on the cost of extraction of uranium from seawater. Initially, the cost estimates by the JAEA for extraction of uranium from seawater with braided polymeric fibers functionalized with amidoxime ligands were evaluated and updated. The economic analyses were subsequently updated to reflect the results of this project while providing insight for cost reductions in the adsorbent development through “cradle-to-grave” case studies for the extraction process. This report highlights the progress made over the last three years on the design, synthesis, and testing of new materials to extract uranium for seawater. This report is organized into sections that highlight the major research activities in this project: (1) Chelate Design and Modeling, (2) Thermodynamics, Kinetics and Structure, (3) Advanced Polymeric Adsorbents by Radiation Induced Grafting, (4) Advanced Nanomaterial Adsorbents, (5) Adsorbent Screening and Modeling, (6) Marine Testing, and (7) Cost and Energy Assessment. At the end of each section, future research directions are briefly discussed to highlight the challenges that still remain to reduce the cost of extractions of uranium for seawater. Finally, contributions from the Nuclear Energy University Programs (NEUP), which complement this research program, are included at the end of this report.

  13. Establishment of a national program for quality control of nuclear medicine instrumentation.

    Science.gov (United States)

    Coca Perez, Marco A; Torres Aroche, Leonel A; Bejerano, Gladys López; Mayor, Roberto Fraxedas; Corona, Consuelo Varela; López, Adlin

    2008-12-01

    Monitoring the quality of instrumentation used in nuclear medicine is mandatory to guarantee the clinical efficacy of medical practice. A national program for the quality control of nuclear medicine instruments was established in Cuba and was certified and approved by the regulatory authorities. The program, which establishes official regulations and audit services, sets up educational activities, distributes technical documentation, and maintains a national phantom bank, constitutes a valuable and useful tool to guarantee the quality of nuclear medicine instrumentation.

  14. Nuclear Technology Series. Radiation Protection Technician. A Suggested Program Planning Guide. Revised June 80.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This program planning guide for a two-year postsecondary radiation protection technician program is designed for use with courses 17-22 of thirty-five included in the Nuclear Technology Series. The purpose of the guide is to describe the nuclear power field and its job categories for specialists, technicians, and operators; and to assist planners,…

  15. Assessment of PWR plutonium burners for nuclear energy centers

    Energy Technology Data Exchange (ETDEWEB)

    Frankel, A J; Shapiro, N L

    1976-06-01

    The purpose of the study was to explore the performance and safety characteristics of PWR plutonium burners, to identify modifications to current PWR designs to enhance plutonium utilization, to study the problems of deploying plutonium burners at Nuclear Energy Centers, and to assess current industrial capability of the design and licensing of such reactors. A plutonium burner is defined to be a reactor which utilizes plutonium as the sole fissile addition to the natural or depleted uranium which comprises the greater part of the fuel mass. The results of the study and the design analyses performed during the development of C-E's System 80 plant indicate that the use of suitably designed plutonium burners at Nuclear Energy Centers is technically feasible.

  16. Nuclear Medicine Technologists' Perception and Current Assessment of Quality: A Society of Nuclear Medicine and Molecular Imaging Technologist Section Survey.

    Science.gov (United States)

    Mann, April; Farrell, Mary Beth; Williams, Jessica; Basso, Danny

    2017-06-01

    In 2015, the Society of Nuclear Medicine and Molecular Imaging Technologist Section (SNMMI-TS) launched a multiyear quality initiative to help prepare the technologist workforce for an evidence-based health-care delivery system that focuses on quality. To best implement the quality strategy, the SNMMI-TS first surveyed technologists to ascertain their perception of quality and current measurement of quality indicators. Methods: An internet survey was sent to 27,989 e-mail contacts. Questions related to demographic data, perceptions of quality, quality measurement, and opinions on the minimum level of education are discussed in this article. Results: A total of 4,007 (14.3%) responses were received. When asked to list 3 words or phrases that represent quality, there were a plethora of different responses. The top 3 responses were image quality, quality control, and technologist education or competency. Surveying patient satisfaction was the most common quality measure (80.9%), followed by evaluation of image quality (78.2%). Evaluation of image quality (90.3%) and equipment functionality (89.4%) were considered the most effective measures. Technologists' differentiation between quality, quality improvement, quality control, quality assurance, and quality assessment seemed ambiguous. Respondents were confident in their ability to assess and improve quality at their workplace (91.9%) and agreed their colleagues were committed to delivering quality work. Of note, 70.7% of respondents believed that quality is directly related to the technologist's level of education. Correspondingly, respondents felt there should be a minimum level of education (99.5%) and that certification or registry should be required (74.4%). Most respondents (59.6%) felt that a Bachelor's degree should be the minimum level of education, followed by an Associate's degree (40.4%). Conclusion: To best help nuclear medicine technologists provide quality care, the SNMMI-TS queried technologists to

  17. International academic program in technologies of light-water nuclear reactors. Phases of development and implementation

    Science.gov (United States)

    Geraskin, N. I.; Glebov, V. B.

    2017-01-01

    The results of implementation of European educational projects CORONA and CORONA II dedicated to preserving and further developing nuclear knowledge and competencies in the area of technologies of light-water nuclear reactors are analyzed. Present article addresses issues of design and implementation of the program for specialized training in the branch of technologies of light-water nuclear reactors. The systematic approach has been used to construct the program for students of nuclear specialties, which corresponding to IAEA standards and commonly accepted nuclear principles recognized in the European Union. Possibilities of further development of the international cooperation between countries and educational institutions are analyzed. Special attention is paid to e-learning/distance training, nuclear knowledge preservation and interaction with European Nuclear Education Network.

  18. Safety Assessment of Nuclear Power Plants for Liquefaction Consequences

    Directory of Open Access Journals (Sweden)

    Tamás János Katona

    2015-01-01

    Full Text Available In case of some nuclear power plants constructed at the soft soil sites, liquefaction should be analysed as beyond design basis hazard. The aim of the analysis is to define the postevent condition of the plant, definition of plant vulnerabilities, and identification of the necessary measures for accident management. In the paper, the methodology of the analysis of liquefaction effects for nuclear power plants is outlined. The procedure includes identification of the scope of the safety analysis and the acceptable limit cases for plant structures having different role from accident management point of view. Considerations are made for identification of dominating effects of liquefaction. The possibility of the decoupling of the analysis of liquefaction effects from the analysis of vibratory ground motion is discussed. It is shown in the paper that the practicable empirical methods for definition of liquefaction susceptibility provide rather controversial results. Selection of method for assessment of soil behaviour that affects the integrity of structures requires specific considerations. The case of nuclear power plant at Paks, Hungary, is used as an example for demonstration of practical importance of the presented results and considerations.

  19. Damage assessment of nuclear containment against aircraft crash

    Energy Technology Data Exchange (ETDEWEB)

    Iqbal, Mohd Ashraf, E-mail: iqbal_ashraf@rediffmail.com; Sadique, Md. Rehan, E-mail: rehan.sadique@gmail.com; Bhargava, Pradeep, E-mail: bhpdpfce@iitr.ac.in; Bhandari, N.M., E-mail: nmbcefce@iitr.ac.in

    2014-10-15

    Highlights: • Damage assessment of nuclear containment is studied against aircraft crash. • Four impact locations have been identified at the outer containment shell. • The mid of the total height has been found to be most vulnerable location. • The crown of dome has been found to be the strongest location. • Phantom F4 caused more localized and severe damage compared to other aircrafts. - Abstract: The behavior of nuclear containment structure has been studied against aircraft crash with an emphasis on the influence of strike location. The impact locations identified on the BWR Mark III type nuclear containment structure are mid-height, junction of dome and cylinder, crown of dome and arc of dome. The containment at each of the above locations has been impacted normally by Phantom F-4, Boeing 707-320 and Airbus A320 aircrafts. The loading of the aircraft has been assigned through the corresponding reaction-time response curve. ABAQUS/Explicit finite element code has been used to carry out the three-dimensional numerical simulations. The concrete damaged plasticity model was used to simulate the behavior of concrete while the behavior of steel reinforcement was incorporated using the Johnson–Cook elasto-viscoplastic material model. The mid-height of containment has been found to experience most severe deformation against each aircraft. Phantom F4 has been found to be most disastrous at each location. The results have been compared with those of the available studies with respect to the containment deformation.

  20. Program Manager Assessments: Professionalism Personified

    Science.gov (United States)

    2015-08-01

    been successful, although I expect I have caused some people to worry. The results, from my perspective at least, have been terrific. I’m still... expected that. What I hadn’t expected , but probably should have, was the window these documents provide into the many complex challenges our PMs...corrective actions, I would prefer less drama in our programs and less need for corrective action in the first place. Like many of our PMs, this one

  1. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR)

    Energy Technology Data Exchange (ETDEWEB)

    Gilbert, B.G.; Richards, R.E.; Reece, W.J.; Gertman, D.I.

    1992-10-01

    This Reference Guide contains instructions on how to install and use Version 3.5 of the NRC-sponsored Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR). The NUCLARR data management system is contained in compressed files on the floppy diskettes that accompany this Reference Guide. NUCLARR is comprised of hardware component failure data (HCFD) and human error probability (HEP) data, both of which are available via a user-friendly, menu driven retrieval system. The data may be saved to a file in a format compatible with IRRAS 3.0 and commercially available statistical packages, or used to formulate log-plots and reports of data retrieval and aggregation findings.

  2. Clinical and economic outcomes assessment in nuclear cardiology

    Energy Technology Data Exchange (ETDEWEB)

    Shaw, L.J. [Atlanta Emory Univ., Atlanta, GA (United States); Miller, D.D. [St. Louis Univ. Health Sciences Center, St. Louis MO (United States); Berman, D.S. [Cedars-Sinai Medical Center, Los Angeles, CA (United States); Hachamovitch, R. [St. Francis Medical Center, New York (United States)

    2000-06-01

    The future of nuclear medicine procedures, as understood within our current economic climate, depends upon its ability to provide relevant clinical information at similar or lower comparative costs. With an ever-increasing emphasis on cost containment, outcome assessment forms the basis of preserving the quality of patient care. Today, outcomes assessment encompasses a wide array of subjects including clinical, economic, and humanistic (i.e., quality of life) outcomes. For nuclear cardiology, evidence-based medicine would require a threshold level of evidence in order to justify the added cost of any test in a patient's work-up. This evidence would include large multicenter, observational series as well as randomized trial data in sufficiently large and diverse patient populations. The new movement in evidence-based medicine is also being applied to the introduction of new technologies, in particular when comparative modalities exist. In the past 5 years, it has seen a dramatic shift in the quality of outcomes data published in nuclear cardiology. This includes the use of statistically rigorous risk-adjusted techniques as well as large populations (i.e., >500 patients) representing multiple diverse medical care settings. This has been the direct result of the development of multiple outcomes databases that have now amassed thousands of patients worth of data. One of the benefits of examining outcomes in large patient datasets is the ability to assess individual endpoints (e.g., cardiac death) as compared with smaller datasets that often assess combined endpoints (e.g., death, myocardial infarction, or unstable angina). New technologies for the diagnosis of coronary artery disease have contributed to the rising costs of care. In the United States and in Europe, costs of care have risen dramatically, consuming an ever-increasing amount of available resources. The overuse of diagnostic angiography often leads to unnecessary revascularization that does not lead to

  3. Developing a program to identify and track corrosion in nuclear plant raw water systems

    Energy Technology Data Exchange (ETDEWEB)

    Spires PE, G.V. [KTA - Tator Inc., Pittsburgh, Pennsylvania (United States); Pickles PE, S.B. [Senior Engineer, Ontario Power Generation, Ontario (Canada)

    2001-07-01

    Findings derived from a comprehensive plant performance survey at Ontario Power Generation's (OPG) nuclear units convinced management that it would be prudent to expand the ongoing power piping Flow Accelerated Corrosion (FAC) induced wall thinning base-lining and tracking program to encompass the raw cooling water systems as well. Such systems are subject to a distinctly different class of pipe wall thinning (PWT) mechanisms than the FAC that degrades high-energy power piping. This paper describes the PWT corrosion assessment and tracking program that has been developed and is currently being implemented by OPG for the raw cooling water (i.e., Service Water) systems within it's nuclear generating stations. Interim databases are used prior to initial inspection rounds to catalogue the prospective locations. For each piping system being surveyed, these interim databases include physical coordinates for the candidate locations, the type and wall thickness of the components comprising each location, ranking indications and recommended NDE methodologies as a function of the anticipated corrosion mechanisms. Rationales for assessing corrosion susceptibility and ranking prospective inspection sites are expounded by way of notations built into the database. (authors)

  4. Environmental Assessment of Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The Department of Energy has completed the Environmental Assessment (EA) of Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel and issued a Finding of No Significant Impact (FONSI) for the proposed action. The EA and FONSI are enclosed for your information. The Department has decided to accept a limited number of spent nuclear fuel elements (409 elements) containing uranium that was enriched in the United States from eight research reactors in Austria, Denmark, Germany, Greece, the Netherlands, Sweden, and Switzerland. This action is necessary to maintain the viability of a major US nuclear weapons nonproliferation program to limit or eliminate the use of highly enriched uranium in civil programs. The purpose of the EA is to maintain the cooperation of the foreign research reactor operators with the nonproliferation program while a more extensive Environmental Impact Statement (EIS) is prepared on a proposed broader policy involving the acceptance of up to 15,000 foreign research reactor spent fuel elements over a 10 to 15 year period. Based on an evaluation of transport by commercial container liner or chartered vessel, five eastern seaboard ports, and truck and train modes of transporting the spent fuel overland to the Savannah River Sits, the Department has concluded that no significant impact would result from any combination of port and made of transport. In addition, no significant impacts were found from interim storage of spent fuel at the Savannah River Site.

  5. Baku paper reports Armenian role in Iran's nuclear program

    CERN Multimedia

    2003-01-01

    "The war in Iraq has made the subject of nuclear research in countries of the third world a matter of current interest. Talk at this time is mostly about Iran, which has oil, and American experts believe, will in the next 3-4 years be perfectly capable of making a nuclear bomb" (1 page).

  6. A Survey of Medical School Programs on Nuclear War.

    Science.gov (United States)

    McCally, Michael; And Others

    1984-01-01

    Several medical schools have sponsored courses on medical aspects of nuclear war, and faculties of medical schools conducting or considering such courses have many questions about the organization of their teaching. A survey of U.S. schools of medicine presentations of nuclear war-related subject matter is discussed. (MLW)

  7. Nuclear accident consequence assessment in Hong Kong using JRODOS.

    Science.gov (United States)

    Leung, W H; Ma, W M; Chan, Philip K Y

    2018-03-01

    The JRODOS (Java-based Real-time Online DecisiOn Support) is a decision support system for off-site emergency management for releases of radioactive material into the environment. This paper documents the application of JRODOS by the Hong Kong Observatory in accident consequence assessment and emergency preparedness studies. For operational considerations, the most computational efficient dispersion model in JRODOS, ATSTEP, is adopted. Verification studies for JRODOS's ATSTEP model have been conducted. Comparison with tracer experiment results showed that under neutral atmospheric conditions and distances up to 50 km, the JRODOS simulation outputs were in general of the same order of magnitude with the tracer data. To further evaluate the capability of JRODOS in short-range simulation, a case study on the Fukushima nuclear power plant accident was also carried out. JRODOS was able to produce realistic simulation results which were comparable to the actual airborne monitoring data of the Cs-137 ground deposition from the Fukushima accident. Furthermore, the results of a comprehensive study to assess the potential consequences of accidents at a nearby nuclear power station are presented. Simulation using the French S3 source term for the Guangdong Nuclear Power Station at Daya Bay showed that the projected effective doses within Hong Kong remain far below the IAEA generic criteria of projected dose for urgent protective actions in sheltering/evacuation, while the projected equivalent dose in thyroid may meet the IAEA generic criteria for use of thyroid blocking agent at some areas in the northeastern part of Hong Kong, at distances of up to about 40 km from Daya Bay depending on the prevailing weather conditions in different seasons. Copyright © 2017 Elsevier Ltd. All rights reserved.

  8. 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.

  9. A Program in Medium-Energy Nuclear Physics

    Energy Technology Data Exchange (ETDEWEB)

    Feldman, Gerald [George Washington Univ., Washington, DC (United States)

    2015-03-23

    We report here on the final stages of the Berman grant. The study of the spectrum and properties of the excited states of the nucleon (the N* states) is one of the highest-priority goals of nuclear physics and one of the major programs of Jefferson Lab, especially in Hall B. We have most recently focused our attention on exclusive studies (in both spin and strangeness) of the neutron in the deuteron. Our g13 experiment, “Production of Kaons from the Deuteron with Polarized Photons” [Nadel-Turonski (2006)], was carried out between October 2006 and June 2007. This experiment was done using both linearly and circularly polarized photons, mainly to try to unscramble the multitude of wide and overlapping N* states and to measure their properties by studying in fine detail their decays into strange-particle reaction channels. To this end, one of our students, Edwin Munevar, has analyzed the γn→K+Σ- reaction channel for his Ph.D. topic. The strangeness-production channels constitute the subject of the original GW group’s g13 proposal. But the g13 data set, by virtue of its statistics, polarization, and kinematic coverage, is ideally suited for many other reaction channels as well. Among these is the azimuthal angular asymmetry for deuteron photodisintegration, which was analyzed by another of our students, Nicholas Zachariou, for his Ph.D. topic, with help from Nickolay Ivanov (from the Yerevan Physics Institute in Armenia). This study required a deuterium target and a linearly polarized photon beam.

  10. Development of Safety Assessment Code for Decommissioning of Nuclear Facilities

    Science.gov (United States)

    Shimada, Taro; Ohshima, Soichiro; Sukegawa, Takenori

    A safety assessment code, DecDose, for decommissioning of nuclear facilities has been developed, based on the experiences of the decommissioning project of Japan Power Demonstration Reactor (JPDR) at Japan Atomic Energy Research Institute (currently JAEA). DecDose evaluates the annual exposure dose of the public and workers according to the progress of decommissioning, and also evaluates the public dose at accidental situations including fire and explosion. As for the public, both the internal and the external doses are calculated by considering inhalation, ingestion, direct radiation from radioactive aerosols and radioactive depositions, and skyshine radiation from waste containers. For external dose for workers, the dose rate from contaminated components and structures to be dismantled is calculated. Internal dose for workers is calculated by considering dismantling conditions, e.g. cutting speed, cutting length of the components and exhaust velocity. Estimation models for dose rate and staying time were verified by comparison with the actual external dose of workers which were acquired during JPDR decommissioning project. DecDose code is expected to contribute the safety assessment for decommissioning of nuclear facilities.

  11. Assessing Early Intervention Outcomes: Beyond Program Variables.

    Science.gov (United States)

    Marfo, Kofi; Dinero, Thomas E.

    1991-01-01

    This paper argues that efficacy of early intervention must be assessed in relation to both program and extra-program variables. A framework outlining five classes of independent variables and two classes of outcomes to be considered in efficacy research is presented, and regression and path analytic techniques are suggested as tools for addressing…

  12. Assessing Quality in Home Visiting Programs

    Science.gov (United States)

    Korfmacher, Jon; Laszewski, Audrey; Sparr, Mariel; Hammel, Jennifer

    2013-01-01

    Defining quality and designing a quality assessment measure for home visitation programs is a complex and multifaceted undertaking. This article summarizes the process used to create the Home Visitation Program Quality Rating Tool (HVPQRT) and identifies next steps for its development. The HVPQRT measures both structural and dynamic features of…

  13. 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…

  14. Assessing the Need for a University Program.

    Science.gov (United States)

    Gunzberger, Linda K.

    1980-01-01

    At Loyola University of Chicago a needs assessment procedure was used to decide whether to establish a master's degree program in public administration that would serve many part-time students. It required the analysis of potential participants, the university, faculty, competing programs, and potential employers. (CT)

  15. Development of Capacity Building Training Programs for Nuclear R and D Personnel

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Eui Jin; Nam, Youngmi; Hwang, Hyeseon; Jang, Eunsook; Song, Eun Ju [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The Nuclear Training and Education Center of the Korea Atomic Energy Research Institute has been operating technical training courses on nuclear engineering, engineering mathematics, management leadership training, out sourced practical training, legal education, etc. Strengthening nuclear R and D capacity is essential for the long-term mission and goals of the institute. Therefore, it requires a comprehensive training program to strengthen the unique capability of the institute that reflects diversity and differentiation. In this regard, the capacity building training program has developed on a modular basis, and the developed training program should be tailored to operate according to the institute needs. The capacity building training program for nuclear R and D personnel was developed to reflect the technology strengths of the institute. The developed training program will be developed into a leading branded education of the institute in the future.

  16. Evaluation of training programs and entry-level qualifications for nuclear-power-plant control-room personnel based on the systems approach to training

    Energy Technology Data Exchange (ETDEWEB)

    Haas, P M; Selby, D L; Hanley, M J; Mercer, R T

    1983-09-01

    This report summarizes results of research sponsored by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to initiate the use of the Systems Approach to Training in the evaluation of training programs and entry level qualifications for nuclear power plant (NPP) personnel. Variables (performance shaping factors) of potential importance to personnel selection and training are identified, and research to more rigorously define an operationally useful taxonomy of those variables is recommended. A high-level model of the Systems Approach to Training for use in the nuclear industry, which could serve as a model for NRC evaluation of industry programs, is presented. The model is consistent with current publically stated NRC policy, with the approach being followed by the Institute for Nuclear Power Operations, and with current training technology. Checklists to be used by NRC evaluators to assess training programs for NPP control-room personnel are proposed which are based on this model.

  17. SU-D-217A-03: Nuclear Medicine Uniformity Assessment Using 2D Noise Power Spectrum.

    Science.gov (United States)

    Nelson, J; Christianson, O; Harkness, B; Madsen, M; Mah, E; Thomas, S; Zaidi, H; Samei, E

    2012-06-01

    Nuclear medicine quality control programs require daily evaluation for the presence of potential non-uniformities by commonly utilizing a traditional pixel value-based assessment (Integral CFOVUniformity). While this method effectively captures regional non- uniformities in the image, it does not adequately reflect subtle periodic structures that are visually apparent and clinically unacceptable, therefore requiring the need for additional visual inspection of the image. The goal of this project was to develop a new uniformity assessment metric by targetingstructural patterns and more closely correlating with visual inspection. The new quantitative uniformity assessment metric is based on the 2D Noise Power Spectrum (NPS). A full 2D NPS was performed on each image. The NPS was thresholded to remove quantum noise and further filtered by the visual response function. A score, the Structure Noise Index (SNI), was then applied to each based on the average magnitude of the structured noise in the processed image. To verify the validity of the new metric, 50 daily uniformity images with varying degrees of visual structured and non-structured non-uniformity were scored by 5 expert nuclear medicine physicists. The correlation between the visual score and SNI were assessed. The Integral CFOV was also compared against the visual score. Our new SNI assessment metric compared to the Integral CFOV showed in increase in sensitivity from 67% to 100% in correctly identifying structured non-uniformities. The overall positive predictive value also increased from 55% to 72%. Our new uniformity metric correlates much more closely with visual assessment of structured non- uniform NM images than the traditional pixel-based method. Using this new metric in conjunction with the traditional pixel value-based assessment will allow a more accurate quantitative assessment of nuclear medicineuniformity. © 2012 American Association of Physicists in Medicine.

  18. Nuclear electric propulsion for planetary science missions: NASA technology program planning

    Science.gov (United States)

    Doherty, Michael P.

    1993-01-01

    This paper presents the status of technology program planning to develop those Nuclear Electric Propulsion technologies needed to meet the advanced propulsion system requirements for planetary science missions in the next century. The technology program planning is based upon technologies with significant development heritage: ion electric propulsion and the SP-100 space nuclear power technologies. Detailed plans are presented for the required ion electric propulsion technology development and demonstration. Closer coordination between space nuclear power and space electric propulsion technology programs is a necessity as technology plans are being further refined in light of NEP concept definition and possible early NEP flight activities.

  19. Progress in space nuclear reactor power systems technology development - The SP-100 program

    Science.gov (United States)

    Davis, H. S.

    1984-01-01

    Activities related to the development of high-temperature compact nuclear reactors for space applications had reached a comparatively high level in the U.S. during the mid-1950s and 1960s, although only one U.S. nuclear reactor-powered spacecraft was actually launched. After 1973, very little effort was devoted to space nuclear reactor and propulsion systems. In February 1983, significant activities toward the development of the technology for space nuclear reactor power systems were resumed with the SP-100 Program. Specific SP-100 Program objectives are partly related to the determination of the potential performance limits for space nuclear power systems in 100-kWe and 1- to 100-MW electrical classes. Attention is given to potential missions and applications, regimes of possible space power applicability, safety considerations, conceptual system designs, the establishment of technical feasibility, nuclear technology, materials technology, and prospects for the future.

  20. Optically-based Sensor System for Critical Nuclear Facilities Post-Event Seismic Structural Assessment

    Energy Technology Data Exchange (ETDEWEB)

    McCallen, David [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Petrone, Floriana [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Buckle, Ian [Univ. of Nevada, Reno, NV (United States); Wu, Suiwen [Univ. of Nevada, Reno, NV (United States); Coates, Jason [California State Univ., Chico, CA (United States)

    2017-09-30

    The U.S. Department of Energy (DOE) has ownership and operational responsibility for a large enterprise of nuclear facilities that provide essential functions to DOE missions ranging from national security to discovery science and energy research. These facilities support a number of DOE programs and offices including the National Nuclear Security Administration, Office of Science, and Office of Environmental Management. With many unique and “one of a kind” functions, these facilities represent a tremendous national investment, and assuring their safety and integrity is fundamental to the success of a breadth of DOE programs. Many DOE critical facilities are located in regions with significant natural phenomenon hazards including major earthquakes and DOE has been a leader in developing standards for the seismic analysis of nuclear facilities. Attaining and sustaining excellence in nuclear facility design and management must be a core competency of the DOE. An important part of nuclear facility management is the ability to monitor facilities and rapidly assess the response and integrity of the facilities after any major upset event. Experience in the western U.S. has shown that understanding facility integrity after a major earthquake is a significant challenge which, lacking key data, can require extensive effort and significant time. In the work described in the attached report, a transformational approach to earthquake monitoring of facilities is described and demonstrated. An entirely new type of optically-based sensor that can directly and accurately measure the earthquake-induced deformations of a critical facility has been developed and tested. This report summarizes large-scale shake table testing of the sensor concept on a representative steel frame building structure, and provides quantitative data on the accuracy of the sensor measurements.

  1. Advanced automotive diesel assessment program

    Science.gov (United States)

    Sekar, R.; Tozzi, L.

    1983-01-01

    Cummins Engine Company completed an analytical study to identify an advanced automotive (light duty) diesel (AAD) power plant for a 3,000-pound passenger car. The study resulted in the definition of a revolutionary diesel engine with several novel features. A 3,000-pound car with this engine is predicted to give 96.3, 72.2, and 78.8 MPG in highway, city, and combined highway-city driving, respectively. This compares with current diesel powered cars yielding 41.7, 35.0, and 37.7 MPG. The time for 0-60 MPH acceleration is 13.9 sec. compared to the baseline of 15.2 sec. Four technology areas were identified as crucial in bringing this concept to fruition. They are: (1) part-load preheating, (2) positive displacement compounding, (3) spark assisted diesel combustion system, and (4) piston development for adiabatic, oilless diesel engine. Marketing and planning studies indicate that an aggressive program with significant commitment could result in a production car in 10 years from the date of commencement.

  2. Regenerating the U.S. nuclear power program

    Energy Technology Data Exchange (ETDEWEB)

    Rowden, Marcus A.; Kraemer, Jay R.; Koehn, Mark R. [Fried, Frank, Harris, Shriver and Jacobson, Washington, DC (United States)

    1995-12-31

    Through industry planning initiatives, new licensing regulations, favorable court decisions and supportive legislation, the U.A. nuclear community - in both its private and governmental sectors - has, during the last five years, produced fundamental changes in the approach to planning, ordering, licensing and operating future nuclear power plants. Integrated and well-planned initiatives are leading to a more hospitable and promising institutional framework for regeneration of the U.S. nuclear option. While demonstrable progress has been made on many fronts - a streamlined plant licensing framework and standardized design development to name the most apparent - other critical path obstacles must still be surmounted to transform current progress into an order for a new nuclear power plant or a family of plants. Early signs are encouraging, but much work remains to be done. (author).

  3. Program Management at the National Nuclear Security Administration Office of Defense Nuclear Security: A Review of Program Management Documents and Underlying Processes

    Energy Technology Data Exchange (ETDEWEB)

    Madden, Michael S.

    2010-05-01

    The scope of this paper is to review the National Nuclear Security Administration Office of Defense Nuclear Security (DNS) program management documents and to examine the underlying processes. The purpose is to identify recommendations for improvement and to influence the rewrite of the DNS Program Management Plan (PMP) and the documentation supporting it. As a part of this process, over 40 documents required by DNS or its stakeholders were reviewed. In addition, approximately 12 other documents produced outside of DNS and its stakeholders were reviewed in an effort to identify best practices. The complete list of documents reviewed is provided as an attachment to this paper.

  4. Robot for Investigations and Assessments of Nuclear Areas

    Energy Technology Data Exchange (ETDEWEB)

    Kanaan, Daniel; Dogny, Stephane [AREVA D and S/DT, 30206 Bagnols sur Ceze (France)

    2015-07-01

    RIANA is a remote controlled Robot dedicated for Investigations and Assessments of Nuclear Areas. The development of RIANA is motivated by the need to have at disposal a proven robot, tested in hot cells; a robot capable of remotely investigate and characterise the inside of nuclear facilities in order to collect efficiently all the required data in the shortest possible time. It is based on a wireless medium sized remote carrier that may carry a wide variety of interchangeable modules, sensors and tools. It is easily customised to match specific requirements and quickly configured depending on the mission and the operator's preferences. RIANA integrates localisation and navigation systems. The robot will be able to generate / update a 2D map of its surrounding and exploring areas. The position of the robot is given accurately on the map. Furthermore, the robot will be able to autonomously calculate, define and follow a trajectory between 2 points taking into account its environment and obstacles. The robot is configurable to manage obstacles and restrict access to forbidden areas. RIANA allows an advanced control of modules, sensors and tools; all collected data (radiological and measured data) are displayed in real time in different format (chart, on the generated map...) and stored in a single place so that may be exported in a convenient format for data processing. This modular design gives RIANA the flexibility to perform multiple investigation missions where humans cannot work such as: visual inspections, dynamic localization and 2D mapping, characterizations and nuclear measurements of floor and walls, non destructive testing, samples collection: solid and liquid. The benefits of using RIANA are: - reducing the personnel exposures by limiting the manual intervention time, - minimizing the time and reducing the cost of investigation operations, - providing critical inputs to set up and optimize cleanup and dismantling operations. (authors)

  5. Lessons Learned While Conducting Educational Program Assessment

    Science.gov (United States)

    Rivas, Olivia; Jones, Irma S.; Pena, Eli E.

    2010-01-01

    Assessment, accountability, and strategic planning are all processes that are included in accreditation for colleges and universities. For most colleges and universities, starting the reaffirmation process means identifying current assessment practices and reports from academic units and programs. This paper discusses the lessons learned during a…

  6. Program Needs Assessment: The Telephone Survey Alternative.

    Science.gov (United States)

    Mishler, Carol

    This guidebook explains how to conduct a telephone survey that will gather the information necessary for new program needs assessment in the Wisconsin Vocational, Technical, and Adult Education system. The guidebook is based on pilot assessments conducted by Fox Valley Technical College. The guidebook contains five sections: (1) introduction--why…

  7. Technical Basis Spent Nuclear Fuel (SNF) Project Radiation and Contamination Trending Program

    Energy Technology Data Exchange (ETDEWEB)

    KURTZ, J.E.

    2000-05-10

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, and radiation surveys of the Cold Vacuum Drying Facility (CVD) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas.

  8. Iran’s Growing Nuclear Weapons Program: A Catalyst for Regional Instability in the Middle East

    Science.gov (United States)

    1993-03-10

    military spending . This increase has been primarily in the area of conventional forces, however there is growing evidence that Iran is also attempting to develop a nuclear weapons capability as well. This study examines Iran’s nuclear weapons program in detail, and Tehran’s increasing ability to emerge as a regional power in the Middle

  9. Environmental assessment report: Nuclear Test Technology Complex. [Construction and operation of proposed facility

    Energy Technology Data Exchange (ETDEWEB)

    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.

  10. RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Yuan, Y.C. [Square Y, Orchard Park, NY (United States); Chen, S.Y.; LePoire, D.J. [Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.; Rothman, R. [USDOE Idaho Field Office, Idaho Falls, ID (United States)

    1993-02-01

    This report presents the technical details of RISIUND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, semiinteractive program that can be run on an IBM or equivalent personal computer. The program language is FORTRAN-77. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incidentfree models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionudide inventory and dose conversion factors.

  11. Building the strategic national stockpile through the NIAID Radiation Nuclear Countermeasures Program.

    Science.gov (United States)

    Rios, Carmen I; Cassatt, David R; Dicarlo, Andrea L; Macchiarini, Francesca; Ramakrishnan, Narayani; Norman, Mai-Kim; Maidment, Bert W

    2014-02-01

    The possibility of a public health radiological or nuclear emergency in the United States remains a concern. Media attention focused on lost radioactive sources and international nuclear threats, as well as the potential for accidents in nuclear power facilities (e.g., Windscale, Three Mile Island, Chernobyl, and Fukushima) highlight the need to address this critical national security issue. To date, no drugs have been licensed to mitigate/treat the acute and long-term radiation injuries that would result in the event of large-scale, radiation, or nuclear public health emergency. However, recent evaluation of several candidate radiation medical countermeasures (MCMs) has provided initial proof-of-concept of efficacy. The goal of the Radiation Nuclear Countermeasures Program (RNCP) of the National Institute of Allergy and Infectious Diseases (National Institutes of Health) is to help ensure the government stockpiling of safe and efficacious MCMs to treat radiation injuries, including, but not limited to, hematopoietic, gastrointestinal, pulmonary, cutaneous, renal, cardiovascular, and central nervous systems. In addition to supporting research in these areas, the RNCP continues to fund research and development of decorporation agents targeting internal radionuclide contamination, and biodosimetry platforms (e.g., biomarkers and devices) to assess the levels of an individual's radiation exposure, capabilities that would be critical in a mass casualty scenario. New areas of research within the program include a focus on special populations, especially pediatric and geriatric civilians, as well as combination studies, in which drugs are tested within the context of expected medical care management (e.g., antibiotics and growth factors). Moving forward, challenges facing the RNCP, as well as the entire radiation research field, include further advancement and qualification of animal models, dose conversion from animal models to humans, biomarker identification, and

  12. Nuclear criticality safety program at the University of Tennessee-Knoxville

    Energy Technology Data Exchange (ETDEWEB)

    Basoglu, B.; Bentley, C.; Brewer, R.; Dunn, M.; Haught, C.; Plaster, M.; Wilkinson, A.; Dodds, H. (Univ. of Tennessee, Knoxville, TN (United States)); Elliott, E.; Waddell, W. (Martin Marietta Energy Systems Inc., Oak Ridge, TN (United States))

    1993-01-01

    This paper presents an overview of the nuclear criticality safety (NCS) educational program at the University of Tennessee-Knoxville. The program is an academic specialization for nuclear engineering graduate students pursuing either the MS or PhD degree and includes special NCS courses and NCS research projects. Both the courses and the research projects serve as partial fulfillment of the requirements for the degree being pursued.

  13. Recruiting Program for the Future R and D Leader in Nuclear Science and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Song, Keechan; Im, Ohsoo; Cho, Changyun; Min, Hwanki; Lee, Jungkong; Jung, Sunghyun; Kim, Jungbae; Joo, Hoyoung

    2013-05-15

    Nuclear technology export, which is represented by a nuclear research reactor, Gen-IV nuclear system development and nuclear safety research are the current key issues in the nuclear field. In order to achieve these missions in the nuclear industry, nuclear HRD(human resource development). However, recruiting of young scientists and researchers in the nuclear field has not been sufficient for last 10 years. Moreover, many experienced persons have been retired during this period. Under these circumstances, the structure of the nuclear experts wind up with vary distorted one. As one of comprehensive countermeasures, the recruiting program for the future R and D leaders come to issues. The human network to lead future R and Ds in the nuclear science and technology is set up, and this network is persistantly maintained and expanded to recruit potential leaders in the nuclear R and D and industry. As one of these strategy and plans for recruiting competent young scientists, who are studying in the U. S., the 2 times briefing meeting were held, and human networking and expertise DB for more than 300 participants were established.

  14. Nuclear spent fuel management scenarios. Status and assessment report

    Energy Technology Data Exchange (ETDEWEB)

    Dufek, J.; Arzhanov, V.; Gudowski, W. [Royal Inst. of Technology, Stockholm (Sweden). Dept. of Nuclear and Reactor Physics

    2006-06-15

    The strategy for management of spent nuclear fuel from the Swedish nuclear power programme is interim storage for cooling and decay for about 30 years followed by direct disposal of the fuel in a geologic repository. In various contexts it is of interest to compare this strategy with other strategies that might be available in the future as a result of ongoing research and development. In particular partitioning and transmutation is one such strategy that is subject to considerable R and D-efforts within the European Union and in other countries with large nuclear programmes. To facilitate such comparisons for the Swedish situation, with a planned phase out of the nuclear power programme, SKB has asked the team at Royal Inst. of Technology to describe and explore some scenarios that might be applied to the Swedish programme. The results of this study are presented in this report. The following scenarios were studied by the help of a specially developed computer programme: Phase out by 2025 with direct disposal. Burning plutonium and minor actinides as MOX in BWR. Burning plutonium and minor actinides as MOX in PWR. Burning plutonium and minor actinides in ADS. Combined LWR-MOX plus ADS. For the different scenarios nuclide inventories, waste amounts, costs, additional electricity production etc have been assessed. As a general conclusion it was found that BWR is more efficient for burning plutonium in MOX fuel than PWR. The difference is approximately 10%. Furthermore the BWR produces about 10% less americium inventory. An ADS reactor park can theoretically in an ideal case burn (transmute) 99% of the transuranium isotopes. The duration of such a scenario heavily depends on the interim time needed for cooling the spent fuel before reprocessing. Assuming 10 years for cooling of nuclear fuel from ADS, the duration will be at least 200 years under optimistic technical assumptions. The development and use of advanced pyro-processing with an interim cooling time of only

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

    Energy Technology Data Exchange (ETDEWEB)

    Thornton, G.; Rothstein, A.J.

    1962-06-28

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

  16. Integrated safety assessment of Indian nuclear power plants for ...

    Indian Academy of Sciences (India)

    Abstract. Nuclear energy professionals need to understand and address the catas- trophe syndrome that of late seems to be increasingly at work in public mind in the context of nuclear energy. Classically the nuclear power reactor design and system evolution has been based on the logic of minimization of risk to an ...

  17. Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    R. Doug Hamelin; G. O. Hayner

    2004-11-01

    The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

  18. Next Generation Nuclear Plant Materials Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    G. O. Hayner; E.L. Shaber

    2004-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

  19. Improved nuclear medicine uniformity assessment with noise texture analysis.

    Science.gov (United States)

    Nelson, Jeffrey S; Christianson, Olav I; Harkness, Beth A; Madsen, Mark T; Mah, Eugene; Thomas, Stephen R; Zaidi, Habib; Samei, Ehsan

    2014-01-01

    Because γ cameras are generally susceptible to environmental conditions and system vulnerabilities, they require routine evaluation of uniformity performance. The metrics for such evaluations are commonly pixel value-based. Although these metrics are typically successful at identifying regional nonuniformities, they often do not adequately reflect subtle periodic structures; therefore, additional visual inspections are required. The goal of this project was to develop, test, and validate a new uniformity analysis metric capable of accurately identifying structures and patterns present in nuclear medicine flood-field uniformity images. A new uniformity assessment metric, termed the structured noise index (SNI), was based on the 2-dimensional noise power spectrum (NPS). The contribution of quantum noise was subtracted from the NPS of a flood-field uniformity image, resulting in an NPS representing image artifacts. A visual response filter function was then applied to both the original NPS and the artifact NPS. A single quantitative score was calculated on the basis of the magnitude of the artifact. To verify the validity of the SNI, an observer study was performed with 5 expert nuclear medicine physicists. The correlation between the SNI and the visual score was assessed with Spearman rank correlation analysis. The SNI was also compared with pixel value-based assessment metrics modeled on the National Electrical Manufacturers Association standard for integral uniformity in both the useful field of view (UFOV) and the central field of view (CFOV). The SNI outperformed the pixel value-based metrics in terms of its correlation with the visual score (ρ values for the SNI, integral UFOV, and integral CFOV were 0.86, 0.59, and 0.58, respectively). The SNI had 100% sensitivity for identifying both structured and nonstructured nonuniformities; for the integral UFOV and CFOV metrics, the sensitivities were only 62% and 54%, respectively. The overall positive predictive

  20. Defense Acquisitions: Assessments of Selected Weapon Programs

    Science.gov (United States)

    2016-03-01

    billion increase in development costs . The Patriot Advanced Capability-3 Missile Segment Enhancement program accounts for $2 billion of the $2.5 billion...than 13GAO, Cost Estimating and Assessment Guide: Best Practices for Developing and Managing Capital Program Costs , GAO-09-3SP (Washington, D.C...development phase to avoid duplication of cost and development efforts, and because market research indicated that only the current vendors were

  1. 75 FR 3762 - Tennessee Valley Authority; Sequoyah Nuclear Plant, Units 1 and 2; Environmental Assessment and...

    Science.gov (United States)

    2010-01-22

    ... COMMISSION Tennessee Valley Authority; Sequoyah Nuclear Plant, Units 1 and 2; Environmental Assessment and..., issued to Tennessee Valley Authority (TVA, the licensee), for operation of the Sequoyah Nuclear Plant... 2010. For the Nuclear Regulatory Commission. Siva P. Lingam, Project Manager, Plant Licensing Branch...

  2. 78 FR 58570 - Environmental Assessment; Entergy Nuclear Operations, Inc., Big Rock Point

    Science.gov (United States)

    2013-09-24

    ... COMMISSION Environmental Assessment; Entergy Nuclear Operations, Inc., Big Rock Point AGENCY: Nuclear... Nuclear Operations, Inc. (ENO) (the applicant or the licensee), for the Big Rock Point (BRP) Independent... for Production and Utilization Facilities,'' for the Big Rock Point (BRP) Independent Spent Fuel...

  3. 76 FR 52356 - Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit 1; Environmental Assessment...

    Science.gov (United States)

    2011-08-22

    ... COMMISSION Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit 1; Environmental Assessment and... to Indiana Michigan Power Company (the licensee), for operation of Donald C. Cook Nuclear Plant, Unit... Statement for Donald C. Cook Nuclear Plant, Unit 1, or the Generic Environmental Impact Statement for...

  4. 75 FR 13607 - Entergy Operations, Inc., Arkansas Nuclear One, Units 1 and 2; Environmental Assessment and...

    Science.gov (United States)

    2010-03-22

    ... COMMISSION Entergy Operations, Inc., Arkansas Nuclear One, Units 1 and 2; Environmental Assessment and... Operations, Inc. (Entergy, the licensee), for operation of the Arkansas Nuclear One, Units 1 and 2 (ANO-1 and... Environmental Statement Related to Operation of Arkansas Nuclear One, Unit 2,'' as supplemented through the...

  5. Power cycle assessment of nuclear high temperature gas-cooled reactors

    OpenAIRE

    Herranz, L.E.; Linares, J.I.; Moratilla, B.Y.

    2009-01-01

    Power cycle assessment of nuclear high temperature gas-cooled reactors correspondance: Corresponding author. Tel.: +34 91 346 62 36; fax: +34 91 346 62 33. (Herranz, L.E.) (Herranz, L.E.) Unit of Nuclear Safety Research (CIEMAT) Avda. Complutense--> , 22 - 28040 Madrid - Spain--> - (Herranz, L.E.) Unit of Nuclear Safety Research (CIEMAT) Avda. Complutense--> , 22 - 28040 Madrid - Spain--...

  6. ICENES `91:Sixth international conference on emerging nuclear energy systems. Program and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-31

    This document contains the program and abstracts of the sessions at the Sixth International Conference on Emerging Nuclear Energy Systems held June 16--21, 1991 at Monterey, California. These sessions included: The plenary session, fission session, fission and nonelectric session, poster session 1P; (space propulsion, space nuclear power, electrostatic confined fusion, fusion miscellaneous, inertial confinement fusion, {mu}-catalyzed fusion, and cold fusion); Advanced fusion session, space nuclear session, poster session 2P, (nuclear reactions/data, isotope separation, direct energy conversion and exotic concepts, fusion-fission hybrids, nuclear desalting, accelerator waste-transmutation, and fusion-based chemical recycling); energy policy session, poster session 3P (energy policy, magnetic fusion reactors, fission reactors, magnetically insulated inertial fusion, and nuclear explosives for power generation); exotic energy storage and conversion session; and exotic energy storage and conversion; review and closing session.

  7. Spent nuclear fuel management: A comprehensive database for the DOE Spent Nuclear Fuel Program

    Energy Technology Data Exchange (ETDEWEB)

    Hale, D.L.

    1994-12-31

    An Integrated Spent Nuclear Fuel Database System (ISNFDS) has been designed by EG&G Idaho, Inc. at the Idaho National Engineering Laboratory (INEL) to maintain an inventory of all US Department of Energy (DOE) spent nuclear fuel (SNF). The purpose of the ISNFDS is to provide a centralized source of SNF information containing accurate and consistent data. A description of the quality control methodology, tools, and techniques for the data collection, entry, and verification process as they apply to the ISNFDS are outlined.

  8. Regional Environmental Monitoring and Assessment Program Data (REMAP)

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Regional Environmental Monitoring and Assessment Program (REMAP) was initiated to test the applicability of the Environmental Monitoring and Assessment Program...

  9. Quantitative assessment of protein function prediction programs.

    Science.gov (United States)

    Rodrigues, B N; Steffens, M B R; Raittz, R T; Santos-Weiss, I C R; Marchaukoski, J N

    2015-12-21

    Fast prediction of protein function is essential for high-throughput sequencing analysis. Bioinformatic resources provide cheaper and faster techniques for function prediction and have helped to accelerate the process of protein sequence characterization. In this study, we assessed protein function prediction programs that accept amino acid sequences as input. We analyzed the classification, equality, and similarity between programs, and, additionally, compared program performance. The following programs were selected for our assessment: Blast2GO, InterProScan, PANTHER, Pfam, and ScanProsite. This selection was based on the high number of citations (over 500), fully automatic analysis, and the possibility of returning a single best classification per sequence. We tested these programs using 12 gold standard datasets from four different sources. The gold standard classification of the databases was based on expert analysis, the Protein Data Bank, or the Structure-Function Linkage Database. We found that the miss rate among the programs is globally over 50%. Furthermore, we observed little overlap in the correct predictions from each program. Therefore, a combination of multiple types of sources and methods, including experimental data, protein-protein interaction, and data mining, may be the best way to generate more reliable predictions and decrease the miss rate.

  10. Nuclear electric propulsion mission engineering study development program and costs estimates, Phase 2 review

    Science.gov (United States)

    1972-01-01

    The results are presented of the second six-month performance period of the Nuclear Electric Propulsion Mission Engineering Study. A brief overview of the program, identifying the study objectives and approach, and a discussion of the program status and schedule are presented. The program results are reviewed and key conclusions to date are summarized. Planned effort for the remainder of the program is reviewed.

  11. 75 FR 61779 - R.E. Ginna Nuclear Power Plant, LLC; R.E. Ginna Nuclear Power Plant Environmental Assessment and...

    Science.gov (United States)

    2010-10-06

    ... COMMISSION R.E. Ginna Nuclear Power Plant, LLC; R.E. Ginna Nuclear Power Plant Environmental Assessment and... Operating License No. DPR-18, issued to R.E. Ginna Nuclear Power Plant, LLC (the licensee), for operation of the R.E. Ginna Nuclear Power Plant (Ginna), located in Ontario, New York. In accordance with 10 CFR 51...

  12. Efficient quality assurance programs in radiology and nuclear medicine in Ostergotland, Sweden.

    Science.gov (United States)

    Sandborg, Michael; Althén, Jonas Nilsson; Gustafsson, Agnetha

    2010-01-01

    Owners of imaging modalities using ionising radiation should have a documented quality assurance (QA) program, as well as methods to justify new radiological procedures to ensure safe operation and adequate clinical image quality. This includes having a system for correcting divergences, written imaging protocols, assessment of patient and staff absorbed doses and a documented education and training program. In this work, how some aspects on QA have been implemented in the County of Ostergötland in Sweden, and efforts to standardise and automate the process as an integrated part of the radiology and nuclear medicine QA programs were reviewed. Some key performance parameters have been identified by a Swedish task group of medical physicists to give guidance on selecting relevant QA methods. These include low-contrast resolution, image homogeneity, automatic exposure control, calibration of air kerma-area product metres and patient-dose data registration in the radiological information system, as well as the quality of reading stations and of the transfer of images to the picture archive and communication system. IT-driven methods to automatically assess patient doses and other data on all examinations are being developed and evaluated as well as routines to assess clinical image quality by use of European quality criteria. By assessing both patient absorbed doses and clinical image quality on a routine basis, the medical physicists in our region aim to be able to spend more time on imaging optimisation and less time on periodic testing of the technical performance of the equipment, particularly on aspects that show very few divergences. The role of the Medical Physics Expert is rapidly developing towards a person doing advanced data-analysis and giving scientific support rather than one performing mainly routine periodic measurements. It is concluded that both the European Council directive and the rapid development towards more complex diagnostic imaging systems

  13. Concept Design and Risk Assessment of Nuclear Propulsion Ship

    Energy Technology Data Exchange (ETDEWEB)

    Gil, Youngmi; Yoo, Seongjin; Kim, Yeontae; Oh, June; Byun, Yoonchul; Woo, Ilguk [Daewoo Shipbuilding and Marine Engineering Co. Ltd., Seoul (Korea, Republic of); Kim, Jiho; Choi, Suhn [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The nuclear propulsion ships (hereinafter referred to as 'nuclear ships') have been considered as an eco-friendly ship. There have historically been warship and submarine with the source of nuclear power. The use of nuclear ships has been recently extending to the icebreaker, the deep-water exploration ship, and the floating nuclear power plant. Prior to developing the new ship, we evaluated the economics of various types of ships and concluded that the container ship could be appropriate for the nuclear propulsion. In order to verify its safety, we performed the ship calculation based on the optimal arrangement of the nuclear reactor. Finally, we verified its safety by the HAZID. In the former research, we confirmed the applicability of the nuclear propulsion system for the large container ship. In this study, we verified the safety of the nuclear ships according to the HAZID analysis. We expect that this research will lead to safe design of the nuclear ships.

  14. Implementation Plan for the Office of Nuclear Energy Knowledge Management Program

    Energy Technology Data Exchange (ETDEWEB)

    Kimberlyn C. Mousseau

    2011-12-01

    The primary purpose of the Department of Energy (DOE), Office of Nuclear Energy (NE) Knowledge Management (KM) Program is to capture, share, disseminate, and ensure the ability to apply the knowledge created by the major nuclear energy Research and Development (R&D) programs. In support of the KM program, the Implementation Plan for the Office of NE KM Program outlines the knowledge management and distributed data environment that is required for its success. In addition to enumerating some strategic goals and objectives, this document characterizes the initial program and identifies computer-based areas of investment required for increased knowledge sharing and collaboration. It identifies and addresses investments already in existence and describes how these investments can be further enhanced and implemented to support a distributed KM program. The Idaho National Laboratory (INL) is leading the effort to identify and address these investments through the implementation of a distributed KM program that includes participants from ten of the major DOE national laboratories.

  15. Semi-annual status report of the Canadian Nuclear Fuel Waste Management Program, April 1--September 30, 1991

    Energy Technology Data Exchange (ETDEWEB)

    Wright, E.D. [comp.

    1992-02-01

    This report is the eleventh in a series of semi-annual status reports on the research and development program for the safe management and disposal of Canada's nuclear fuel waste. it describes progress achieved in the three major subprograms, engineered systems, natural systems and performance assessment, from 1991 April 1 to September 30. It also gives a brief description of the activities being carried out in preparation for the public and governmental review of the disposal concept. Since 1987, this program has been jointly funded by AECL and Ontario Hydro under the auspices of the CANDU Owners Group (COG).

  16. Second Language Proficiency Assessment and Program Evaluation.

    Science.gov (United States)

    Nunan, David

    A discussion of the role of second language proficiency assessment in the evaluation of language programs argues that for four reasons, the use of proficiency is inappropriate as a central element in evaluation. The reasons are: (1) the construct of proficiency has not been operationalized in a way that enables it to be used usefully; (2)…

  17. Assessing the Productivity of Human Service Programs.

    Science.gov (United States)

    Green, Rex S.

    2003-01-01

    Applied an alternative strategy for assessing the extent of change clients undergo as a result of receiving human services. Used the approach in a survey of parents of 61 young children in an art program. Findings show the feasibility of the service productivity approach. Psychometric properties of the approach were promising. (SLD)

  18. Implications of a North Korean Nuclear Weapons Program

    Energy Technology Data Exchange (ETDEWEB)

    Lehman, R.F. II

    1993-07-01

    The Democratic People`s Republic of Korea (DPRK) is one of the Cold War`s last remaining totalitarian regimes. Rarely has any society been as closed to outside influences and so distant from political, economic, and military developments around the globe. In 1991 and in 1992, however, this dictatorship took a number of political steps which increased Pyongyang`s interaction with the outside world. Although North Korea`s style of engagement with the broader international community involved frequent pauses and numerous steps backward, many observers believed that North Korea was finally moving to end its isolated, outlaw status. As the end of 1992 approached, however, delay and obstruction by Pyongyang became intense as accumulating evidence suggested that the DPRK, in violation of the nuclear Non-Proliferation Treaty (NPT), was seeking to develop nuclear weapons. On March 12, 1993, North Korea announced that it would not accept additional inspections proposed by the International Atomic Energy Agency (IAEA) to resolve concerns about possible violations and instead would withdraw from the Treaty. Pyongyang`s action raised the specter that, instead of a last act of the Cold War, North Korea`s diplomatic maneuvering would unravel the international norms that were to be the basis of stability and peace in the post-Cold War era. Indeed, the discovery that North Korea was approaching the capability to produce nuclear weapons suggested that the nuclear threat, which had been successfully managed throughout the Cold War era, could increase in the post-Cold War era.

  19. Research program in nuclear and solid state physics

    Science.gov (United States)

    Stronach, C. E.

    1973-01-01

    The spectra of prompt gamma rays emitted following nuclear pion absorption were studied to determine the states of excited daughter nuclei, and the branching ratios for these states. Studies discussed include the negative pion absorption of C-12, S-32, and N-14; and the positive pion absorption on 0-16. Abstracts of papers submitted to the conference of the American Physical Society are included.

  20. Nuclear safeguards research and development program. Status report, January--April 1977

    Energy Technology Data Exchange (ETDEWEB)

    Sapir, J.L. (comp.)

    1977-06-01

    The status of the Nuclear Safeguards Research and Development program pursued by LASL Safeguards Groups Q-1, Q-2, Q-3, and Q-4 is presented . Topics covered include nondestructive assay technology development and applications, international safeguards, perimeter safeguards and surveillance, concepts and subsystems development (e.g., DYMAC program), integrated safeguards systems, training courses, and technology transfer.

  1. Educational Programs and Facilities in Nuclear Science and Engineering. Fifth Edition.

    Science.gov (United States)

    Oak Ridge Associated Universities, TN.

    This publication contains detailed descriptions of nuclear programs and facilities of 182 four-year educational institutions. Instead of chapters, the contents are presented in five tables. Table I presents the degrees, graduate appointments, special facilities and programs of the institutions. The institutions are arranged in alphabetical order…

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

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

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

  3. Systems engineering programs for geologic nuclear waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Klett, R. D.; Hertel, Jr., E. S.; Ellis, M. A.

    1980-06-01

    The design sequence and system programs presented begin with general approximate solutions that permit inexpensive analysis of a multitude of possible wastes, disposal media, and disposal process properties and configurations. It then continues through progressively more precise solutions as parts of the design become fixed, and ends with repository and waste form optimization studies. The programs cover both solid and gaseous waste forms. The analytical development, a program listing, a users guide, and examples are presented for each program. Sensitivity studies showing the effects of disposal media and waste form thermophysical properties and repository layouts are presented as examples.

  4. Price-Anderson Nuclear Safety Enforcement Program. 1996 Annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    This first annual report on DOE`s Price Anderson Amendments Act enforcement program covers the activities, accomplishments, and planning for calendar year 1996. It also includes the infrastructure development activities of 1995. It encompasses the activities of the headquarters` Office of Enforcement in the Office of Environment, Safety and Health (EH) and Investigation and the coordinators and technical advisors in DOE`s Field and Program Offices and other EH Offices. This report includes an overview of the enforcement program; noncompliances, investigations, and enforcement actions; summary of significant enforcement actions; examples where enforcement action was deferred; and changes and improvements to the program.

  5. USCEA/NIST measurement assurance programs for the radiopharmaceutical and nuclear power industries

    Energy Technology Data Exchange (ETDEWEB)

    Golas, D.B. [Council for Energy Awareness, Washington, DC (United States)

    1993-12-31

    In cooperation with the U.S. Council for Energy Awareness (USCEA), the National Institute of Standards and Technology (NIST) supervises and administers two measurement assurance programs for radioactivity measurement traceability. One, in existence since the mid 1970s, provides traceability to suppliers of radiochemicals and radiopharmaceuticals, dose calibrators, and nuclear pharmacy services. The second program, begun in 1987, provides traceability to the nuclear power industry for utilities, source suppliers, and service laboratories. Each program is described, and the results of measurements of samples of known, but undisclosed activity, prepared at NIST and measured by the participants are presented.

  6. Recruiting program for the future R and D leader in nuclear science and technology

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Wonho; Kim, Inchul; Min, Hwanki; Park, Jungseung; Jung, Sung Hyon; Jeong, Bitna; Choi, Myound Jong

    2012-04-15

    The national projects of advanced nuclear system development are underway, however, there was little in their need for human resources in the development of nuclear industry and in the nuclear R and D program for the last 10 years. At the same time, a large portion of well-experienced expert in the national research institute and the industry, are getting old and retired, drastically. They faced an unbalanced situation in their supply and demand of human resources in the field of nuclear science and technology. Bring up the experts such as scientists and engineers in nuclear technology makes an important issue as a national agenda. Regardless of the economically stagnated situation in the country, KAERI(Korea Atomic Energy Research Institute) has hired young nuclear scientists and engineers continuously since 2006 last, in order to substitute the increasing retired experts. However, they need more well-brought-up nuclear scientists and engineers in the near future, as a leader of nuclear science and technology. Through this project, we try to recruit a leader of nuclear science and technology, who can create and carry out the world top class R and D programme.

  7. Automatic Nuclear Segmentation Using Multiscale Radial Line Scanning With Dynamic Programming.

    Science.gov (United States)

    Xu, Hongming; Lu, Cheng; Berendt, Richard; Jha, Naresh; Mandal, Mrinal

    2017-10-01

    In the diagnosis of various cancers by analyzing histological images, automatic nuclear segmentation is an important step. However, nuclear segmentation is a difficult problem because of overlapping nuclei, inhomogeneous staining, and presence of noisy pixels and other tissue components. In this paper, we present an automatic technique for nuclear segmentation in skin histological images. The proposed technique first applies a bank of generalized Laplacian of Gaussian kernels to detect nuclear seeds. Based on the detected nuclear seeds, a multiscale radial line scanning method combined with dynamic programming is applied to extract a set of candidate nuclear boundaries. The gradient, intensity, and shape information are then integrated to determine the optimal boundary for each nucleus in the image. Nuclear overlap limitation is finally imposed based on a Dice coefficient measure such that the obtained nuclear contours do not severely intersect with each other. Experiments have been thoroughly performed on two datasets with H&E and Ki-67 stained images, which show that the proposed technique is superior to conventional schemes of nuclear segmentation.

  8. Nuclear cardiac imaging for the assessment of myocardial viability.

    Science.gov (United States)

    Slart, R H J A; Bax, J J; van der Wall, E E; van Veldhuisen, D J; Jager, P L; Dierckx, R A

    2005-11-01

    An important aspect of the diagnostic and prognostic work-up of patients with ischaemic cardiomyopathy is the assessment of myocardial viability. Patients with left ventricular dysfunction who have viable myocardium are the patients at highest risk because of the potential for ischaemia but at the same time benefit most from revascularisation. It is important to identify viable myocardium in these patients, and radionuclide myocardial scintigraphy is an excellent tool for this. Single-photon emission computed tomography perfusion scintigraphy (SPECT), whether using 201thallium, 99mTc-sestamibi, or 99mTc- tetrofosmin, in stress and/or rest protocols, has consistently been shown to be an effective modality for identifying myocardial viability and guiding appropriate management. Metabolic and perfusion imaging with positron emission tomography radiotracers frequently adds additional information and is a powerful tool for predicting which patients will have an improved outcome from revascularisation. New techniques in the nuclear cardiology field, such as attenuation corrected SPECT, dual isotope simultaneous acquisition (DISA) SPECT and gated FDG PET are promising and will further improve the detection of myocardial viability. Also the combination of multislice computed tomography scanners with PET opens possibilities of adding coronary calcium scoring and noninvasive coronary angiography to myocardial perfusion imaging and quantification.

  9. ENVIRONMENTAL ASSESSMENT METHODOLOGY FOR THE NUCLEAR FUEL CYCLE

    Energy Technology Data Exchange (ETDEWEB)

    Brenchley, D. L.; Soldat, J. K.; McNeese, J. A.; Watson, E. C.

    1977-07-01

    This report describes the methodology for determining where environmental control technology is required for the nuclear fuel cycle. The methodology addresses routine emission of chemical and radioactive effluents, and applies to mining, milling, conversion, enrichment, fuel fabrication, reactors (LWR and BWR) and fuel reprocessing. Chemical and radioactive effluents are evaluated independently. Radioactive effluents are evaluated on the basis of maximum exposed individual dose and population dose calculations for a 1-year emission period and a 50-year commitment. Sources of radionuclides for each facility are then listed according to their relative contribution to the total calculated dose. Effluent, ambient and toxicology standards are used to evaluate the effect of chemical effluents. First, each chemical and source configuration is determined. Sources are tagged if they exceed existirrg standards. The combined effect of all chemicals is assessed for each facility. If the additive effects are unacceptable, then additional control technology is recommended. Finally, sources and their chemicals at each facility are ranked according to their relative contribution to the ambient pollution level. This ranking identifies those sources most in need of environmental control.

  10. Drug and alcohol abuse: the bases for employee assistance programs in the nuclear-utility industry

    Energy Technology Data Exchange (ETDEWEB)

    Radford, L.R.; Rankin, W.L.; Barnes, V.; McGuire, M.V.; Hope, A.M.

    1983-07-01

    This report describes the nature, prevalence, and trends of drug and alcohol abuse among members of the US adult population and among personnel in non-nuclear industries. Analogous data specific to the nuclear utility industry are not available, so these data were gathered in order to provide a basis for regulatory planning. The nature, prevalence, and trend inforamtion was gathered using a computerized literature, telephone discussions with experts, and interviews with employee assistance program representatives from the Seattle area. This report also evaluates the possible impacts that drugs and alcohol might have on nuclear-related job performance, based on currently available nuclear utility job descriptions and on the scientific literature regarding the impairing effects of drugs and alcohol on human performance. Employee assistance programs, which can be used to minimize or eliminate job performance decrements resulting from drug or alcohol abuse, are also discussed.

  11. Topics in nuclear and radiochemistry for college curricula and high school science programs

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    The concern with the current status and trends of nuclear chemistry and radiochemistry education in academic institutions was addressed in a recent workshop. The 1988 workshop considered the important contributions that scientist with nuclear and radiochemistry backgrounds have made and are continuing to make to other sciences and to various applied fields. Among the areas discussed were environmental studies, life sciences, materials science, separation technology, hot atom chemistry, cosmochemistry, and the rapidly growing field of nuclear medicine. It is intent of the organizer and participants of this symposium entitled Topics in Nuclear and Radiochemistry for College Curricula and High School Science Program'' to provide lecture material on topics related to nuclear and radiochemistry to educators. It is our hope that teachers, who may or may not be familiar with the field, will find this collections of articles useful and incorporate some of them into their lectures.

  12. Evaluation of Millstone Nuclear Power Plant, Environmental Impact prediction, based on monitoring programs

    Energy Technology Data Exchange (ETDEWEB)

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

    1977-02-01

    This report evaluates the nonradiological monitoring program at Millstone Nuclear Power Plant. Both operational as well as preoperational monitoring programs were analyzed to produce long-term (5 yr or longer) data sets, where possible. In order to determine the effectiveness of these monitoring programs, the appropriate data sets have to be analyzed by the appropriate statistical analysis. Thus, both open literature and current statistical analysis being developed at Pacific Northwest Laboratories (PNL) were employed in data analysis.

  13. Improving Insider Threat Training Awareness and Mitigation Programs at Nuclear Facilities.

    Energy Technology Data Exchange (ETDEWEB)

    Abbott, Shannon [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-06-01

    In recent years, insider threat programs have become an important aspect of nuclear security, and nuclear security training courses. However, many nuclear security insider threat programs fail to address the insider threat attack and monitoring potential that exists on information technology (IT) systems. This failure is critical because of the importance of information technology and networks in today’s world. IT systems offer an opportunity to perpetrate dangerous insider attacks, but they also present an opportunity to monitor for them and prevent them. This paper suggests a number of best practices for monitoring and preventing insider attacks on IT systems, and proposes the development of a new IT insider threat tabletop that can be used to help train nuclear security practitioners on how best to implement IT insider threat prevention best practices. The development of IT insider threat best practices and a practical tabletop exercise will allow nuclear security practitioners to improve nuclear security trainings as it integrates a critical part of insider threat prevention into the broader nuclear security system.

  14. Update: nuclear power program information and data, April-June 1982

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interst to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office.

  15. UPDATE: nuclear power program information and data, July-September 1981

    Energy Technology Data Exchange (ETDEWEB)

    DOE/NBM--6011986

    1981-01-01

    UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATA is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office.

  16. Update: nuclear power program information and data, March-April 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office.

  17. The Effects of a Demonstration School Program on Nuclear Energy for Elementary School Students in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Han, EunOk; Lee, Seung Koo; Choi, Yoon Seok [Korea Academy of Nuclear Safety, Seoul (Korea, Republic of)

    2016-10-15

    Advancing nuclear energy and radiation technology to drive the country forward should be based on the understanding and acceptance of the public. Korea has provided numerous types of information to increase public acceptance of nuclear energy, but it has been difficult to change adults’ perceptions and increase their acceptance of nuclear energy. As a result, social costs are rising. After a pilot program of 13 classes on understanding nuclear energy and radiation offered to elementary school students, who were expected to easily change their perceptions and to experience a relatively greater educational effect, this study analyzed changes to knowledge, attitudes, and behaviors regarding nuclear energy. In addition, this program was the first curriculum of its kind used as a step to lay the groundwork for offering it nationally in the free semester system. Therefore, the study analyzed its appropriateness to educational purposes. A lack of research and practice on communication strategies could be responsible for the situation in Korea of low support for nuclear energy because Korea does not have public understanding even though it is a nuclear energy exporter. If Korea implemented strategic communications from this point, such efforts could reduce unnecessary social costs.

  18. Development of a computational database for probabilistic safety assessment of nuclear research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Macedo, Vagner S.; Oliveira, Patricia S. Pagetti de; Andrade, Delvonei Alves de, E-mail: vagner.macedo@usp.br, E-mail: patricia@ipen.br, E-mail: delvonei@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The objective of this work is to describe the database being developed at IPEN - CNEN / SP for application in the Probabilistic Safety Assessment of nuclear research reactors. The database can be accessed by means of a computational program installed in the corporate computer network, named IPEN Intranet, and this access will be allowed only to professionals previously registered. Data updating, editing and searching tasks will be controlled by a system administrator according to IPEN Intranet security rules. The logical model and the physical structure of the database can be represented by an Entity Relationship Model, which is based on the operational routines performed by IPEN - CNEN / SP users. The web application designed for the management of the database is named PSADB. It is being developed with MySQL database software and PHP programming language is being used. Data stored in this database are divided into modules that refer to technical specifications, operating history, maintenance history and failure events associated with the main components of the nuclear facilities. (author)

  19. Technical Basis Spent Nuclear Fuel (SNF) Project Radiation and Contamination Trending Program

    Energy Technology Data Exchange (ETDEWEB)

    ELGIN, J.C.

    2000-10-02

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, radiation surveys of the Cold Vacuum Drying Facility (CVD), and radiation surveys of the Canister Storage Building (CSB) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas.

  20. Assessment of the current status of basic nuclear data compilations

    Energy Technology Data Exchange (ETDEWEB)

    Riemer, R.L.

    1992-12-31

    The Panel on Basic Nuclear Data Compilations believes that it is important to provide the user with an evaluated nuclear database of the highest quality, dependability, and currency. It is also important that the evaluated nuclear data are easily accessible to the user. In the past the panel concentrated its concern on the cycle time for the publication of A-chain evaluations. However, the panel now recognizes that publication cycle time is no longer the appropriate goal. Sometime in the future, publication of the evaluated A-chains will evolve from the present hard-copy Nuclear Data Sheets on library shelves to purely electronic publication, with the advent of universal access to terminals and the nuclear databases. Therefore, the literature cut-off date in the Evaluated Nuclear Structure Data File (ENSDF) is rapidly becoming the only important measure of the currency of an evaluated A-chain. Also, it has become exceedingly important to ensure that access to the databases is as user-friendly as possible and to enable electronic publication of the evaluated data files. Considerable progress has been made in these areas: use of the on-line systems has almost doubled in the past year, and there has been initial development of tools for electronic evaluation, publication, and dissemination. Currently, the nuclear data effort is in transition between the traditional and future methods of dissemination of the evaluated data. Also, many of the factors that adversely affect the publication cycle time simultaneously affect the currency of the evaluated nuclear database. Therefore, the panel continues to examine factors that can influence cycle time: the number of evaluators, the frequency with which an evaluation can be updated, the review of the evaluation, and the production of the evaluation, which currently exists as a hard-copy issue of Nuclear Data Sheets.

  1. Application of fisheries management techniques to assessing impacts: task I report. [Assessment of chemical, radiological, and thermal impacts of nuclear power plants on fish populations

    Energy Technology Data Exchange (ETDEWEB)

    McKenzie, D.H.; Baker, K.S.; Fickeisen, D.H.; Metzger, R.M.; Skalski, J.R.

    1979-03-01

    Task I efforts examined the available fisheries management techniques and assessed their potential application in a confirmatory monitoring program. The objective of such monitoring programs is to confirm that the prediction of an insignificant impact (usually made in the FES) was correct. Fisheries resource managers have developed several tools for assessing the fish population response to stress (exploitation) and they were thought potentially useful for detecting nuclear power plant impacts. Techniques in three categories were examined; catch removal, population dynamics, and nondestructive censuses, and the report contains their description, examples of application, advantages, and disadvantages. The techniques applied at nuclear power plant sites were examined in detail to provide information on implementation and variability of specific approaches. The most suitable techniques to incorporate into a monitoring program confirming no impact appear to be those based on Catch Per Unity Effort (CPUE) and hydroacoustic data. In some specific cases, age and growth studies and indirect census techniques may be beneficial. Recommendations for task II efforts to incorporate these techniques into monitoring program designs are presented. These include development of guidelines for; (1) designing and implementing a data collection program; (2) interpreting these data and assessing the occurrence of impact, and (3) establishment of the monitoring program's ability to detect changes in the affected populations.

  2. 7 CFR 37.11 - Publication of program assessment status.

    Science.gov (United States)

    2010-01-01

    ... CONTAINER REGULATIONS PROGRAM TO ASSESS ORGANIC CERTIFYING AGENCIES § 37.11 Publication of program... assessment; effective date of assessment; and control number(s) of official certificate(s), as applicable. (b...

  3. Assessment of Radiation Exposure Dose Due to the Operation of Daeduk Nuclear Facilities.

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Won Tae; Lee, Young Bok; Han, Moon Hee; Kim, Eun Han; Suh, Kyung Suk; Choi, Young Gil [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1998-02-01

    The objective of this project is to assure the public acceptance for nuclear facilities and the environmental safety of Daeduk nuclear facilities, such as HANARO research reactor, nuclear fuel processing facility and other. For the assessment of the safety, the maximum individual doses at the site boundary and on the areas of high population density were assessed. Also, the population doses within radius 80 km from the site were investigated. The radiation impacts for residents around the site due to the operation of nuclear facilities in 1997 were neglectable. 9 refs., 43 tabs., 14 figs. (author)

  4. Integrative Curriculum Development in Nuclear Education and Research Vertical Enhancement Program

    Energy Technology Data Exchange (ETDEWEB)

    Egarievwe, Stephen U.; Jow, Julius O.; Edwards, Matthew E.; Montgomery, V. Trent [Nuclear Engineering and Radiological Science Center, Alabama A and M University, Huntsville, AL (United States); James, Ralph B.; Blackburn, Noel D. [Nonproliferation and National Security Department, Brookhaven National Laboratory, Upton, NY (United States); Glenn, Chance M. [College of Engineering, Technology and Physical Sciences, Alabama A and M University, Huntsville, AL (United States)

    2015-07-01

    Using a vertical education enhancement model, a Nuclear Education and Research Vertical Enhancement (NERVE) program was developed. The NERVE program is aimed at developing nuclear engineering education and research to 1) enhance skilled workforce development in disciplines relevant to nuclear power, national security and medical physics, and 2) increase the number of students and faculty from underrepresented groups (women and minorities) in fields related to the nuclear industry. The program uses multi-track training activities that vertically cut across the several education domains: undergraduate degree programs, graduate schools, and post-doctoral training. In this paper, we present the results of an integrative curriculum development in the NERVE program. The curriculum development began with nuclear content infusion into existing science, engineering and technology courses. The second step involved the development of nuclear engineering courses: 1) Introduction to Nuclear Engineering, 2) Nuclear Engineering I, and 2) Nuclear Engineering II. The third step is the establishment of nuclear engineering concentrations in two engineering degree programs: 1) electrical engineering, and 2) mechanical engineering. A major outcome of the NERVE program is a collaborative infrastructure that uses laboratory work, internships at nuclear facilities, on-campus research, and mentoring in collaboration with industry and government partners to provide hands-on training for students. The major activities of the research and education collaborations include: - One-week spring training workshop at Brookhaven National Laboratory: The one-week training and workshop is used to enhance research collaborations and train faculty and students on user facilities/equipment at Brookhaven National Laboratory, and for summer research internships. Participants included students, faculty members at Alabama A and M University and research collaborators at BNL. The activities include 1) tour and

  5. Next Generation Nuclear Plant Methods Research and Development 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

    2008-09-01

    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.

  6. Perceptions of a National Achievement Assessment Program

    Directory of Open Access Journals (Sweden)

    Marielle Simon

    2002-10-01

    Full Text Available The School Achievement Indicators Program (SAIP has been collecting data across Canada on 13- and 16-year-old student achievement in mathematics, in science, and in reading and writing since 1993. In 1999, it completed its second assessment cycle and was reviewed in Spring 2000. The review design included a survey of officials from all the school boards/districts that participated in the science assessment program held in 1999. The results of this study show that this stakeholder views as the most pressing issue for SAIP to succeed in its mandate, the need for development in four areas: a Increased teacher and student motivation to participate wholeheartedly in the program; b Effective dissemination options; c Leadership through innovation in teaching and in assessment practices despite high accountability orientation; and d Cost-effective, yet rigorous means of providing both snapshot information and longitudinal means of comparisons. Although universally appealing, such approaches have yet to be supported by sound educational theory and methodology.

  7. Impact of structural aging on seismic risk assessment of reinforced concrete structures in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ellingwood, B.; Song, J. [Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Civil Engineering

    1996-03-01

    The Structural Aging Program is addressing the potential for degradation of concrete structural components and systems in nuclear power plants over time due to aging and aggressive environmental stressors. Structures are passive under normal operating conditions but play a key role in mitigating design-basis events, particularly those arising from external challenges such as earthquakes, extreme winds, fires and floods. Structures are plant-specific and unique, often are difficult to inspect, and are virtually impossible to replace. The importance of structural failures in accident mitigation is amplified because such failures may lead to common-cause failures of other components. Structural condition assessment and service life prediction must focus on a few critical components and systems within the plant. Components and systems that are dominant contributors to risk and that require particular attention can be identified through the mathematical formalism of a probabilistic risk assessment, or PRA. To illustrate, the role of structural degradation due to aging on plant risk is examined through the framework of a Level 1 seismic PRA of a nuclear power plant. Plausible mechanisms of structural degradation are found to increase the core damage probability by approximately a factor of two.

  8. Environmental Impact Assessment for Olkiluoto 4 Nuclear Power Plant Unit in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Dersten, Riitta; Gahmberg, Sini; Takala, Jenni [Teollisuuden Voima Oyj, Olkiluoto, FI-27160 Eurajoki (Finland)

    2008-07-01

    In order to improve its readiness for constructing additional production capacity, Teollisuuden Voima Oyj (TVO) initiated in spring 2007 the environmental impact assessment procedure (EIA procedure) concerning a new nuclear power plant unit that would possibly be located at Olkiluoto. When assessing the environmental impacts of the Olkiluoto nuclear power plant extension project, the present state of the environment was first examined, and after that, the changes caused by the projects as well as their significance were assessed, taking into account the combined impacts of the operations at Olkiluoto. The environmental impact assessment for the planned nuclear power plant unit covers the entire life cycle of the plant unit. (authors)

  9. Review of the Tri-Agency Space Nuclear Reactor Power System Technology Program

    Science.gov (United States)

    Ambrus, J. H.; Wright, W. E.; Bunch, D. F.

    1984-01-01

    The Space Nuclear Reactor Power System Technology Program designated SP-100 was created in 1983 by NASA, the U.S. Department of Defense, and the Defense Advanced Research Projects Agency. Attention is presently given to the development history of SP-100 over the course of its first year, in which it has been engaged in program objectives' definition, the analysis of civil and military missions, nuclear power system functional requirements' definition, concept definition studies, the selection of primary concepts for technology feasibility validation, and the acquisition of initial experimental and analytical results.

  10. Seventy Years of Computing in the Nuclear Weapons Program

    Energy Technology Data Exchange (ETDEWEB)

    Archer, Billy Joe [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-05-30

    Los Alamos has continuously been on the forefront of scientific computing since it helped found the field. This talk will explore the rich history of computing in the Los Alamos weapons program. The current status of computing will be discussed, as will the expectations for the near future.

  11. Materials for Nuclear Plants From Safe Design to Residual Life Assessments

    CERN Document Server

    Hoffelner, Wolfgang

    2013-01-01

    The clamor for non-carbon dioxide emitting energy production has directly  impacted on the development of nuclear energy. As new nuclear plants are built, plans and designs are continually being developed to manage the range of challenging requirement and problems that nuclear plants face especially when managing the greatly increased operating temperatures, irradiation doses and extended design life spans. Materials for Nuclear Plants: From Safe Design to Residual Life Assessments  provides a comprehensive treatment of the structural materials for nuclear power plants with emphasis on advanced design concepts.   Materials for Nuclear Plants: From Safe Design to Residual Life Assessments approaches structural materials with a systemic approach. Important components and materials currently in use as well as those which can be considered in future designs are detailed, whilst the damage mechanisms responsible for plant ageing are discussed and explained. Methodologies for materials characterization, material...

  12. Laboratory Directed Research and Development Program Assessment for FY 2008

    Energy Technology Data Exchange (ETDEWEB)

    Looney, J P; Fox, K J

    2008-03-31

    Brookhaven National Laboratory (BNL) is a multidisciplinary Laboratory that carries out basic and applied research in the physical, biomedical, and environmental sciences, and in selected energy technologies. It is managed by Brookhaven Science Associates, LLC, (BSA) under contract with the U. S. Department of Energy (DOE). BNL's Fiscal Year 2008 spending was $531.6 million. There are approximately 2,800 employees, and another 4,300 guest scientists and students who come each year to use the Laboratory's facilities and work with the staff. The BNL Laboratory Directed Research and Development (LDRD) Program reports its status to the U.S. Department of Energy (DOE) annually in March, as required by DOE Order 413.2B, 'Laboratory Directed Research and Development,' April 19, 2006, and the Roles, Responsibilities, and Guidelines for Laboratory Directed Research and Development at the Department of Energy/National Nuclear Security Administration Laboratories dated June 13, 2006. The goals and objectives of BNL's LDRD Program can be inferred from the Program's stated purposes. These are to (1) encourage and support the development of new ideas and technology, (2) promote the early exploration and exploitation of creative and innovative concepts, and (3) develop new 'fundable' R&D projects and programs. The emphasis is clearly articulated by BNL to be on supporting exploratory research 'which could lead to new programs, projects, and directions' for the Laboratory. To be a premier scientific Laboratory, BNL must continuously foster groundbreaking scientific research and renew its research agenda. The competition for LDRD funds stimulates Laboratory scientists to think in new and creative ways, which becomes a major factor in achieving and maintaining research excellence and a means to address National needs within the overall mission of the DOE and BNL. By fostering high-risk, exploratory research, the LDRD program helps

  13. A study on the Secondary School Teacher's Perception Change for Nuclear Power through an Experiment Practice Program

    Energy Technology Data Exchange (ETDEWEB)

    Lee, ByungChae; Kim, JuHyun; Na, JungHyun; Yoo, DaYoung; Kim, WoongKi [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    It is important to correct mis-understanding perception of general public for nuclear power for development of nuclear industry and the nation‟s advancement. It is required to provide secondary school students and teachers with correct information by learning activities in addition to mass media and textbook. If teachers have wrong concept, students are affected by the negative impact. Therefore, teachers should understand nuclear power correctly. KAERI(Korea Atomic Energy Research Institute) has served an education program entitled „to understand nuclear power correctly by experiment and practice‟ as an practice and improvement program for the secondary school teachers. We checked the change of the secondary teacher‟s recognition for nuclear power by the survey. In this study, we checked the change of the secondary school teacher‟s recognition level for nuclear power by the survey before and after the education program. Nuclear Perception level was increased by 8% showing optimistic mind for the safety, dangerousness, and necessity of nuclear power plants after the education. Nuclear knowledge level also went up 15% through the education program. It is concluded that the nuclear perception of the secondary school teachers can be improved through the education program for nuclear power. Secondary school students form general public in the future. Perception of the students is influenced by teachers deeply.

  14. Science in Flux: NASA's Nuclear Program at Plum Brook Station 1955-2005

    Science.gov (United States)

    Bowles, Mark D.

    2006-01-01

    Science in Flux traces the history of one of the most powerful nuclear test reactors in the United States and the only nuclear facility ever built by NASA. In the late 1950's NASA constructed Plum Brook Station on a vast tract of undeveloped land near Sandusky, Ohio. Once fully operational in 1963, it supported basic research for NASA's nuclear rocket program (NERVA). Plum Brook represents a significant, if largely forgotten, story of nuclear research, political change, and the professional culture of the scientists and engineers who devoted their lives to construct and operate the facility. In 1973, after only a decade of research, the government shut Plum Brook down before many of its experiments could be completed. Even the valiant attempt to redefine the reactor as an environmental analysis tool failed, and the facility went silent. The reactors lay in costly, but quiet standby for nearly a quarter-century before the Nuclear Regulatory Commission decided to decommission the reactors and clean up the site. The history of Plum Brook reveals the perils and potentials of that nuclear technology. As NASA, Congress, and space enthusiasts all begin looking once again at the nuclear option for sending humans to Mars, the echoes of Plum Brook's past will resonate with current policy and space initiatives.

  15. Origins of the tactical nuclear weapons modernization program: 1969-1979

    Energy Technology Data Exchange (ETDEWEB)

    Yaffe, M.D.

    1991-01-01

    On December 12, 1979 NATO decided to deploy new long-range theater nuclear forces. This marked the first major change in NATO's nuclear stockpile since the adoption of the flexible-response strategy in 1967. The decision was controversial inasmuch as the Allies disagreed on the fundamental role of nuclear weapons in this strategy and, thereby, the types and number of weapons required for an effective deterrent posture. Thus, the decision is often described as purely politically motivated, in which the Americans reluctantly acquiesced to a European initiative for long-range weapons, prominently expressed by West German Chancellor Helmut Schmidt in 1977. Recently declassified US government documents reveal, however, that long-range missiles were part of a long-term comprehensive nuclear-modernization program conceived in the Pentagon during the period of 1973 through 1975, and presented to skeptical European elites who favored arms-control negotiations over costly new deployments.

  16. Identification and Analysis of Critical Gaps in Nuclear Fuel Cycle Codes Required by the SINEMA Program

    Energy Technology Data Exchange (ETDEWEB)

    Adrian Miron; Joshua Valentine; John Christenson; Majd Hawwari; Santosh Bhatt; Mary Lou Dunzik-Gougar: Michael Lineberry

    2009-10-01

    The current state of the art in nuclear fuel cycle (NFC) modeling is an eclectic mixture of codes with various levels of applicability, flexibility, and availability. In support of the advanced fuel cycle systems analyses, especially those by the Advanced Fuel Cycle Initiative (AFCI), Unviery of Cincinnati in collaboration with Idaho State University carried out a detailed review of the existing codes describing various aspects of the nuclear fuel cycle and identified the research and development needs required for a comprehensive model of the global nuclear energy infrastructure and the associated nuclear fuel cycles. Relevant information obtained on the NFC codes was compiled into a relational database that allows easy access to various codes' properties. Additionally, the research analyzed the gaps in the NFC computer codes with respect to their potential integration into programs that perform comprehensive NFC analysis.

  17. ELECTRIC INFRASTRUCTURE TECHNOLOGY, TRAINING, AND ASSESSMENT PROGRAM

    Energy Technology Data Exchange (ETDEWEB)

    TREMEL, CHARLES L

    2007-06-28

    The objective of this Electric Infrastructure Technology, Training and Assessment Program was to enhance the reliability of electricity delivery through engineering integration of real-time technologies for wide-area applications enabling timely monitoring and management of grid operations. The technologies developed, integrated, tested and demonstrated will be incorporated into grid operations to assist in the implementation of performance-based protection/preventive measures into the existing electric utility infrastructure. This proactive approach will provide benefits of reduced cost and improved reliability over the typical schedule-based and as needed maintenance programs currently performed by utilities. Historically, utilities have relied on maintenance and inspection programs to diagnose equipment failures and have used the limited circuit isolation devices, such as distribution main circuit breakers to identify abnormal system performance. With respect to reliable problem identification, customer calls to utility service centers are often the sole means for utilities to identify problem occurrences and determine restoration methodologies. Furthermore, monitoring and control functions of equipment and circuits are lacking; thus preventing timely detection and response to customer outages. Finally, the two-way flow of real-time system information is deficient, depriving decision makers of key information required to effectively manage and control current electric grid demands to provide reliable customer service in abnormal situations. This Program focused on advancing technologies and the engineering integration required to incorporate them into the electric grid operations to enhance electrical system reliability and reduce utility operating costs.

  18. Overview of nuclear education and outreach program among Malaysian school students

    Science.gov (United States)

    Sahar, Haizum Ruzanna; Masngut, Nasaai; Yusof, Mohd Hafizal; Ngadiron, Norzehan; Adnan, Habibah

    2017-01-01

    This paper gives an overview of nuclear education and outreach program conducted by Agensi Nuklear Malaysia (Nuklear Malaysia) throughout its operation and establishment. Since its foundation in 1972, Nuklear Malaysia has been the pioneer and is competent in the application of nuclear science and technology. Today, Nuklear Malaysia has ventured and eventually contributed into the development of various socio-economic sectors which include but not limited to medical, industry, manufacturing, agriculture, health, radiation safety and environment. This paper accentuates on the history of education and outreach program by Nuklear Malaysia, which include its timeline and evolution; as well as a brief on education and outreach program management, involvement of knowledge management as part of its approach and later the future of Nuklear Malaysia education and outreach program.

  19. 75 FR 73135 - Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant, Environmental Assessment...

    Science.gov (United States)

    2010-11-29

    ... licensee), for operation of the Joseph M. Farley Nuclear Plant, Units 1 and 2 (FNP), located in Houston... the FNP from the required implementation date of March 31, 2010, for several new requirements of 10 CFR Part 73. Specifically, FNP would be granted an exemption from being in full compliance with...

  20. Assessment of Space Nuclear Thermal Propulsion Facility and Capability Needs

    Energy Technology Data Exchange (ETDEWEB)

    James Werner

    2014-07-01

    The development of a Nuclear Thermal Propulsion (NTP) system rests heavily upon being able to fabricate and demonstrate the performance of a high temperature nuclear fuel as well as demonstrating an integrated system prior to launch. A number of studies have been performed in the past which identified the facilities needed and the capabilities available to meet the needs and requirements identified at that time. Since that time, many facilities and capabilities within the Department of Energy have been removed or decommissioned. This paper provides a brief overview of the anticipated facility needs and identifies some promising concepts to be considered which could support the development of a nuclear thermal propulsion system. Detailed trade studies will need to be performed to support the decision making process.

  1. ORNL Nuclear Safety Research and Development Program Bimonthly Report for July-August 1968

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.

    2001-08-17

    The accomplishments during the months of July and August in the research and development program under way at ORNL as part of the U.S. Atomic Energy Commission's Nuclear Safety Program are summarized, Included in this report are work on various chemical reactions, as well as the release, characterization, and transport of fission products in containment systems under various accident conditions and on problems associated with the removal of these fission products from gas streams. Although most of this work is in general support of water-cooled power reactor technology, including LOFT and CSE programs, the work reflects the current safety problems, such as measurements of the prompt fuel element failure phenomena and the efficacy of containment spray and pool-suppression systems for fission-product removal. Several projects are also conducted in support of the high-temperature gas-cooled reactor (HTGR). Other major projects include fuel-transport safety investigations, a series of discussion papers on various aspects of water-reactor technology, antiseismic design of nuclear facilities, and studies of primary piping and steel, pressure-vessel technology. Experimental work relative to pressure-vessel technology includes investigations of the attachment of nozzles to shells and the implementation of joint AEX-PVFX programs on heavy-section steel technology and nuclear piping, pumps, and valves. Several of the projects are directly related to another major undertaking; namely, the AEC's standards program, which entails development of engineering safeguards and the establishment of codes and standards for government-owned or -sponsored reactor facilities. Another task, CHORD-S, is concerned with the establishment of computer programs for the evaluation of reactor design data, The recent activities of the NSIC and the Nuclear Safety journal in behalf of the nuclear community are also discussed.

  2. Desertification risk assessment and management program

    Directory of Open Access Journals (Sweden)

    M. Akbari

    2016-12-01

    Full Text Available Risk assessment provides the possibility of planning and management to prevent and reduce the risk of desertification. The present study is aimed to assess the hazard and risk of desertification and to develop management programs in the semi-arid western regions of Golestan Province in Iran. Desertification rate was obtained using the Iranian model of desertification potential assessment. Since the rating system was considered for the indicators, data analyses were carried out according to the Mann-Whitney test. The risk of desertification was calculated based on hazard, elements at risk and vulnerability assessment maps. The intensity of desertification was estimated to be medium. Among the factors affecting desertification, agriculture by the weighted average of 3.22 had the highest effect, followed by soil, vegetation, water and wind erosion criteria by weighted averages of 2.45, 2.32, 2.15 and 1.6 respectively. Desertification risk assessment results also showed that about 78% of central and northern parts of the region, with the largest population and residential centers, surface and underground water resources, agriculture and horticulture, is confronted with a high to very high degree of risk. Management plans and control measures, based on risk values were presented in four activities (with two management priorities under critical and non-critical conditions. For the management program with the largest area. Control measures and strategies such as the establishment of halophytic and xerophytic plants, drainage networks, resilient facilities and infrastructure were proposed. Reducing the risk of desertification, could play a crucial role in the sustainable development of drylands and desert ecosystems.

  3. Summary of inspection findings of licensee inservice testing programs at United States commercial nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Dunlop, A.; Colaccino, J.

    1996-12-01

    Periodic inspections of pump and valve inservice testing (IST) programs in United States commercial nuclear power plants are performed by Nuclear Regulatory Commission (NRC) Regional Inspectors to verify licensee regulatory compliance and licensee commitments. IST inspections are conducted using NRC Inspection Procedure 73756, {open_quotes}Inservice Testing of Pumps and Valves{close_quotes} (IP 73756), which was updated on July 27, 1995. A large number of IST inspections have also been conducted using Temporary Instruction 2515/114, {open_quotes}Inspection Requirements for Generic Letter 89-04, Acceptable Inservice Testing Programs{close_quotes} (TI-2515/114), which was issued January 15, 1992. A majority of U.S. commercial nuclear power plants have had an IST inspection to either IP 73756 or TI 2515/114. This paper is intended to summarize the significant and recurring findings from a number of these inspections since January of 1990.

  4. DOE role in nuclear policies and programs: official transcript of public briefing, December 13, 1977

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-02-01

    The record for the first of the public briefings in the Consumer Information Series scheduled by the Department of Energy is presented. The series presents, for public information and discussion, those DOE policies and programs of specific interest to consumers and public interest groups. In the first meeting DOE officials responded to questions from the public on the DOE role in nuclear policies and programs.

  5. Assessment of nuclear reactor concepts for low power space applications

    Science.gov (United States)

    Klein, Andrew C.; Gedeon, Stephen R.; Morey, Dennis C.

    1988-01-01

    The results of a preliminary small reactor concepts feasibility and safety evaluation designed to provide a first order validation of the nuclear feasibility and safety of six small reactor concepts are given. These small reactor concepts have potential space applications for missions in the 1 to 20 kWe power output range. It was concluded that low power concepts are available from the U.S. nuclear industry that have the potential for meeting both the operational and launch safety space mission requirements. However, each design has its uncertainties, and further work is required. The reactor concepts must be mated to a power conversion technology that can offer safe and reliable operation.

  6. 77 FR 51071 - Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit 2, Environmental Assessment...

    Science.gov (United States)

    2012-08-23

    ... COMMISSION Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit 2, Environmental Assessment and... Indiana Michigan Power Company (the licensee), for operation of Donald C. Cook Nuclear Plant, Unit 2 (CNP... exemption, these proposed actions do not result in changes to land use or water use, or result in changes to...

  7. 75 FR 9955 - Entergy Operations, Inc.; Grand Gulf Nuclear Station, Unit 1; Environmental Assessment and...

    Science.gov (United States)

    2010-03-04

    ... COMMISSION Entergy Operations, Inc.; Grand Gulf Nuclear Station, Unit 1; Environmental Assessment and Finding... protection of plants and materials,'' for Facility Operating License No. DPR-46, issued to Entergy Operations, Inc. (Entergy, the licensee), for operation of the Grand Gulf Nuclear Station, Unit 1 (GGNS), located...

  8. LABORATORY DIRECTED RESEARCH AND DEVELOPMENT PROGRAM ASSESSMENT FOR FY 2006.

    Energy Technology Data Exchange (ETDEWEB)

    FOX,K.J.

    2006-01-01

    Brookhaven National Laboratory (BNL) is a multidisciplinary laboratory that carries out basic and applied research in the physical, biomedical, and environmental sciences, and in selected energy technologies. It is managed by Brookhaven Science Associates, LLC, (BSA) under contract with the U. S. Department of Energy (DOE). BNL's total annual budget has averaged about $460 million. There are about 2,500 employees, and another 4,500 guest scientists and students who come each year to use the Laboratory's facilities and work with the staff. The BNL Laboratory Directed Research and Development (LDRD) Program reports its status to the U.S. Department of Energy (DOE) annually in March, as required by DOE Order 413.2B, ''Laboratory Directed Research and Development,'' April 19,2006, and the Roles, Responsibilities, and Guidelines for Laboratory Directed Research and Development at the Department of Energy National Nuclear Security Administration Laboratories dated June 13,2006. The goals and' objectives of BNL's LDRD Program can be inferred from the Program's stated purposes. These are to (1) encourage and support the development of new ideas and technology, (2) promote the early exploration and exploitation of creative and innovative concepts, and (3) develop new ''fundable'' R&D projects and programs. The emphasis is clearly articulated by BNL to be on supporting exploratory research ''which could lead to new programs, projects, and directions'' for the Laboratory. As one of the premier scientific laboratories of the DOE, BNL must continuously foster groundbreaking scientific research. At Brookhaven National Laboratory one such method is through its LDRD Program. This discretionary research and development tool is critical in maintaining the scientific excellence and long-term vitality of the Laboratory. Additionally, it is a means to stimulate the scientific community and foster new

  9. Laboratory Directed Research and Development Program Assessment for FY 2007

    Energy Technology Data Exchange (ETDEWEB)

    Newman,L.; Fox, K.J.

    2007-12-31

    Brookhaven National Laboratory (BNL) is a multidisciplinary laboratory that carries out basic and applied research in the physical, biomedical, and environmental sciences, and in selected energy technologies. It is managed by Brookhaven Science Associates, LLC, (BSA) under contract with the U. S. Department of Energy (DOE). BNL's Fiscal Year 2007 spending was $515 million. There are approximately 2,600 employees, and another 4,500 guest scientists and students who come each year to use the Laboratory's facilities and work with the staff. The BNL Laboratory Directed Research and Development (LDRD) Program reports its status to the U.S. Department of Energy (DOE) annually in March, as required by DOE Order 413.2B, 'Laboratory Directed Research and Development', April 19, 2006, and the Roles, Responsibilities, and Guidelines for Laboratory Directed Research and Development at the Department of Energy/National Nuclear Security Administration Laboratories dated June 13, 2006. The goals and objectives of BNL's LDRD Program can be inferred from the Program's stated purposes. These are to (1) encourage and support the development of new ideas and technology, (2) promote the early exploration and exploitation of creative and innovative concepts, and (3) develop new 'fundable' R&D projects and programs. The emphasis is clearly articulated by BNL to be on supporting exploratory research 'which could lead to new programs, projects, and directions' for the Laboratory. As one of the premier scientific laboratories of the DOE, BNL must continuously foster groundbreaking scientific research. At Brookhaven National Laboratory one such method is through its LDRD Program. This discretionary research and development tool is critical in maintaining the scientific excellence and long-term vitality of the Laboratory. Additionally, it is a means to stimulate the scientific community and foster new science and technology ideas, which

  10. TRECII: a computer program for transportation risk assessment

    Energy Technology Data Exchange (ETDEWEB)

    Franklin, A.L.

    1980-05-01

    A risk-based fault tree analysis method has been developed at the Pacific Northwest Laboratory (PNL) for analysis of nuclear fuel cycle operations. This methodology was developed for the Department of Energy (DOE) as a risk analysis tool for evaluating high level waste management systems. A computer package consisting of three programs was written at that time to assist in the performance of risk assessment: ACORN (draws fault trees), MFAULT (analyzes fault trees), and RAFT (calculates risk). This methodology evaluates release consequences and estimates the frequency of occurrence of these consequences. This document describes an additional risk calculating code which can be used in conjunction with two of the three codes for transportation risk assessment. TRECII modifies the definition of risk used in RAFT (prob. x release) to accommodate release consequences in terms of fatalities. Throughout this report risk shall be defined as probability times consequences (fatalities are one possible health effect consequence). This methodology has been applied to a variety of energy material transportation systems. Typically the material shipped has been radioactive, although some adaptation to fossil fuels has occurred. The approach is normally applied to truck or train transport systems with some adaptation to pipelines and aircraft. TRECII is designed to be used primarily in conjunction with MFAULT; however, with a moderate amount of effort by the user, it can be implemented independent of the risk analysis package developed at PNL. Code description and user instructions necessary for the implementation of the TRECII program are provided.

  11. Nuclear fragmentation and DNA degradation during programmed cell death in petals of morning glory (Ipomoea nil)

    NARCIS (Netherlands)

    Yamada, T.; Takatsu, Y.; Kasumi, K.; Ichimura, K.; Doorn, van W.G.

    2006-01-01

    We studied DNA degradation and nuclear fragmentation during programmed cell death (PCD) in petals of Ipomoea nil (L.) Roth flowers. The DNA degradation, as observed on agarose gels, showed a large increase. Using DAPI, which stains DNA, and flow cytometry for DAPI fluorescence, we found that the

  12. DNA degradation and nuclear degeneration during programmed cell death in petals of Antirrhinum, Argyranthemum, and Petunia

    NARCIS (Netherlands)

    Yamada, T.; Ichimura, K.; Doorn, van W.G.

    2006-01-01

    Programmed cell death (PCD) was studied in the petals of Antirrhinum majus, Argyranthemum frutescens, and Petunia hybrida, using DNA degradation and changes in nuclear morphology as parameters. The petals exhibit loss of turgor (wilting) as a visible symptom of PCD. DNA degradation, as shown on

  13. Nuclear Propulsion and Power Non-Nuclear Test Facility (NP2NTF): Preliminary Analysis and Feasibility Assessment Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Nuclear reactors, which power nuclear propulsion and power systems, and the nuclear radiation and residual radioactivity associated with these systems, impose...

  14. SUBJECTIVE ASSESSMENTS OF RADIATION RISK ON THE TERRITORIES ADJACENT TO THE PLACES OF PEACEFUL NUCLEAR EXPLOSIONS

    Directory of Open Access Journals (Sweden)

    G. V. Arkhangelskaya

    2009-01-01

    Full Text Available The article contains results of public opinion assessment of the radiation hazard due to consequences of two accidental peaceful nuclear explosions: Globus-1 in the Ivanovo region and Dnepr-1, Dnepr-2 in the Murmansk region. Results of query poll reveal that population knows about peaceful nuclear explosions that were done many years ago near their settlement. Radiation hazard and territory contamination due to these events is estimated by population as rather high. This public opinion is reflected in the information about consequences of peaceful nuclear explosions presented in the Internet and local printed mass media, especially due to consequences of accidental peaceful nuclear explosion Globus-1.

  15. Corrosion of Spent Nuclear Fuel: The Long-Term Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Ewing, Rodney C.

    2003-09-14

    The successful disposal of spent nuclear fuel (SNF) is one of the most serious challenges to the successful completion of the nuclear fuel cycle and the future of nuclear power generation. In the United States, 21 percent of the electricity is generated by 107 commercial nuclear power plants (NPP), each of which generates 20 metric tons of spent nuclear fuel annually. In 1996, the total accumulation of spent nuclear fuel was 33,700 metric tons of heavy metal (MTHM) stored at 70 sites around the country. The end-of-life projection for current nuclear power plants (NPP) is approximately 86,000 MTHM. In the proposed nuclear waste repository at Yucca Mountain over 95% of the radioactivity originates from spent nuclear fuel. World-wide in 1998, approximately 130,000 MTHM of SNF have accumulated, most of it located at 236 NPP in 36 countries. Annual production of SNF is approximately 10,000 MTHM, containing about 100 tons of ''reactor grade'' plutonium. Any reasonable increase in the proportion of energy production by NPP, i.e., as a substitute for hydrocarbon-based sources of energy, will significantly increase spent nuclear fuel production. Spent nuclear fuel is essentially UO{sub 2} with approximately 4-5 atomic percent actinides and fission product elements. A number of these elements have long half-lives hence, the long-term behavior of the UO{sub 2} is an essential concern in the evaluation of the safety and risk of a repository for spent nuclear fuel. One of the unique and scientifically most difficult aspects of the successful disposal of spent nuclear fuel is the extrapolation of short-term laboratory data (hours to years) to the long time periods (10{sup 3} to 10{sup 5} years) as required by the performance objectives set in regulations, i.e. 10 CFR 60. The direct verification of these extrapolations or interpolations is not possible, but methods must be developed to demonstrate compliance with government regulations and to satisfy the

  16. Nuclear Terrorism: Assessing the Threat, Developing a Response

    Science.gov (United States)

    2009-01-01

    cylinder into a second subcritical piece of HEU; these pieces form a supercritical mass and generate a nuclear explosion if they can be brought together...amount of deuterium and tritium gas in the core of the fission device. The gas undergoes fusion as the fission chain reaction gets underway, and

  17. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  18. Improving the assessment of the proliferation risk of nuclear fuel cycles

    National Research Council Canada - National Science Library

    Nuclear and Radiation Studies Board; Division on Earth and Life Studies; National Research Council; National Research Council

    2013-01-01

    .... As the Department of Energy (DOE) and other parts of the government make decisions about future nuclear fuel cycles, DOE would like to improve proliferation assessments to better inform those decisions...

  19. A program in medium-energy nuclear physics. Progress report, January 1, 1992--March 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Berman, B.L.; Dhuga, K.S.

    1994-08-01

    This renewal proposal requests continued funding for our program in experimental medium-energy nuclear physics. The focus of our program remains the understanding of the short-range part of the strong interaction in the nuclear medium. In the past three years we have focused our attention ever more sharply on experiments with real tagged photons at CEBAF. We are part of the Hall-B Collaboration at CEBAF. We are co-spokespersons on two approved CEBAF experiments, Photoreactions on {sup 3}He and Photoabsorption and Photofission of Nuclei, and we are preparing another, Nondiffractive Photoproduction of the {rho} Meson with Linearly Polarized Photons, for presentation to the next CEBAF PAC. We are part of the team that is instrumenting the Photon Tagger and a high-energy tagged polarized-photon beam for Hall B; some of the instrumentation for these projects is being built at our Nuclear Detector Laboratory, under the auspices of The George Washington University Center for Nuclear Studies. Our recent measurements of pion scattering from {sup 3}H and {sup 3}He at LAMPF and of cluster knockout from few-body nuclei at NIKHEF have yielded very provocative results, showing the importance of the very light nuclei as a laboratory for quantifying important aspects of the nuclear many-body force. We look forward to expanding our studies of short-range forces in nuclei, particularly the very fight nuclei using electromagnetic probes and employing the extraordinary power of CEBAF and the CLAS.

  20. Nuclear Waste Treatment Program annual report for FY 1988

    Energy Technology Data Exchange (ETDEWEB)

    Brouns, R.A.; Powell, J.A. (comps.)

    1989-11-01

    Much emphasis continues to be on the transfer of remote design technology for components integral to the West Valley Demonstration Project's (WVDP) vitrification process. In addition to preparing equipment specifications and drawings, Pacific Northwest Laboratory (PNL) staff also participated in numerous design coordination meetings and reviews of drawings prepared by other WVDP contractors. Nearly 200 jumper drawings for the vitrification cell were prepared by this program in FY 1988. The remote jumpers connect vessels in the cell to each other for the transfer of solutions and provide for the flow of materials, instrumentation signals, and power from outside the cell. Analysis required in preparing the jumper designs involved balance, thermal stress, seismic, set-down stress, and displacement calculations. Design efforts were begun on the canister decontamination and swipe station and on the remote maintenance station. Equipment selection and layouts of the vitrification off-gas treatment system, including a reamer to remotely clean the melter off-gas line, were finalized. Also finalized were the designs for the high-efficiency particulate air (HEPA) filter assemblies for heating, cooling and air conditioning of the vitrification cell.

  1. Assessment of NDE for key indicators of aging cables in nuclear power plants - Interim status

    Science.gov (United States)

    Glass, S. W.; Ramuhalli, P.; Fifield, L. S.; Prowant, M. S.; Dib, G.; Tedeschi, J. R.; Suter, J. D.; Jones, A. M.; Good, M. S.; Pardini, A. F.; Hartman, T. S.

    2016-02-01

    Degradation of the cable jacket, electrical insulation, and other cable components of installed cables within nuclear power plants (NPPs) is known to occur as a function of age, temperature, radiation, and other environmental factors. System tests verify cable function under normal loads; however, the concern is over cable performance under exceptional loads associated with design-basis events (DBEs). The cable's ability to perform safely over the initial 40-year planned and licensed life has generally been demonstrated and there have been very few age-related cable failures. With greater than 1000 km of power, control, instrumentation, and other cables typically found in an NPP, replacing all the cables would be a severe cost burden. Justification for life extension to 60 and 80 years requires a cable aging management program to justify cable performance under normal operation as well as accident conditions. Currently the gold standard for determining cable insulation degradation is the elongation-at-break (EAB). This, however, is an ex-situ measurement and requires removal of a sample for laboratory investigation. A reliable nondestructive examination (NDE) in-situ approach is desirable to objectively determine the suitability of the cable for service. A variety of tests are available to assess various aspects of electrical and mechanical cable performance, but none of these tests are suitable for all cable configurations nor does any single test confirm all features of interest. Nevertheless, the complete collection of test possibilities offers a powerful range of tools to assure the integrity of critical cables. Licensees and regulators have settled on a practical program to justify continued operation based on condition monitoring of a lead sample set of cables where test data is tracked in a database and the required test data are continually adjusted based on plant and fleet-wide experience. As part of the Light Water Reactor Sustainability program sponsored

  2. A comparison between nuclear dismantling during plant and animal programmed cell death.

    Science.gov (United States)

    Domínguez, Fernando; Cejudo, Francisco Javier

    2012-12-01

    Programmed cell death (PCD) is a process of organized destruction of cells, essential for the development and maintenance of cellular homeostasis of multicellular organisms. Cells undergoing PCD begin a degenerative process in response to internal or external signals, whereby the nucleus becomes one of the targets. The process of nuclear dismantling includes events affecting the nuclear envelope, such as formation of lobes at the nuclear surface, selective proteolysis of nucleoporins and nuclear pore complex clustering. In addition, chromatin condensation increases in coordination with DNA fragmentation. These processes have been largely studied in animals, but remain poorly understood in plants. The overall process of cell death has different morphological and biochemical features in plants and animals. However, recent advances suggest that nuclear dismantling in plant cells progresses with morphological and biochemical characteristics similar to those in apoptotic animal cells. In this review, we summarize nuclear dismantling in plant PCD, focusing on the similarities and differences with their animal counterparts. Copyright © 2012 Elsevier Ireland Ltd. All rights reserved.

  3. Role of apoptosis-inducing factor (AIF in programmed nuclear death during conjugation in Tetrahymena thermophila

    Directory of Open Access Journals (Sweden)

    Endoh Hiroshi

    2010-02-01

    Full Text Available Abstract Background Programmed nuclear death (PND, which is also referred to as nuclear apoptosis, is a remarkable process that occurs in ciliates during sexual reproduction (conjugation. In Tetrahymena thermophila, when the new macronucleus differentiates, the parental macronucleus is selectively eliminated from the cytoplasm of the progeny, concomitant with apoptotic nuclear events. However, the molecular mechanisms underlying these events are not well understood. The parental macronucleus is engulfed by a large autophagosome, which contains numerous mitochondria that have lost their membrane potential. In animals, mitochondrial depolarization precedes apoptotic cell death, which involves DNA fragmentation and subsequent nuclear degradation. Results We focused on the role of mitochondrial apoptosis-inducing factor (AIF during PND in Tetrahymena. The disruption of AIF delays the normal progression of PND, specifically, nuclear condensation and kilobase-size DNA fragmentation. AIF is localized in Tetrahymena mitochondria and is released into the macronucleus prior to nuclear condensation. In addition, AIF associates and co-operates with the mitochondrial DNase to facilitate the degradation of kilobase-size DNA, which is followed by oligonucleosome-size DNA laddering. Conclusions Our results suggest that Tetrahymena AIF plays an important role in the degradation of DNA at an early stage of PND, which supports the notion that the mitochondrion-initiated apoptotic DNA degradation pathway is widely conserved among eukaryotes.

  4. Utility of Social Modeling for Proliferation Assessment - Enhancing a Facility-Level Model for Proliferation Resistance Assessment of a Nuclear Enegry System

    Energy Technology Data Exchange (ETDEWEB)

    Coles, Garill A.; Brothers, Alan J.; Gastelum, Zoe N.; Olson, Jarrod; Thompson, Sandra E.

    2009-10-26

    based nuclear facility assessment; 5. a discussion of a way to engage with the owners of the PR assessment methodology to assess and improve the enhancement concept; 6. a discussion of implementation of the proposed approach, including a discussion of functionality and potential users; and 7. conclusions from the research. This report represents technical deliverables for the NA-22 Simulations, Algorithms, and Modeling program. Specifically this report is the Task 2 and 3 deliverables for project PL09-UtilSocial.

  5. Functional process descriptions for the program to develop the Nuclear Waste Management System

    Energy Technology Data Exchange (ETDEWEB)

    Woods, T.W.

    1991-09-01

    The Office of Civilian Radioactive Waste Management (OCRWM) is executing a plan for improvement of the systems implemented to carry out its responsibilities under the Nuclear Waste Policy Act of 1982 (NWPA). As part of the plan, OCRWM is performing a systems engineering analysis of both the physical system, i.e., the Nuclear Waste Management System (NWMS), and the programmatic functions that must be accomplished to bring the physical system into being. The purpose of the program analysis is to provide a systematic identification and definition of all program functions, functional process flows, and function products necessary and sufficient to provide the physical system. The analysis resulting from this approach provides a basis for development of a comprehensive and integrated set of policies, standard practices, and procedures for the effective and efficient execution of the program. Thus, this analysis will form a basis for revising current OCRWM policies and procedures, or developing new ones is necessary. The primary purposes of this report are as follows: (1) summarizes the major functional processes and process flows that have been developed as a part of the program analysis, and (2) provide an introduction and assistance in understanding the detailed analysis information contained in the three volume report titled The Analysis of the Program to Develop the Nuclear Waste Management System (Woods 1991a).

  6. Utilization Practice of the Concept Mapping Program for Nuclear Engineer Training

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Bae Joo; Ko, Byung Moo; Heo, Yuk [Korea Hydro and Nuclear Power, Daejeon (Korea, Republic of)

    2009-05-15

    Knowledge is the most important factor in the safe and reliable operation of the NPP. Many methods are used to enhance the knowledge level of the personnel in the NPP. Generally, classroom lecture method is used for nuclear engineers. But this method has some pitfalls as an adult training method because students have already a lot of knowledge, so they want to participate actively in the learning process. KNPEI undertook a research project from March 2006 to September 2007 to capture the experience knowledge from senior staff and transfer it to junior staff. As part of the research activity KNPEI introduced a Concept Mapping Program and set up a Concept Mapping server to capture the experience knowledge of the senior staff. This Concept Mapping Program has some characteristics that can be used in learning about conceptual knowledge. The purpose of this report is to introduce the utilization method and practice at KNPEI for the nuclear engineer training using the Concept Mapping Program.

  7. Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

    Energy Technology Data Exchange (ETDEWEB)

    Cover, L.E.; Bohn, M.P.; Campbell, R.D.; Wesley, D.A.

    1983-12-01

    The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the reactor system which actively participate in the hypothesized accident scenarios. This report describes the development of the required fragility relations and the data sources and data reduction techniques upon which they are based. Both building and component fragilities are covered. The building fragilities are for the Zion Unit 1 reactor which was the specific plant used for development of methodology in the program. Some of the component fragilities are site-specific also, but most would be usable for other sites as well.

  8. Design and analysis of aquatic monitoring programs at nuclear power plants.

    Energy Technology Data Exchange (ETDEWEB)

    McKenzie, D.H.; Kannberg, L.D.; Gore, K.L.; Arnold, E.M.; Watson, D.G.

    1977-11-01

    This report addresses some of the problems of designing, conducting, and analyzing aquatic environmental monitoring programs for impact assessment of nuclear power plants. The concepts discussed are applicable to monitoring the effects of chemical, radioactive, or thermal effluents. The concept of control and treatment station pairs is the fundamental basis for the experimental method proposed. This concept is based on the hypothesis that the relationship between the two stations forming the pair can be estimated from the preoperational period and that this relationship holds during the operational period. Any changes observed in this relationship during the operational period are assumed to be the result of the power plant impacts. Thus, it is important that station pairs are selected so it can be assumed that they respond to natural environmental changes in a manner that maintains that relationship. The major problem in establishing the station pairs will be the location of the control station. The universal heterogeneity in the environment will prevent the establishment of identical station pairs. The requirement that the control station remain unaffected by the operation of the power plant dictates a spacial separation with its associated differences in habitat. Thus, selection of the control station will be based upon balancing the following two criteria: (1) far enough away from the plant site to be beyond the plant influence, and (2) close enough to the treatment station that the biological communities will respond to natural environmental changes consistently in the same manner.

  9. Use of scientometrics to assess nuclear and other analytical methods

    Energy Technology Data Exchange (ETDEWEB)

    Lyon, W.S.

    1986-01-01

    Scientometrics involves the use of quantitative methods to investigate science viewed as an information process. Scientometric studies can be useful in ascertaining which methods have been most employed for various analytical determinations as well as for predicting which methods will continue to be used in the immediate future and which appear to be losing favor with the analytical community. Published papers in the technical literature are the primary source materials for scientometric studies; statistical methods and computer techniques are the tools. Recent studies have included growth and trends in prompt nuclear analysis impact of research published in a technical journal, and institutional and national representation, speakers and topics at several IAEA conferences, at modern trends in activation analysis conferences, and at other non-nuclear oriented conferences. Attempts have also been made to predict future growth of various topics and techniques. 13 refs., 4 figs., 17 tabs.

  10. Assessment of the Fusion Energy Sciences Program. Final Report

    Energy Technology Data Exchange (ETDEWEB)

    None

    2001-05-01

    An assessment of the Office of Fusion Energy Sciences (OFES) program with guidance for future program strategy. The overall objective of this study is to prepare an independent assessment of the scientific quality of the Office of Fusion Energy Sciences program at the Department of Energy. The Fusion Science Assessment Committee (FuSAC) has been appointed to conduct this study.

  11. Communications experiment for the Nuclear Electric Propulsion Space Test Program (NEPSTP)

    Science.gov (United States)

    Bokulic, Robert S.; Gatsonis, Nikolaos A.; Bythrow, Peter F.; Mauk, Barry H.

    1993-06-01

    A planned experiment for characterizing RF/plume interaction effects on the Nuclear Electric Propulsion Space Test Program (NEPSTP) is described. The NEPSTP spacecraft will use a Russian Topaz II nuclear reactor to power a suite of electric thrusters on-orbit. Transmission of signals through the thruster plumes at S-band (2 GHz) will be characterized over a wide range of viewing angles by controlling the spacecraft attitude as it passes by the ground station. Planned measurements include signal strength, bit error count, scintillation, phase transient effects, and radio frequency interference. Possible future augmentations to the experiment, including a UHF transmitter and a measurement of total election content, are also described.

  12. Required Assets for a Nuclear Energy Applied R&D Program

    Energy Technology Data Exchange (ETDEWEB)

    Harold F. McFarlane; Craig L. Jacobson

    2009-03-01

    This report is one of a set of three documents that have collectively identified and recommended research and development capabilities that will be required to advance nuclear energy in the next 20 to 50 years. The first report, Nuclear Energy for the Future: Required Research and Development Capabilities—An Industry Perspective, was produced by Battelle Memorial Institute at the request of the Assistant Secretary of Nuclear Energy. That report, drawn from input by industry, academia, and Department of Energy laboratories, can be found in Appendix 5.1. This Idaho National Laboratory report maps the nuclear-specific capabilities from the Battelle report onto facility requirements, identifying options from the set of national laboratory, university, industry, and international facilities. It also identifies significant gaps in the required facility capabilities. The third document, Executive Recommendations for Nuclear R&D Capabilities, is a letter report containing a set of recommendations made by a team of senior executives representing nuclear vendors, utilities, academia, and the national laboratories (at Battelle’s request). That third report can be found in Appendix 5.2. The three reports should be considered as set in order to have a more complete picture. The basis of this report was drawn from three sources: previous Department of Energy reports, workshops and committee meetings, and expert opinion. The facilities discussed were winnowed from several hundred facilities that had previously been catalogued and several additional facilities that had been overlooked in past exercises. The scope of this report is limited to commercial nuclear energy and those things the federal government, or more specifically the Office of Nuclear Energy, should do to support its expanded deployment in order to increase energy security and reduce carbon emissions. In the context of this report, capabilities mean innovative, well-structured research and development programs

  13. Light Water Reactor Sustainability Program: Computer-Based Procedures for Field Activities: Results from Three Evaluations at Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Oxstrand, Johanna [Idaho National Lab. (INL), Idaho Falls, ID (United States); Le Blanc, Katya [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bly, Aaron [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    The Computer-Based Procedure (CBP) research effort is a part of the Light-Water Reactor Sustainability (LWRS) Program, which is a research and development (R&D) program sponsored by Department of Energy (DOE) and performed in close collaboration with industry R&D programs that provides the technical foundations for licensing and managing the long-term, safe, and economical operation of current nuclear power plants. One of the primary missions of the LWRS program is to help the U.S. nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. One area that could yield tremendous savings in increased efficiency and safety is in improving procedure use. Nearly all activities in the nuclear power industry are guided by procedures, which today are printed and executed on paper. This paper-based procedure process has proven to ensure safety; however, there are improvements to be gained. Due to its inherent dynamic nature, a CBP provides the opportunity to incorporate context driven job aids, such as drawings, photos, and just-in-time training. Compared to the static state of paper-based procedures (PBPs), the presentation of information in CBPs can be much more flexible and tailored to the task, actual plant condition, and operation mode. The dynamic presentation of the procedure will guide the user down the path of relevant steps, thus minimizing time spent by the field worker to evaluate plant conditions and decisions related to the applicability of each step. This dynamic presentation of the procedure also minimizes the risk of conducting steps out of order and/or incorrectly assessed applicability of steps.

  14. Characterization Program Management Plan for Hanford K Basin Spent Nuclear Fuel (SNF) (OCRWM)

    Energy Technology Data Exchange (ETDEWEB)

    BAKER, R.B.; TRIMBLE, D.J.

    2000-12-12

    The management plan developed to characterize the K Basin spent nuclear fuel (SNF) and sludge was originally developed for Westinghouse Hanford Company and Pacific Northwest National Laboratory to work together on a program to provide characterization data to support removal, conditioning, and subsequent dry storage of the SNF stored at the Hanford K Basins. The plan also addressed necessary characterization for the removal, transport, and storage of the sludge from the Hanford K Basins. This plan was revised in 1999 (i.e., Revision 2) to incorporate actions necessary to respond to the deficiencies revealed as the result of Quality Assurance surveillances and audits in 1999 with respect to the fuel characterization activities. Revision 3 to this Program Management Plan responds to a Worker Assessment resolution determined in Fical Year 2000. This revision includes an update to current organizational structures and other revisions needed to keep this management plan consistent with the current project scope. The plan continues to address both the SNF and the sludge accumulated at K Basins. Most activities for the characterization of the SNF have been completed. Data validation, Office of Civilian Radioactive Waste Management (OCRWM) document reviews, and OCRWM data qualification are the remaining SNF characterization activities. The transport and storage of K Basin sludge are affected by recent path forward revisions. These revisions require additional laboratory analyses of the sludge to complete the acquisition of required supporting engineering data. Hence, this revision of the management plan provides the overall work control for these remaining SNF and sludge characterization activities given the current organizational structure of the SNF Project.

  15. Environmental impact assessment and socio political issues of nuclear waste management; Ydinjaetehuollon ympaeristoevaikutusten arviointi ja sosiopoliittiset kysymykset

    Energy Technology Data Exchange (ETDEWEB)

    Harmaajaervi, I.; Tolsa, H. [VTT Communities and Infrastructure, Espoo (Finland). Urban Planning; Vuori, S. [VTT Energy, Espoo (Finland). Nuclear Energy; Litmanen, T. [Jyvaeskylae Univ. (Finland)

    1997-09-01

    The study is a part of the Publicly Administrated Nuclear Waste Management Research Programme (JYT2) which was carried out in 1994-1996. The principal goal of the research programme has been to provide the authorities with information and research results relevant for the safety of nuclear waste management in order to support the various activities of the authorities. The main emphasis of the research programme focuses on the disposal of spent fuel. In addition to nuclear waste research in the field of natural sciences and technology, the research program- me has focused mostly on societal issues associated with nuclear waste disposal facilities and on the non-radiological environmental effects in the environs of the disposal site. Some of the local effects are already revealed in the research phase, before any final decisions are made as to the selection of the disposal site. The study has focused primarily on local and regional issues. The statutory requirement to conduct environ- mental impact assessment (EIA) chiefly concerns those who are responsible for waste management, but the authorities also need to acquire systematic information in the field to support developing requirements for the content and scope of EIA procedure and preparedness to check the assessments made. This is a report of the first parts of the study in 1994-1995. The report deals with the subject matter generally based on earlier studies in Finland and other countries. The results of the study will be reported later. 101 refs.

  16. Study of the application of virtual reality in programs training on nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Pastura, Valéria da F. e S.; Mol, Antonio Carlos de A. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Siqueira, Ana Paula L. de, E-mail: vpastura@ien.gov.br, E-mail: mol@ien.gov.br, E-mail: analegey@hotmail.com [Centro Universitário Carioca (UniCarioca), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The activities developed in the units which organize the National Nuclear Energy Commission (CNEN) are present in various sectors of the Brazilian society, being them in medicine, industry, electricity generation, mining, and among the others. Based on the assumption that the employees are CNEN's mayor differential and the training programs play an important role in the process of organizational development, because they align the professionals with the strategies of the institution properly. Focusing on these matters, this master thesis aimed to evaluate the training programs which are applied by CNEN, in order to propose and evaluate the use of the Virtual Reality (VR) expertise as a new method to be applied in the training programs. To accomplish this purpose, we performed two methodological approaches through questionnaires. And from the analysis of the results obtained, we could realize that there was no efficient training program which is systematically applied by CNEN, and the use of the VR technique improves the training programs in the understanding of themes whose assimilation is challengeable, such as those related to nuclear power. In this sense, for a better functional performance, the training programs adopted by CNEN must be structured so as to enable the development of each server's skills as well as abilities and, it is actually hoped that the virtual reality tools could be inserted in these programs to pursue only this purpose. (author). (author)

  17. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  18. Development of a New Safety Culture Assessment Method for Nuclear Power Plants (NPPs) (A study to suggest a new safety culture assessment method in nuclear power plants)

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sang Min; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

    2014-08-15

    This study is conducted to suggest a new safety culture assessment method in nuclear power plants. Criteria with various existing safety culture analysis methods are united, and reliability analysis methods are applied. The concept of the most representative methods, Fault Tree Analysis (FTA) and Failure Mode and Effect Analysis (FMEA), are adopted to assess safety culture. Through this application, it is expected that the suggested method will bring results with convenience and objectiveness.

  19. Technology Assessment and Roadmap for the Emergency Radiation Dose Assessment Program

    Energy Technology Data Exchange (ETDEWEB)

    Turteltaub, K W; Hartman-Siantar, C; Easterly, C; Blakely, W

    2005-10-03

    A Joint Interagency Working Group (JIWG) under the auspices of the Department of Homeland Security Office of Research and Development conducted a technology assessment of emergency radiological dose assessment capabilities as part of the overall need for rapid emergency medical response in the event of a radiological terrorist event in the United States. The goal of the evaluation is to identify gaps and recommend general research and development needs to better prepare the Country for mitigating the effects of such an event. Given the capabilities and roles for responding to a radiological event extend across many agencies, a consensus of gaps and suggested development plans was a major goal of this evaluation and road-mapping effort. The working group consisted of experts representing the Departments of Homeland Security, Health and Human Services (Centers for Disease Control and the National Institutes of Health), Food and Drug Administration, Department of Defense and the Department of Energy's National Laboratories (see appendix A for participants). The specific goals of this Technology Assessment and Roadmap were to: (1) Describe the general context for deployment of emergency radiation dose assessment tools following terrorist use of a radiological or nuclear device; (2) Assess current and emerging dose assessment technologies; and (3) Put forward a consensus high-level technology roadmap for interagency research and development in this area. This report provides a summary of the consensus of needs, gaps and recommendations for a research program in the area of radiation dosimetry for early response, followed by a summary of the technologies available and on the near-term horizon. We then present a roadmap for a research program to bring present and emerging near-term technologies to bear on the gaps in radiation dose assessment and triage. Finally we present detailed supporting discussion on the nature of the threats we considered, the status of

  20. Translating Theory Into Practice: Implementing a Program of Assessment.

    Science.gov (United States)

    Hauer, Karen E; O'Sullivan, Patricia S; Fitzhenry, Kristen; Boscardin, Christy

    2018-03-01

    A program of assessment addresses challenges in learner assessment using a centrally planned, coordinated approach that emphasizes assessment for learning. This report describes the steps taken to implement a program of assessment framework within a medical school. A literature review on best practices in assessment highlighted six principles that guided implementation of the program of assessment in 2016-2017: (1) a centrally coordinated plan for assessment aligns with and supports a curricular vision; (2) multiple assessment tools used longitudinally generate multiple data points; (3) learners require ready access to information-rich feedback to promote reflection and informed self-assessment; (4) mentoring is essential to facilitate effective data use for reflection and learning planning; (5) the program of assessment fosters self-regulated learning behaviors; and (6) expert groups make summative decisions about grades and readiness for advancement. Implementation incorporated stakeholder engagement, use of multiple assessment tools, design of a coaching program, and creation of a learner performance dashboard. The assessment team monitors adherence to principles defining the program of assessment and gathers and responds to regular feedback from key stakeholders, including faculty, staff, and students. Next steps include systematically collecting evidence for validity of individual assessments and the program overall. Iterative review of student performance data informs curricular improvements. The program of assessment also highlights technology needs that will be addressed with information technology experts. The outcome ultimately will entail showing evidence of validity that the program produces physicians who engage in lifelong learning and provide high-quality patient care.

  1. Aeroelasticity Benchmark Assessment: Subsonic Fixed Wing Program

    Science.gov (United States)

    Florance, Jennifer P.; Chwalowski, Pawel; Wieseman, Carol D.

    2010-01-01

    Aeroelasticity Branch will examine other experimental efforts within the Subsonic Fixed Wing (SFW) program (such as testing of the NASA Common Research Model (CRM)) and other NASA programs and assess aeroelasticity issues and research topics.

  2. UMCP-BG and E collaboration in nuclear power engineering in the framework of DOE-Utility Nuclear Power Engineering Education Matching Grant Program

    Energy Technology Data Exchange (ETDEWEB)

    Wolfe, Lothar PhD

    2000-03-01

    The DOE-Utility Nuclear Power Engineering Education Matching Grant Program has been established to support the education of students in Nuclear Engineering Programs to maintain a knowledgeable workforce in the United States in order to keep nuclear power as a viable component in a mix of energy sources for the country. The involvement of the utility industry ensures that this grant program satisfies the needs and requirements of local nuclear energy producers and at the same time establishes a strong linkage between education and day-to-day nuclear power generation. As of 1997, seventeen pairs of university-utility partners existed. UMCP was never a member of that group of universities, but applied for the first time with a proposal to Baltimore Gas and Electric Company in January 1999 [1]. This proposal was generously granted by BG&E [2,3] in the form of a gift in the amount of $25,000 from BG&E's Corporate Contribution Program. Upon the arrival of a newly appointed Director of Administration in the Department of Materials and Nuclear Engineering, the BG&E check was deposited into the University's Maryland Foundation Fund. The receipt of the letter and the check enabled UMCP to apply for DOE's matching funds in the same amount by a proposal.

  3. Safety assessment of a nuclear power plant building subjected to an aircraft crash

    Energy Technology Data Exchange (ETDEWEB)

    Thai, Duc-Kien; Kim, Seung-Eock, E-mail: sekim@sejong.ac.kr

    2015-11-15

    Highlights: • Numerical analysis of a nuclear auxiliary building under aircraft crash is conducted. • The analysis result of impact force is verified using the Riera function. • The safety assessment is performed with regard to different impact scenarios. • Discussions and conclusions on safety of the nuclear building are presented. - Abstract: This paper presents a safety assessment of a nuclear building subjected to an aircraft crash using numerical analysis. For impact simulation, the reinforced concrete (RC) Primary Auxiliary Building (PAB) of the Korea Standard Nuclear Power Plant (KSNP) is fully modeled and an aircraft model of a Boeing 767-400 is used. The Riera function is used to verify the analysis result of impact force–time history. The IRIS test is used to verify the structural behavior of the RC wall under impact loading. The safety assessment of the building is performed with regard to different impact scenarios. The safety of the nuclear building under aircraft crash, including (1) global structural safety, (2) local structural safety, and (3) vibration safety are evaluated and discussed. The results show that the global and local structural safety of the PAB is ensured in all impact scenarios. However, the vibration safety of the building is not ensured. In accordance, the regulatory guide of United States Nuclear Regulatory Commission (U.S. NRC), shutdown of the nuclear power plant is required.

  4. Corrosion of Spent Nuclear Fuel: The Long-Term Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Rodney C. Ewing

    2004-10-07

    Spent nuclear fuel, essentially U{sub 2}, accounts for over 95% of the total radioactivity of all of the radioactive wastes in the United States that require disposal, disposition or remediation. The UO{sub 2} in SNF is not stable under oxiding conditions and may also be altered under reducing conditions. The alteration of SNF results in the formation of new uranium phases that can cause the release or retardation of actinide and fission product radionuclides. Over the long term, and depending on the extent to which the secondary uranium phases incorporate fission products and actinides, these alteration phases become the near-field source term.

  5. 75 FR 30007 - Race to the Top Fund Assessment Program

    Science.gov (United States)

    2010-05-28

    ... Overview Information Race to the Top Fund Assessment Program Catalog of Federal Domestic Assistance (CFDA) Numbers: 84.395B (Comprehensive Assessment Systems grants) and 84.395C (High School Course Assessment... applications for new awards for FY 2010 (NIA) for the Race to the Top Fund Assessment Program. This notice...

  6. Standard guide for establishing a quality assurance program for analytical chemistry laboratories within the nuclear industry

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2006-01-01

    1.1 This guide covers the establishment of a quality assurance (QA) program for analytical chemistry laboratories within the nuclear industry. Reference to key elements of ANSI/ISO/ASQC Q9001, Quality Systems, provides guidance to the functional aspects of analytical laboratory operation. When implemented as recommended, the practices presented in this guide will provide a comprehensive QA program for the laboratory. The practices are grouped by functions, which constitute the basic elements of a laboratory QA program. 1.2 The essential, basic elements of a laboratory QA program appear in the following order: Section Organization 5 Quality Assurance Program 6 Training and Qualification 7 Procedures 8 Laboratory Records 9 Control of Records 10 Control of Procurement 11 Control of Measuring Equipment and Materials 12 Control of Measurements 13 Deficiencies and Corrective Actions 14

  7. A Performance Assessment of NASA's Heliophysics Program

    Science.gov (United States)

    2009-01-01

    Recognizing the importance of distributed observations of all elements of the Sun-to-Earth system and the synergies between observation and theory and between basic and targeted research, the National Research Council's 2003 solar and space physics decadal survey laid out an integrated research strategy that sought to extend and augment what has now become the Heliophysics Great Observatory as well as to enhance NASA, NOAA, NSF, and DOD's other solar and space physics research activities. The Integrated Research Strategy provided a prioritized list of flight missions and theory and modeling programs that would advance the relevant physical theories, incorporate those theories in models that describe a system of interactions between the Sun and the space environment, obtain data on the system, and analyze and test the adequacy of the theories and models. As directed by Congress in the NASA Authorization Act of 2005, the purpose of this report is to assess the progress of NASA's Heliophysics Division at the 5-year mark against the NASA goals and priorities laid out in the decadal survey. In addition to the Integrated Research Strategy, the decadal survey also considered non-mission-specific initiatives to foster a robust solar and space physics program. The decadal survey set forth driving science challenges as well as recommendations devoted to the need for technology development, collaborations and cooperation with other disciplines, understanding the effects of the space environment on technology and society, education and public outreach, and steps that could strengthen and enhance the research enterprise. Unfortunately, very little of the recommended NASA program priorities from the decadal survey s Integrated Research Strategy will be realized during the period (2004-2013) covered by the survey. Mission cost growth, reordering of survey mission priorities, and unrealized budget assumptions have delayed or deferred nearly all of the NASA spacecraft missions

  8. NANA Geothermal Assessment Program Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Jay Hermanson

    2010-06-22

    In 2008, NANA Regional Corporation (NRC) assessed geothermal energy potential in the NANA region for both heat and/or electricity production. The Geothermal Assessment Project (GAP) was a systematic process that looked at community resources and the community's capacity and desire to develop these resources. In October 2007, the US Department of Energy's Tribal Energy Program awarded grant DE-FG36-07GO17075 to NRC for the GAP studies. Two moderately remote sites in the NANA region were judged to have the most potential for geothermal development: (1) Granite Mountain, about 40 miles south of Buckland, and (2) the Division Hot Springs area in the Purcell Mountains, about 40 miles south of Shungnak and Kobuk. Data were collected on-site at Granite Mountain Hot Springs in September 2009, and at Division Hot Springs in April 2010. Although both target geothermal areas could be further investigated with a variety of exploration techniques such as a remote sensing study, a soil geochemical study, or ground-based geophysical surveys, it was recommended that on-site or direct heat use development options are more attractive at this time, rather than investigations aimed more at electric power generation.

  9. Thermal hydraulic feasibility assessment for the Spent Nuclear Fuel Project

    Energy Technology Data Exchange (ETDEWEB)

    Heard, F.J.; Cramer, E.R.; Beaver, T.R. [Westinghouse Hanford Co., Richland, WA (United States); Thurgood, M.J. [Marvin (John), Inc. (United States)

    1996-01-01

    A series of scoping analyses have been completed investigating the thermal-hydraulic performance and feasibility of the Spent Nuclear Fuel Project (SNFP) Integrated Process Strategy (IPS). The SNFP was established to develop engineered solutions for the expedited removal, stabilization, and storage of spent nuclear fuel from the K Basins at the U.S. Department of Energy`s Hanford Site in Richland, Washington. The subject efforts focused on independently investigating, quantifying, and establishing the governing heat production and removal mechanisms for each of the IPS operations and configurations, obtaining preliminary results for comparison with and verification of other analyses, and providing technology-based recommendations for consideration and incorporation into the design bases for the SNFP. The goal was to develop a series fo thermal-hydraulic models that could respond to all process and safety-related issues that may arise pertaining to the SNFP. A series of sensitivity analyses were also performed to help identify those parameters that have the greatest impact on energy transfer and hence, temperature control. It is anticipated that the subject thermal-hydraulic models will form the basis for a series of advanced and more detailed models that will more accurately reflect the thermal performance of the IPS and alleviate the necessity for some of the more conservative assumptions and oversimplifications, as well as form the basis for the final process and safety analyses.

  10. CHANDA and ERINDA: Joint European programs for research on safety of nuclear facilities and waste reduction

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, Roland; Hannaske, Roland; Koegler, Toni [Institut fuer Strahlenphysik, Helmholtz Zentrum DD-Rossendorf, 01328 Dresden (Germany); Institut fuer Kern- und Teilchenphysik, TU Dresden, 01069 Dresden (Germany); Grosse, Eckart [Institut fuer Kern- und Teilchenphysik, TU Dresden, 01069 Dresden (Germany); Junghans, Arnd R. [Institut fuer Strahlenphysik, Helmholtz Zentrum DD-Rossendorf, 01328 Dresden (Germany)

    2014-07-01

    In spite of the planned termination of the German nuclear power program neutron beam facilities in Germany can contribute considerably to research studies on the reduction of hazards due to nuclear waste. Transnational research programs support EU groups who want to carry out projects at the new tof set-up nELBE at HZDR, the calibrated n-flux at PTB and the FRANZ accelerator under construction at Frankfurt. Vice versa various facilities in the EU offer beams for transmutation and safety related studies with neutrons to German scientists under support by ERINDA (2011-2013) and CHANDA (2014-2017; solving challenges in nuclear data for the safety of European nuclear facilities). For work in that field scientific visits are also fostered to improve the exchange of experience between the partners (13 and in future about 35 from 18 countries). Plans for new projects as well as results obtained so far are discussed, and special emphasis is given to the present research performed at nELBE on neutron scattering and absorption.

  11. The Soviet program for peaceful uses of nuclear explosions. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Nordyke, M.D.

    1996-10-01

    An extensive review is given of the US and Russian efforts on peaceful uses of nuclear explosions (PNE). The Soviet PNE program was many times larger than the US Plowshare program in terms of both the number of applications explored with field experiments and the extent to which they were introduced into industrial use. Several PNE applications, such as deep seismic sounding and oil stimulation, have been explored in depth and appear to have had a positive cost benefit at minimal public risk. Closure of runaway gas wells is another possible application where all other techniques fail. However, the fundamental problem with PNEs is the fact that, if they are to be economically significant, there must be widespread use of the technology, involving large numbers of sites, each of which presents a potential source of radioactivity to the environment and nearby communities. Russia now has more than 100 sites where significant high-level radioactivity has been buried. Experience over the last 20 years in US and in today`s Russia shows that it is virtually impossible to gain public acceptance of such applications of nuclear energy. In addition, PNEs also pose a difficult problem in the arms control area. Under a comprehensive test ban, any country conducting PNEs would, in appearance if not in fact, receive information useful for designing new nuclear weapons or maintaining an existing nuclear stockpile, information denied to the other parties to the treaty. 6 tabs, 10 figs.

  12. CAD-based Monte Carlo Program for Integrated Simulation of Nuclear System SuperMC

    Science.gov (United States)

    Wu, Yican; Song, Jing; Zheng, Huaqing; Sun, Guangyao; Hao, Lijuan; Long, Pengcheng; Hu, Liqin

    2014-06-01

    Monte Carlo (MC) method has distinct advantages to simulate complicated nuclear systems and is envisioned as routine method for nuclear design and analysis in the future. High fidelity simulation with MC method coupled with multi-physical phenomenon simulation has significant impact on safety, economy and sustainability of nuclear systems. However, great challenges to current MC methods and codes prevent its application in real engineering project. SuperMC is a CAD-based Monte Carlo program for integrated simulation of nuclear system developed by FDS Team, China, making use of hybrid MC-deterministic method and advanced computer technologies. The design aim, architecture and main methodology of SuperMC were presented in this paper. SuperMC2.1, the latest version for neutron, photon and coupled neutron and photon transport calculation, has been developed and validated by using a series of benchmarking cases such as the fusion reactor ITER model and the fast reactor BN-600 model. SuperMC is still in its evolution process toward a general and routine tool for nuclear system. Warning, no authors found for 2014snam.conf06023.

  13. Insights from the IAEA extrabugetary program on the safety of WWER and RBMK nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lederman, L. [IAEA, Vienna (Austria). Div. of Nuclear Instalation Safety; Goodison, D. [Nuclear Installation Inspectorate (NII), Formby (United Kingdom); Chakraborty, S. [Federal Nuclear Safety Inspectorate (HSK), Villingen (Switzerland). Safety Research and International Affairs

    1999-06-01

    An IAEA Extrabudgetary Program commenced in 1990. The objective of the Program was to assist regulators and operators of WWER and RBMK nuclear power plants to evaluate safety aspects related to the design and operation of these plants. The program terminated in 1998 and a comprehensive final report was published by the IAEA. The results showed that despite the improvements in safety already achieved, much remains to be done at individual NPPs, particularly at the WWER and RBMK plants of the first generation. Safety improvement work for these plants is essential if they are not decommissioned in the near future. The IAEA is continuing to provide specific assistance to Member States with WWER and RBMK NPPs. A specific project on WWER and RBMK safety has already been included in the IAEA Nuclear Safety program for 1999-2000. Three ongoing regional Technical Co-operation projects are also being extended until the year 2000. An important element of this assistance is to strengthen the national regulatory authorities in the countries operating these NPPs on the basis of IAEA recommendations and good international regulatory practices. Of utmost importance is to ensure that the operating organisations draw up a safety case for each NPP based on a plant specific safety analysis and that it is reviewed and approved by the national regulatory authorities. This will allow an assessment of the overall safety impact of plant modifications. (orig.) [Deutsch] Im Jahr 1990 begann ein Zusatzprogramm zum Haushalt der IAEO (Internationale Atomenergie-Organisation). Das Ziel dieses Programms war die Unterstuetzung der Regulierer und Betreiber der Kernkraftwerke des Typs WWER und RBMK bei der Bewertung der Sicherheitsaspekte hinsichtlich der Konstruktion und des Betriebs dieser KKWs. Das Programm lief im Jahr 1998 aus und die IAEO veroeffentlichte einen umfangreichen Abschlussbericht. Die Ergebnisse zeigten, dass trotz der bereits erreichten sicherheitstechnischen Verbesserungen bei

  14. Health consequences and health systems response to the Pacific U.S. Nuclear Weapons Testing Program.

    Science.gov (United States)

    Palafox, Neal A; Riklon, Sheldon; Alik, Wilfred; Hixon, Allen L

    2007-03-01

    Between 1946 and 1958, the United States detonated 67 thermonuclear devices in the Pacific as part of their U.S. Nuclear Weapons Testing Program (USNWTP). The aggregate explosive power was equal to 7,200 Hiroshima atomic bombs. Recent documents released by the U.S. government suggest that the deleterious effects of the nuclear testing were greater and extended farther than previously known. The Republic of the Marshall Islands (RMI) government and affected communities have sought refress through diplomatic routes with the U.S. government, however, existing medical programs and financial reparations have not adequately addressed many of the health consequences of the USNWTP. Since radiation-induced cancers may have a long latency, a healthcare infrastructure is needed to address both cancer and related health issues. This article reviews the health consequences of the Pacific USNWTP and the current health systems ability to respond.

  15. RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Yuan, Y.C. [Square Y Consultants, Orchard Park, NY (US); Chen, S.Y.; Biwer, B.M.; LePoire, D.J. [Argonne National Lab., IL (US)

    1995-11-01

    This report presents the technical details of RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, interactive program that can be run on an IBM or equivalent personal computer under the Windows{trademark} environment. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incident-free models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionuclide inventory and dose conversion factors. In addition, the flexibility of the models allows them to be used for assessing any accidental release involving radioactive materials. The RISKIND code allows for user-specified accident scenarios as well as receptor locations under various exposure conditions, thereby facilitating the estimation of radiological consequences and health risks for individuals. Median (50% probability) and typical worst-case (less than 5% probability of being exceeded) doses and health consequences from potential accidental releases can be calculated by constructing a cumulative dose/probability distribution curve for a complete matrix of site joint-wind-frequency data. These consequence results, together with the estimated probability of the entire spectrum of potential accidents, form a comprehensive, probabilistic risk assessment of a spent nuclear fuel transportation accident.

  16. Psychological Assessment Training in Clinical Psychology Doctoral Programs.

    Science.gov (United States)

    Mihura, Joni L; Roy, Manali; Graceffo, Robert A

    2017-01-01

    We surveyed American Psychological Association-accredited clinical psychology doctoral programs' (n = 83) training in psychological assessment-specifically, their coverage of various assessment topics and tests in courses and practica, and whether the training was optional or required. We report results overall and separately per training model (clinical science, scientist-practitioner, and practitioner-focused). Overall, our results suggest that psychological assessment training is as active, or even more active, than in previous years. Areas of increased emphasis include clinical interviewing and psychometrics; multimethod, outcomes, health, and collaborative or therapeutic assessment; and different types of cognitive and self-report personality tests. All or almost all practice-focused programs offered training with the Thematic Apperception Test and Rorschach compared to about half of the scientist-practitioner programs and a third of the clinical science programs. Although almost all programs reported teaching multimethod assessment, what constitutes different methods of assessing psychopathology should be clarified in future studies because many programs appear to rely on one method-self-report (especially clinical science programs). Although doctoral programs covered many assessment topics and tests in didactic courses, there appears to be a shortage of program-run opportunities for students to obtain applied assessment training. Finally, we encourage doctoral programs to be familiar with (a) internships' assessment expectations and opportunities, (b) the professional guidelines for assessment training, and (c) the American Psychological Association's requirements for preinternship assessment competencies.

  17. Recommended research program for improving seismic safety of light-water nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-04-01

    Recommendations are presented for research areas concerned with seismic safety. These recommendations are based on an analysis of the answers to a questionnaire which was sent to over 80 persons working in the area of seismic safety of nuclear power plants. In addition to the answers of the 55 questionnaires which were received, the recommendations are based on ideas expressed at a meeting of an ad hoc group of professionals formed by Sandia, review of literature, current research programs, and engineering judgement.

  18. Nuclear ubiquitin proteasome degradation affects WRKY45 function in the rice defense program

    OpenAIRE

    Matsushita, Akane; Inoue, Haruhiko; Goto, Shingo; NAKAYAMA, Akira; Sugano, Shoji; Hayashi, Nagao; Takatsuji, Hiroshi

    2012-01-01

    The transcriptional activator WRKY45 plays a major role in the salicylic acid/benzothiadiazole-induced defense program in rice. Here, we show that the nuclear ubiquitin?proteasome system (UPS) plays a role in regulating the function of WRKY45. Proteasome inhibitors induced accumulation of polyubiquitinated WRKY45 and transient up-regulation of WRKY45 target genes in rice cells, suggesting that WRKY45 is constantly degraded by the UPS to suppress defense responses in the absence of defense sig...

  19. Nuclear safeguards research and development. Program status report, October 1980-January 1981

    Energy Technology Data Exchange (ETDEWEB)

    Henry, C.N. (comp.)

    1981-11-01

    This report presents the status of the Nuclear Safeguards Research and Development Program pursued by the Energy, Chemistry-Materials Science, and Operational Security/Safeguards Divisions of the Los Alamos National Laboratory. Topics include nondestructive assay technology development and applications, international safeguards systems. Also discussed are training courses, technology transfer, analytical chemistry methods for fissionable materials safeguards, the Department of Energy Computer Security Technical Center, and operational security.

  20. A study of the international trend and comprehensive enhancement program on the Nuclear Power Plant safety

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Soon Hong; Cho, Nam Jin; Paek, Won Phil [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)] (and others)

    1990-12-15

    The objectives of this study are as follows : overview of the international trend related to the safety of Nuclear Power Plant(NPPs), study of the present status of NPP safety in Korea in aspects of design, construction and operation, suggestion of the comprehensive program to improve NPP safety in Korea. The results of this study can contribute to improve the safety of existing and future NPPs, and to establish the severe accident policy in Korea.

  1. Russia and the Iranian Nuclear Program: Replay or Breakthrough? (Strategic Perspectives, no. 9)

    Science.gov (United States)

    2012-03-01

    Nuclear Program Executive Summary Despite protests across Russia sparked by last December’s fraud-filled Duma (parlia- ment) elections, Vladimir Putin ...is preparing to return to the presidency this May. Will Putin replay his 2004–2008 approach to Iran, during which Russia negotiated the S–300 air... Russia under Pu- tin actually refrained from negotiating and concluding any significant new arms contracts with Iran until 2004. Putin was the first

  2. Performance Assessment of a Generic Repository in Bedded Salt for DOE-Managed Nuclear Waste

    Science.gov (United States)

    Stein, E. R.; Sevougian, S. D.; Hammond, G. E.; Frederick, J. M.; Mariner, P. E.

    2016-12-01

    A mined repository in salt is one of the concepts under consideration for disposal of DOE-managed defense-related spent nuclear fuel (SNF) and high level waste (HLW). Bedded salt is a favorable medium for disposal of nuclear waste due to its low permeability, high thermal conductivity, and ability to self-heal. Sandia's Generic Disposal System Analysis framework is used to assess the ability of a generic repository in bedded salt to isolate radionuclides from the biosphere. The performance assessment considers multiple waste types of varying thermal load and radionuclide inventory, the engineered barrier system comprising the waste packages, backfill, and emplacement drifts, and the natural barrier system formed by a bedded salt deposit and the overlying sedimentary sequence (including an aquifer). The model simulates disposal of nearly the entire inventory of DOE-managed, defense-related SNF (excluding Naval SNF) and HLW in a half-symmetry domain containing approximately 6 million grid cells. Grid refinement captures the detail of 25,200 individual waste packages in 180 disposal panels, associated access halls, and 4 shafts connecting the land surface to the repository. Equations describing coupled heat and fluid flow and reactive transport are solved numerically with PFLOTRAN, a massively parallel flow and transport code. Simulated processes include heat conduction and convection, waste package failure, waste form dissolution, radioactive decay and ingrowth, sorption, solubility limits, advection, dispersion, and diffusion. Simulations are run to 1 million years, and radionuclide concentrations are observed within an aquifer at a point approximately 4 kilometers downgradient of the repository. The software package DAKOTA is used to sample likely ranges of input parameters including waste form dissolution rates and properties of engineered and natural materials in order to quantify uncertainty in predicted concentrations and sensitivity to input parameters. Sandia

  3. Teacher perceptions of a physical education statewide assessment program.

    Science.gov (United States)

    Rink, Judith; Jones, Laura; Kirby, Kym; Mitchell, Murray; Doutis, Panayiotis

    2007-06-01

    A statewide program assessment was established to make positive change in physical education school programs in South Carolina. Reform efforts depend both on balancing accountability for change and teacher support for change (Odden &Anderson, 1986). The purpose of the study was to determine teacher perceptions of the South Carolina Physical Education Assessment Program and its effects across six related themes including: changes in teaching and learning, changes in curriculum and instruction, teacher awareness of the assessment program, teacher support for the program, work place conditions, and the advocacy role of the program. It was also the purpose of this study to determine if the survey responses were in any way related to teacher and school variables. The overall results of the study indicated positive change and support for the assessment program, supporting the viability of the standards, assessment, and accountability reform effort to positively impact physical education programs.

  4. Guidelines for exposure assessment in health risk studies following a nuclear reactor accident.

    Science.gov (United States)

    Bouville, André; Linet, Martha S; Hatch, Maureen; Mabuchi, Kiyohiko; Simon, Steven L

    2014-01-01

    Worldwide concerns regarding health effects after the Chernobyl and Fukushima nuclear power plant accidents indicate a clear need to identify short- and long-term health impacts that might result from accidents in the future. Fundamental to addressing this problem are reliable and accurate radiation dose estimates for the affected populations. The available guidance for activities following nuclear accidents is limited with regard to strategies for dose assessment in health risk studies. Here we propose a comprehensive systematic approach to estimating radiation doses for the evaluation of health risks resulting from a nuclear power plant accident, reflected in a set of seven guidelines. Four major nuclear reactor accidents have occurred during the history of nuclear power production. The circumstances leading to these accidents were varied, as were the magnitude of the releases of radioactive materials, the pathways by which persons were exposed, the data collected afterward, and the lifestyle factors and dietary consumption that played an important role in the associated radiation exposure of the affected populations. Accidents involving nuclear reactors may occur in the future under a variety of conditions. The guidelines we recommend here are intended to facilitate obtaining reliable dose estimations for a range of different exposure conditions. We recognize that full implementation of the proposed approach may not always be feasible because of other priorities during the nuclear accident emergency and because of limited resources in manpower and equipment. The proposed approach can serve as a basis to optimize the value of radiation dose reconstruction following a nuclear reactor accident.

  5. Nuclear Fuel Assembly Assessment Project and Image Categorization

    Energy Technology Data Exchange (ETDEWEB)

    Lindsey, C.S.; Lindblad, T.; Waldemark, K. [Royal Inst. of Tech., Stockholm (Sweden); Hildingsson, Lars [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    1998-07-01

    A project has been underway to add digital imaging and processing to the inspection of nuclear fuel by the International Atomic Energy Agency. The ultimate goals are to provide the inspector not only with the advantages of Ccd imaging, such as high sensitivity and digital image enhancements, but also with an intelligent agent that can analyze the images and provide useful information about the fuel assemblies in real time. The project is still in the early stages and several interesting sub-projects have been inspired. Here we give first a review of the work on the fuel assembly image analysis and then give a brief status report on one of these sub-projects that concerns automatic categorization of fuel assembly images. The technique could be of benefit to the general challenge of image categorization

  6. Spectrophotometric assessment of nuclear proteins: a preliminary study

    Directory of Open Access Journals (Sweden)

    A Ubiali

    2009-06-01

    Full Text Available Qualitative evaluation of protein content in formalin fixed, paraffin-embedded tissues is usually performed by means of cytofluorimetric analysis. On the other hand, several studies underline the opportunity to measure the concentration of nuclear proteins, which is often accomplished by using complex techniques and instrumentation. In the present work, we suggest a new application for the spectrophotometric evaluation of protein content on extracted and isolated nuclei, based on EDTA treatment of specimens and chemical extraction of proteins, followed by direct spectrophotometric measurement at UV wavelengths. We also demonstrate how this parameter correlates with other diagnostic factors, such as the proliferation index (MIB-1 and the DNA content (ploidy of cells. This method is simple and effective, yet less expensive than other protein quantitation protocols.

  7. Bulk Electrical Cable Non-Destructive Examination Methods for Nuclear Power Plant Cable Aging Management Programs

    Energy Technology Data Exchange (ETDEWEB)

    Glass, Samuel W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, Anthony M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fifield, Leonard S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hartman, Trenton S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-01

    This Pacific Northwest National Laboratory milestone report describes progress to date on the investigation of nondestructive test methods focusing particularly on bulk electrical test methods that provide key indicators of cable aging and damage. The work includes a review of relevant literature as well as hands-on experimental verification of inspection capabilities. As nuclear power plants consider applying for second, or subsequent, license renewal to extend their operating period from 60 years to 80 years, it is important to understand how the materials installed in plant systems and components will age during that time and develop aging management programs to assure continued safe operation under normal and design basis events (DBE). Normal component and system tests typically confirm the cables can perform their normal operational function. The focus of the cable test program, however, is directed toward the more demanding challenge of assuring the cable function under accident or DBE. The industry has adopted 50% elongation at break (EAB) relative to the un-aged cable condition as the acceptability standard. All tests are benchmarked against the cable EAB test. EAB, however, is a destructive test so the test programs must apply an array of other nondestructive examination (NDE) tests to assure or infer the overall set of cable’s system integrity. Assessment of cable integrity is further complicated in many cases by vendor’s use of dissimilar material for jacket and insulation. Frequently the jacket will degrade more rapidly than the underlying insulation. Although this can serve as an early alert to cable damage, direct test of the cable insulation without violating the protective jacket becomes problematic. This report addresses the range of bulk electrical NDE cable tests that are or could be practically implemented in a field-test situation with a particular focus on frequency domain reflectometry (FDR). The FDR test method offers numerous advantages

  8. Development of hydrogeological modelling approaches for assessment of consequences of hazardous accidents at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Rumynin, V.G.; Mironenko, V.A.; Konosavsky, P.K.; Pereverzeva, S.A. [St. Petersburg Mining Inst. (Russian Federation)

    1994-07-01

    This paper introduces some modeling approaches for predicting the influence of hazardous accidents at nuclear reactors on groundwater quality. Possible pathways for radioactive releases from nuclear power plants were considered to conceptualize boundary conditions for solving the subsurface radionuclides transport problems. Some approaches to incorporate physical-and-chemical interactions into transport simulators have been developed. The hydrogeological forecasts were based on numerical and semi-analytical scale-dependent models. They have been applied to assess the possible impact of the nuclear power plants designed in Russia on groundwater reservoirs.

  9. Impact of quality assurance program: providing practice assessment.

    Science.gov (United States)

    Saporito, R A; Feldman, C A; Stewart, D C; Echoldt, H; Buchanan, R N

    1994-05-01

    Participation in a self-administered quality assessment (SAQA) program led to changes in New Jersey dentists' perceptions of practice quality. Ninety-four percent indicated they discovered practice deficiencies. This study suggests that using a self-administered quality assessment program, such as the SAQA program, can lead to a better understanding of a practice's strengths and weaknesses.

  10. Strengthening Teacher Education Program: Keys to Develop through Teacher Assessment

    OpenAIRE

    Tecnam Yoon

    2014-01-01

    Teacher performance assessment is a part of a global trend based on teacher education program. The purpose of this paper is to investigate the American Teacher Performance Assessment (TPA) program, to identify some of the features in creating a system for pre-service teachers in developing countries, and to suggest an ideal TPA model for strengthening the teacher education program.

  11. Listening for the Squeaky Wheel: Designing Distance Writing Program Assessment

    Science.gov (United States)

    Tucker, Virginia M.

    2012-01-01

    Distance writing programs still struggle with assessment strategies that can evaluate student writing as well as their ability to communicate about that writing with peers at a distance. This article uses Kim, Smith and Maeng's 2008 distance education program assessment scheme to evaluate a single distance writing program at Old Dominion…

  12. On the fundamentals of nuclear reactor safety assessment. Inherent threats and their implications

    Energy Technology Data Exchange (ETDEWEB)

    Hyvaerinen, J. [Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland). Nuclear Safety Dept.

    1996-12-01

    The thesis addresses some fundamental questions related to implementation and assessment of nuclear safety. The safety principles and assessment methods are described, followed by descriptions of selected novel technical challenges to nuclear safety. The novel challenges encompass a wide variety of technical issues, thus providing insights on the limitations of conventional safety assessment methods. Study of the limitations suggests means to improve nuclear reactor design criteria and safety assessment practices. The novel safety challenges discussed are (1) inherent boron dilution in PWRs, (2) metallic insulation performance with respect to total loss of emergency cooling systems in a loss-of-coolant accident, and (3) horizontal steam generator heat transfer performance at natural circulation conditions. (50 refs.).

  13. Use of comparative assessment framework for comparison of geological nuclear waste and CO2 disposal technologies

    Energy Technology Data Exchange (ETDEWEB)

    Streimikiene, Dalia

    2010-09-15

    Comparative assessment of few future energy and climate change mitigation options for Lithuania in 2020 performed indicated that nuclear and combined cycle gas turbine technologies are very similar energy options in terms of costs taking into account GHG emission reduction costs. Comparative assessment of these energy options requires evaluation of the potentials and costs for geological CO2 and nuclear waste storage as the main uncertainties in comparative assessment of electricity generation technologies are related with these back-end technologies. The paper analyses the main characteristics of possible geological storage of CO2 and NW options in Lithuania.

  14. Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

    1985-11-01

    This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training.

  15. Economic Assessment of Russian Nuclear Strategies on the Basis of Fast Breeder Reactors

    Directory of Open Access Journals (Sweden)

    O. V. Marchenko

    2013-01-01

    Full Text Available The paper assesses the economic risk caused by the delay in commissioning innovative nuclear power plants with fast breeder reactors in Russia. The risk is quantitatively measured by the excessive costs for energy development and the possibility of implementing the considered variants that differ in power consumption, technical and economic indices of the reactors, and constraints on CO2 emissions. The probability distribution functions of economic losses for different strategies of nuclear energy development are constructed.

  16. Assessment of radiation exposure of nuclear medicine staff using personal TLD dosimeters and charcoal detectors

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez, F.; Garcia-Talavera, M.; Pardo, R.; Deban, L. [Valladolid Univ., Dept. de Quimica Analitica, Facultad de Ciencias (Spain); Garcia-Talavera, P.; Singi, G.M.; Martin, E. [Hospital Clinico Univ., Servicio de Medicina Nuclear, Salamanca (Spain)

    2006-07-01

    Although the main concern regarding exposure to ionizing radiation for nuclear medicine workers is external radiation, inhalation of radionuclides can significantly contribute to the imparted doses. We propose a new approach to assess exposure to inhalation of {sup 131}I based on passive monitoring using activated charcoal detectors. We compared the inhalation doses to the staff of a nuclear medicine department, based on the measurements derived from charcoal detectors placed at various locations, and the external doses monitored using personal TLD dosimeters. (authors)

  17. Guidelines for Exposure Assessment in Health Risk Studies Following a Nuclear Reactor Accident

    OpenAIRE

    Bouville, André; Linet, Martha S.; Hatch, Maureen; Mabuchi, Kiyohiko; Simon, Steven L.

    2013-01-01

    Background: Worldwide concerns regarding health effects after the Chernobyl and Fukushima nuclear power plant accidents indicate a clear need to identify short- and long-term health impacts that might result from accidents in the future. Fundamental to addressing this problem are reliable and accurate radiation dose estimates for the affected populations. The available guidance for activities following nuclear accidents is limited with regard to strategies for dose assessment in health risk s...

  18. [Assessment of the congenital syphilis prevention programs].

    Science.gov (United States)

    Daoud, M; Duca, Elena; Onofriescu, M; Petrescu, Zenaida

    2011-01-01

    The Romanian program for the management and screening of syphilis includes the recording, follow-up, and antenatal care of pregnant women. It aims at testing all pregnant women for syphilis with the help of VDLR (Venereal Disease Research Laboratory) or RPR (Rapid Plasma Reagin) tests, and in the women with positive tests to confirm the results by treponemal tests (treponemal antibodies): THPA (Treponema Pallidum Hemagglutination), FTA-Abs (Fluorescent Treponemal Antibody with Absorption), ELISA-Captia-IgM, and Western Blotting-IgM. In the pregnant women with positive tests two doses of 2.4 million units of penicillin G benzathine were administered at 5 days interval. These pregnant women are in the evidence of a specialist (obstetrician, dermatologist), and District Department of Public Health, and required to come for another serology test in 3 months. In case they still test positive, the same treatment is applied at the beginning of the third trimester of pregnancy. To assess the outcome of congenital syphilis prevention programs in lasi, Romania. In the interval 2005-2011, in the Iasi town, 84 RPR positive pregnant women were recorded. There was no significant difference in the number of pregnant women residing in urban as compared to rural areas. Most of these women were from poor social environments and had a low level of education. The diagnosis of acquired syphilis was made by serological tests as most pregnant women presented in the period of syphilis latency, being asymptomatic. All pregnant women followed the treatment, and were tested periodically. Ultrasound examination was normal in all women (no changes suggestive of fetal malformations). Free clinical, laboratory, and ultrasound investigations, history taking, psychological assessment, sex education, rapid identification of contacts of known patients, follow-up of the interaction between health care providers and syphilitic pregnant women, booklets, and leaflets altogether made that in the last 3

  19. What can Iran gain by having a nuclear weapons program that threatens to destabilize security in the Middle East?

    DEFF Research Database (Denmark)

    Nielsen, Thomas Galasz

    In this paper, Iran’s nuclear aspiration to destabilise power in the Middle East is analysed. Iran is attempting to develop a nuclear energy program, and perhaps even a nuclear weapons program, despite assurances of the opposite. An Iranian nuclear weapon would be a game changer in the region......, and domestic challenges, caused in part by United Nations’ sanctions, lack of development and internal political power struggles. Iran balances cleverly on the edge of either further international isolation or becoming a significant local power. It uses the threat of developing nuclear weapons, in com...... and a lot of neigh- bouring countries fear such a development for security reasons. But why is Iran following a nuclear path that may further destabilise the fragile security situation in the Middle East? It is to do with Iran’s own perception of security risks, its desire for greatness in the region...

  20. Assessement of Codes and Standards Applicable to a Hydrogen Production Plant Coupled to a Nuclear Reactor

    Energy Technology Data Exchange (ETDEWEB)

    M. J. Russell

    2006-06-01

    This is an assessment of codes and standards applicable to a hydrogen production plant to be coupled to a nuclear reactor. The result of the assessment is a list of codes and standards that are expected to be applicable to the plant during its design and construction.

  1. National Nuclear Security Administration Nonproliferation Graduate Fellowship Program Annual Report in Brief: October 2007 - May 2008

    Energy Technology Data Exchange (ETDEWEB)

    Berkman, Clarissa O.; Fankhauser, Jana G.; Sandusky, Jessica A.

    2009-05-01

    This abbreviated Annual Report covers program activities of the National Nuclear Security Administration (NNSA) Nonproliferation Graduate Fellowship Program (NGFP) from October 2007 through May 2008--the timeframe between the last Annual Report (which covered activities through September 2007) and the next report (which will begin with June 2008 activities). In that timeframe, the NGFP continued building a solid foundation as the program began reaping the benefits of recently implemented changes. This report is organized by Fellowship class and the pertinent program activities for each, including: October 2007 Recruiting events and final applications (Class of 2008) Winter 2007 Selection and hiring (Class of 2008) Spring 2008 Career development roundtables (Class of 2007) Orientation planning (Class of 2008) Recruitment planning and university outreach (Class of 2009) May 2008 Closing ceremony (Class of 2007)

  2. Final summary report of the Nordic Nuclear Safety Research Program 1998-2001; Sammanfattning av det nordiska forsknings-programmet for karnsakerhet

    Energy Technology Data Exchange (ETDEWEB)

    Bennerstedt, T. (ed.)

    2002-11-01

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

  3. A CAD (Classroom Assessment Design) of a Computer Programming Course

    Science.gov (United States)

    Hawi, Nazir S.

    2012-01-01

    This paper presents a CAD (classroom assessment design) of an entry-level undergraduate computer programming course "Computer Programming I". CAD has been the product of a long experience in teaching computer programming courses including teaching "Computer Programming I" 22 times. Each semester, CAD is evaluated and modified…

  4. Development and Operation of International Nuclear Education/Training Program and HRD Cooperation Network

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Min, B. J.; Han, K. W. (and others)

    2006-12-15

    The primary result of the project is the establishment of a concept of International Nuclear R and D Academy that integrates the on-going long term activity for international nuclear education/training and a new activity to establish an international cooperation network for nuclear human resources development. For this, the 2007 WNU Summer Institute was hosted with the establishment of an MOU and subsequent preparations. Also, ANENT was promoted through development of a cyber platform for the ANENT web-portal, hosting the third ANENT Coordination Committee meeting, etc. Then a cooperation with universities in Vietnam was launched resulting in preparation of an MOU for the cooperation. Finally, a relevant system framework was established and required procedures were drafted especially for providing students from developing countries with long term education/training programs (e.g. MS and Ph D. courses). The international nuclear education/training programs have offered 13 courses to 182 people from 43 countries. The overall performance of the courses was evaluated to be outstanding. In parallel, the establishment of an MOU for the cooperation of KOICA-IAEA-KAERI courses to ensure their stable and systematic operation. Also, an effort was made to participate in FNCA. Atopia Hall of the International Nuclear Training and Education Center (INTEC) hosted 477 events (corresponding to 18,521 participants) and Nuri Hall (guesthouse) accommodated 4,616 people in 2006. This shows a steady increase of the use rate since the opening of the center, along with a continuous improvement of the equipment.

  5. V-Model based Configuration Management Program for New-Build Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    An, Kyungik [PartDB Co. Ltd., Daejeon (Korea, Republic of); Cho, Yoon Sang [KHNP Co. Ltd., Daejeon (Korea, Republic of); Freeland, Kent R. [Industrial Analysts Incorporated, New Hampshire (United States)

    2014-05-15

    As NPP operators undertook design basis reconstitution efforts, they began to realize that the design basis is a foundation for Configuration Management (CM). This realization was made evident in the magnitude of the problems that were being observed. This experience also raised serious questions about how the information being developed to produce the design basis documents would be kept up to date in the future. A process to reconstitute the design basis is likely to be ineffective if CM controls are not in place. The right IT solution for CM depends upon a number of factors, including the nuclear power plant culture, budget, target technology, and the nuclear power plant owner/operator's standards, requirements and limitations for its generating fleet. Comprehensive CM Program for NPP is the single greatest strategy to meet the commitment to nuclear excellence. The safety and viability of nuclear power, particularly at the fleet level, depends upon the development of positive design control and design basis to better understanding plant operating dynamics and margin management, along with technology to control the realization of such design in the physical plant. However the most of plant facilities are modified many times, often without suitable support needed to confirm with their design base and to update their engineering data, maintenance rules and operating procedures. This lack of equilibrium between the requirements, design information and physical plant still remains a important issue. This study focuses on how to manage the configuration information of NPP using systems engineering V-model approach, and proposes data model to manage the configuration information in relation to manage their life cycle. Comprehensive CM Program and IMS for NPP life cycle support is the greatest strategy to meet the commitment to nuclear safety.

  6. A program in medium energy nuclear physics. Progress report, January 1, 1992--March 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Berman, B.L.; Dhuga, K.S.

    1995-10-01

    This progress report and continuation proposal summarizes our achievements for the period from July 1, 1994 to September 30, 1995 and requests continued funding for our program in experimental medium-energy nuclear physics. The focus of our program remains the understanding of the short-range part of the strong interaction in the nuclear medium. In the past year we have focused our attention ever more sharply on experiments with real tagged photons, and we have successfully defended two new experimental proposals: Photofission of Actinide and Preactinide Nuclei at SAL and Photoproduction of the {rho} Meson from the Proton with Linearly Polarized Photons at CEBAF. (We are co-spokespersons on two previously approved Hall-B experiments at CEBAF, Photoreactions on {sup 3}He and Photoabsorption and Photofission of Nuclei.) As part of the team that is instrumenting the Photon Tagger for Hall B; we report excellent progress on the focal-plane detector array that is being built at our Nuclear Detector Laboratory, as well as progress on our plans for instrumentation of a tagged polarized-photon beam using coherent bremsstrahlung. Also, we shall soon receive a large computer system (from the SSC) which will form the basis for our new Data Analysis Center, which, like the Nuclear Detector Laboratory, will be operated under the auspices of The George Washington University Center for Nuclear Studies. Finally, during the past year we have published six more papers on the results of our measurements of pion scattering at LAMPF and of electron scattering at NIKHEF and Bates, and we can report that nearly all of the remaining papers documenting this long series of measurements are in the pipeline.

  7. Trend of public perception on nuclear energy and future PA programs for winning public consensus in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Choe, Seung-Jin [Organization for Korea Atomic Energy Awareness, Seoul (Korea, Republic of)

    1996-10-01

    Before the second half of 1980`s, the Korean government could carry out the nuclear power projects easily without any oppositions. However, the anti-nuclear and environmental preservation movement has been more vigorous after Chernobyl accident. Since 1987, the democratized social environment and improved standard of living which is resulted from economic growth have increased the public interest on a positive environment and safety of life. Moreover, the introduction of local self-government system has imposed heavy burdens on nuclear power development. The prevailing of local egoism is also a hard task to overcome in securing nuclear facility sites. The public began to recognize the necessity of nuclear energy. However, this is still a far cry from the ultimate target to the site selection. Therefore, winning public acceptance is the most important issue in implementing the nation`s nuclear programs without significant obstacles, and it is necessary to develop sociopolitical approaches to deal with nuclear issues. (author)

  8. NANA Wind Resource Assessment Program Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Jay Hermanson

    2010-09-23

    NANA Regional Corporation (NRC) of northwest Alaska is located in an area with abundant wind energy resources. In 2007, NRC was awarded grant DE-FG36-07GO17076 by the US Department of Energy's Tribal Energy Program for funding a Wind Resource Assessment Project (WRAP) for the NANA region. The NANA region, including Kotzebue Electric Association (KEA) and Alaska Village Electric Cooperative (AVEC) have been national leaders at developing, designing, building, and operating wind-diesel hybrid systems in Kotzebue (starting in 1996) and Selawik (2002). Promising sites for the development of new wind energy projects in the region have been identified by the WRAP, including Buckland, Deering, and the Kivalina/Red Dog Mine Port Area. Ambler, Shungnak, Kobuk, Kiana, Noorvik & Noatak were determined to have poor wind resources at sites in or very near each community. However, all five of these communities may have better wind resources atop hills or at sites with slightly higher elevations several miles away.

  9. Adaptive Sampling Algorithms for Probabilistic Risk Assessment of Nuclear Simulations

    Energy Technology Data Exchange (ETDEWEB)

    Diego Mandelli; Dan Maljovec; Bei Wang; Valerio Pascucci; Peer-Timo Bremer

    2013-09-01

    Nuclear simulations are often computationally expensive, time-consuming, and high-dimensional with respect to the number of input parameters. Thus exploring the space of all possible simulation outcomes is infeasible using finite computing resources. During simulation-based probabilistic risk analysis, it is important to discover the relationship between a potentially large number of input parameters and the output of a simulation using as few simulation trials as possible. This is a typical context for performing adaptive sampling where a few observations are obtained from the simulation, a surrogate model is built to represent the simulation space, and new samples are selected based on the model constructed. The surrogate model is then updated based on the simulation results of the sampled points. In this way, we attempt to gain the most information possible with a small number of carefully selected sampled points, limiting the number of expensive trials needed to understand features of the simulation space. We analyze the specific use case of identifying the limit surface, i.e., the boundaries in the simulation space between system failure and system success. In this study, we explore several techniques for adaptively sampling the parameter space in order to reconstruct the limit surface. We focus on several adaptive sampling schemes. First, we seek to learn a global model of the entire simulation space using prediction models or neighborhood graphs and extract the limit surface as an iso-surface of the global model. Second, we estimate the limit surface by sampling in the neighborhood of the current estimate based on topological segmentations obtained locally. Our techniques draw inspirations from topological structure known as the Morse-Smale complex. We highlight the advantages and disadvantages of using a global prediction model versus local topological view of the simulation space, comparing several different strategies for adaptive sampling in both

  10. Assessment in Accelerated Learning Programs: A Practical Guide.

    Science.gov (United States)

    Walvoord, Barbara E.

    2003-01-01

    Discusses these aspects of accelerated learning program assessment: defining learning goals, selecting instruments to evaluate performance, establishing relationships between performance and other factors, and improving performance and programs using evaluation data. (SK)

  11. Evaluating Prior Learning Assessment Programs: A Suggested Framework

    Directory of Open Access Journals (Sweden)

    Nan L. Travers and Marnie T. Evans

    2011-01-01

    Full Text Available Over the past two decades, American institutions have been expected to include systematic program reviews to meet accrediting standards, either by independent or governmental review agencies. Program evaluation is critical for several reasons: it provides systematic ways to assess what needs improvement or what needs changing and it provides ways to validate practices, whether to internal or external audiences (Mishra, 2007. Most program evaluative models are focused on academic programs, which don’t fit the uniqueness of prior learning assessment programs. This paper proposes an evaluative framework for prior learning assessment programs, which takes into account the type of work within prior learning assessment programs and uses program portfolios, similar to how students are asked to document their work.

  12. Program Educational Objectives Definition and Assessment for Accreditation Purposes

    National Research Council Canada - National Science Library

    Noureddine Abbadeni; Ahmed Ghoneim; Abdullah AlGhamdi

    2013-01-01

    ... (Accreditation Board for Engineering and Technology). A key problem towards the satisfaction of ABET accreditation criteria is the appropriate definition and assessment of program educational objectives for a specific degree program...

  13. Assessment of Nuclear Fuels using Radiographic Thickness Measurement Method

    Energy Technology Data Exchange (ETDEWEB)

    Muhammad Abir; Fahima Islam; Hyoung Koo Lee; Daniel Wachs

    2014-11-01

    The Convert branch of the National Nuclear Security Administration (NNSA) Global Threat Reduction Initiative (GTRI) focuses on the development of high uranium density fuels for research and test reactors for nonproliferation. This fuel is aimed to convert low density high enriched uranium (HEU) based fuel to high density low enriched uranium (LEU) based fuel for high performance research reactors (HPRR). There are five U.S. reactors that fall under the HPRR category, including: the Massachusetts Institute of Technology Reactor (MITR), the National Bureau of Standards Reactor (NBSR), the Missouri University Research Reactor (UMRR), the Advanced Test Reactor (ATR), and the High Flux Isotope Reactor (HFIR). U-Mo alloy fuel phase in the form of either monolithic or dispersion foil type fuels, such as ATR Full-size In center flux trap Position (AFIP) and Reduced Enrichment for Research and Test Reactor (RERTR), are being designed for this purpose. The fabrication process1 of RERTR is susceptible to introducing a variety of fuel defects. A dependable quality control method is required during fabrication of RERTR miniplates to maintain the allowable design tolerances, therefore evaluating and analytically verifying the fabricated miniplates for maintaining quality standards as well as safety. The purpose of this work is to analyze the thickness of the fabricated RERTR-12 miniplates using non-destructive technique to meet the fuel plate specification for RERTR fuel to be used in the ATR.

  14. Three Types of Programed Learning and the Conventional Teaching of the Nuclear Chemistry Portion of the High School Chemistry Course.

    Science.gov (United States)

    Darnowski, Vincent S.

    Compared was the learning and retention of facts and principles of nuclear chemistry in the high school chemistry course using three forms of programed materials, and the conventional lecture-demonstration method of teaching. Groups using the programs gained significantly more than the control group, and among the three forms of programs, the…

  15. Programs for the work with ENSDF format files: Evaluator's editor EVE, Viewer for the nuclear level schemes

    CERN Document Server

    Shulyak, G I

    2010-01-01

    Tools for the regular work of the nuclear data evaluator are presented: the context-dependent editor EVE and the viewer for the level schemes of nuclei from ENSDF datasets. These programs may be used by everybody who works with the Evaluated Nuclear Structure Data File and for the educational purposed.

  16. Proceedings of seventh symposium on sharing of computer programs and technology in nuclear medicine, computer assisted data processing

    Energy Technology Data Exchange (ETDEWEB)

    Howard, B.Y.; McClain, W.J.; Landay, M. (comps.)

    1977-01-01

    The Council on Computers (CC) of the Society of Nuclear Medicine (SNM) annually publishes the Proceedings of its Symposium on the Sharing of Computer Programs and Technology in Nuclear Medicine. This is the seventh such volume and has been organized by topic, with the exception of the invited papers and the discussion following them. An index arranged by author and by subject is included.

  17. Realistic retrospective dose assessments to members of the public around Spanish nuclear facilities.

    Science.gov (United States)

    Jiménez, M A; Martín-Valdepeñas, J M; García-Talavera, M; Martín-Matarranz, J L; Salas, M R; Serrano, J I; Ramos, L M

    2011-11-01

    In the frame of an epidemiological study carried out in the influence areas around the Spanish nuclear facilities (ISCIII-CSN, 2009. Epidemiological Study of The Possible Effect of Ionizing Radiations Deriving from The Operation of Spanish Nuclear Fuel Cycle Facilities on The Health of The Population Living in Their Vicinity. Final report December 2009. Ministerio de Ciencia e Innovación, Instituto de Salud Carlos III, Consejo de Seguridad Nuclear. Madrid. Available from: http://www.csn.es/images/stories/actualidad_datos/especiales/epidemiologico/epidemiological_study.pdf), annual effective doses to public have been assessed by the Spanish Nuclear Safety Council (CSN) for over 45 years using a retrospective realistic-dose methodology. These values are compared with data from natural radiation exposure. For the affected population, natural radiation effective doses are in average 2300 times higher than effective doses due to the operation of nuclear installations (nuclear power stations and fuel cycle facilities). When considering the impact on the whole Spanish population, effective doses attributable to nuclear facilities represent in average 3.5×10(-5)mSv/y, in contrast to 1.6mSv/y from natural radiation or 1.3mSv/y from medical exposures. Copyright © 2011 Elsevier Ltd. All rights reserved.

  18. Quo Vadis, Japan. [Status of Japan's Nuclear Power Program

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    A pile of plutonium - 1.4 tonnes in all - was on board Japanese nuclear transport ship Akatsuki Maru when it left France on November 8, 1992 for Japan. Alongside it were Greenpeace's hostile and ever-vigilant boats and the great swells of public protest from around the world. Transports like this are likely to follow. But more to the tune of 30 to 40 tonnes of plutonium cargo is expected from the Japanese spent fuel that is separated at European reprocessing plants. Both Japanese utilities and governmental agencies have agreed that plutonium is to be fabricated into mixed oxide fuel (MOX) before being returned to Japan. But in the meantime, critics are accusing Japan of being one of the greatest threats to international safety. After the Akatsuki Maru spectacle, the Japanese civil nuclear program is awash in criticism and can not escape the watchful eye of the international community. Now, with Japan's parliamentary elections over and a review of its nuclear program just around the corner, the question is: Quo vadis, Japan

  19. Assessment of water resources for nuclear energy centers

    Energy Technology Data Exchange (ETDEWEB)

    Samuels, G.

    1976-09-01

    Maps of the conterminous United States showing the rivers with sufficient flow to be of interest as potential sites for nuclear energy centers are presented. These maps show the rivers with (1) mean annual flows greater than 3000 cfs, with the flow rates identified for ranges of 3000 to 6000, 6000 to 12,000, 12,000 to 24,000, and greater than 24,000 cfs; (2) monthly, 20-year low flows greater than 1500 cfs, with the flow rates identified for ranges of 1500 to 3000, 3000 to 6000, 6000 to 12,000, and greater than 12,000 cfs; and (3) annual, 20-year low flows greater than 1500 cfs, with the flow rates identified for ranges of 1500 to 3000, 3000 to 6000, 6000 to 12,000, and greater than 12,000 cfs. Criteria relating river flow rates required for various size generating stations both for sites located on reservoirs and for sites without local storage of cooling water are discussed. These criteria are used in conjunction with plant water consumption rates (based on both instantaneous peak and annual average usage rates) to estimate the installed generating capacity that may be located at one site or within a river basin. Projections of future power capacity requirements, future demand for water (both withdrawals and consumption), and regions of expected water shortages are also presented. Regional maps of water availability, based on annual, 20-year low flows, are also shown. The feasibility of locating large energy centers in these regions is discussed.

  20. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement. Volume 1, Appendix B: Idaho National Engineering Laboratory Spent Nuclear Fuel Management Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) has prepared this report to assist its management in making two decisions. The first decision, which is programmatic, is to determine the management program for DOE spent nuclear fuel. The second decision is on the future direction of environmental restoration, waste management, and spent nuclear fuel management activities at the Idaho National Engineering Laboratory. Volume 1 of the EIS, which supports the programmatic decision, considers the effects of spent nuclear fuel management on the quality of the human and natural environment for planning years 1995 through 2035. DOE has derived the information and analysis results in Volume 1 from several site-specific appendixes. Volume 2 of the EIS, which supports the INEL-specific decision, describes environmental impacts for various environmental restoration, waste management, and spent nuclear fuel management alternatives for planning years 1995 through 2005. This Appendix B to Volume 1 considers the impacts on the INEL environment of the implementation of various DOE-wide spent nuclear fuel management alternatives. The Naval Nuclear Propulsion Program, which is a joint Navy/DOE program, is responsible for spent naval nuclear fuel examination at the INEL. For this appendix, naval fuel that has been examined at the Naval Reactors Facility and turned over to DOE for storage is termed naval-type fuel. This appendix evaluates the management of DOE spent nuclear fuel including naval-type fuel.

  1. Disposability Assessment: Aluminum-Based Spent Nuclear Fuel Forms

    Energy Technology Data Exchange (ETDEWEB)

    Vinson, D.W.

    1998-11-06

    This report provides a technical assessment of the Melt-Dilute and Direct Al-SNF forms in disposable canisters with respect to meeting the requirements for disposal in the Mined Geologic Disposal System (MGDS) and for interim dry storage in the Treatment and Storage Facility (TSF) at SRS.

  2. Monthly highlights for Office of Nuclear Regulatory Research Programs at Oak Ridge National Laboratory, August 1977

    Energy Technology Data Exchange (ETDEWEB)

    Fee, G.G. (comp.)

    1977-09-13

    Technical highlights are presented for the following safety-related studies: heavy section steel technology, fission product beta and gamma energy release, fission product release from LWR fuel, fission product transport tests, multirod burst tests, Nuclear Safety Information Center, PWR blowdown heat transfer-separate effects, zircaloy fuel cladding collapse studies, zirconium metal-water oxidation kinetics, aerosol release and transport from LMFBR fuel, HTGR safety analysis and research, design criteria for piping and nozzles, and noise diagnostics for safety assessment.

  3. 75 FR 3945 - Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and 2; Environmental Assessment and...

    Science.gov (United States)

    2010-01-25

    ... From the Federal Register Online via the Government Publishing Office ] NUCLEAR REGULATORY COMMISSION Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and 2; Environmental Assessment and... Tennessee Valley Authority (TVA, the licensee), for operation of the Watts Bar Nuclear Plant (WBN), Unit 1...

  4. 75 FR 43572 - Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2; Environmental Assessment and...

    Science.gov (United States)

    2010-07-26

    ... COMMISSION Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of... McGuire Nuclear Station, Units 1 and 2, or the Generic Environmental Impact Statement for License...

  5. 75 FR 14206 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment...

    Science.gov (United States)

    2010-03-24

    ... COMMISSION [Docket Nos. 50-266 And 50-301; NRC-2010-0123 FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear...-1437, Supplement 23, ``Generic Environmental Impact Statement for License Renewal of Nuclear Plants...

  6. 75 FR 43571 - Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; Environmental Assessment And...

    Science.gov (United States)

    2010-07-26

    ... COMMISSION Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; Environmental Assessment And Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of... Catawba Nuclear Station, Units 1 and 2, or the Generic Environmental Impact Statement for License Renewal...

  7. 75 FR 24997 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment...

    Science.gov (United States)

    2010-05-06

    ... COMMISSION FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering..., ``Generic Environmental Impact Statement for License Renewal of Nuclear Plants [regarding Point Beach...

  8. 75 FR 14637 - James A. FitzPatrick Nuclear Power Plant; Environmental Assessment and Finding of No Significant...

    Science.gov (United States)

    2010-03-26

    ... COMMISSION James A. FitzPatrick Nuclear Power Plant; Environmental Assessment and Finding of No Significant...), for the operation of the James A. FitzPatrick Nuclear Power Plant (JAFNPP) located in Oswego County... related to operation of James A. FitzPatrick Nuclear Power Plant Power Authority of the State of New York...

  9. Realistic retrospective dose assessments to members of the public around Spanish nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez, M.A., E-mail: majg@csn.es [Consejo de Seguridad Nuclear (CSN), Pedro Justo Dorado Dellmans 11, E-28040 Madrid (Spain); Martin-Valdepenas, J.M.; Garcia-Talavera, M.; Martin-Matarranz, J.L.; Salas, M.R.; Serrano, J.I.; Ramos, L.M. [Consejo de Seguridad Nuclear (CSN), Pedro Justo Dorado Dellmans 11, E-28040 Madrid (Spain)

    2011-11-15

    In the frame of an epidemiological study carried out in the influence areas around the Spanish nuclear facilities (ISCIII-CSN, 2009. Epidemiological Study of The Possible Effect of Ionizing Radiations Deriving from The Operation of Spanish Nuclear Fuel Cycle Facilities on The Health of The Population Living in Their Vicinity. Final report December 2009. Ministerio de Ciencia e Innovacion, Instituto de Salud Carlos III, Consejo de Seguridad Nuclear. Madrid. Available from: (http://www.csn.es/images/stories/actualidad{sub d}atos/especiales/epidemiologico/epidemiological{sub s}tudy.pdf)), annual effective doses to public have been assessed by the Spanish Nuclear Safety Council (CSN) for over 45 years using a retrospective realistic-dose methodology. These values are compared with data from natural radiation exposure. For the affected population, natural radiation effective doses are in average 2300 times higher than effective doses due to the operation of nuclear installations (nuclear power stations and fuel cycle facilities). When considering the impact on the whole Spanish population, effective doses attributable to nuclear facilities represent in average 3.5 x 10{sup -5} mSv/y, in contrast to 1.6 mSv/y from natural radiation or 1.3 mSv/y from medical exposures. - Highlights: > Most comprehensive dose assessment to public by nuclear facilities ever done in Spain. > Dose to public is dominated by liquid effluent pathways for the power stations. > Dose to public is dominated by Rn inhalation for milling and mining facilities. > Average annual doses to public in influence areas are negligible (10 {mu}Sv/y or less). > Doses from facilities average 3.5 x 10{sup -2} {mu}Sv/y per person onto whole Spanish population.

  10. System model for evaluation of an emergency response plan for a nuclear power plant based on an assessment of nuclear emergency exercises

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Marcos Vinicius C.; Medeiros, Jose A.C.C. [Universidade Federal do Rio de Janeiro (PEN/COPPE/UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao de Engenharia. Programa de Engenharia Nuclear

    2011-07-01

    Nuclear power plants are designed and built with systems dedicated to provide a high degree of protection to its workers, the population living in their neighborhoods and the environment. Among the requirements for ensuring safety there are the existence of the nuclear emergency plan. Due to the relationship between the actions contemplated in the emergency plan and the nuclear emergency exercise, it becomes possible to assess the quality of the nuclear emergency plan, by means of emergency exercise evaluation, The techniques used in this work aim at improving the evaluation method of a nuclear emergency exercise through the use of performance indicators in the evaluation of the structures, actions and procedures involved. The proposed model enables comparisons between different moments of an emergency plan directed to a nuclear power plant as well as comparisons between plans dedicated to different facilities. (author)

  11. Life-assessment technique for nuclear power plant cables

    Energy Technology Data Exchange (ETDEWEB)

    Bartonicek, B.; Hnat, V.; Placek, V

    1998-06-01

    The condition of polymer-based cable material can be best characterized by measuring elongation at break of its insulating materials. However, it is not often possible to take sufficiently large samples for measurement with the tensile testing machine. The problem has been conveniently solved by utilizing differential scanning calorimetry technique. From the tested cable, several microsamples are taken and the oxidation induction time (OIT) is determined. For each cable which is subject to the assessment of the lifetime, the correlation of OIT with elongation at break and the correlation of elongation at break with the cable service time has to be performed. A reliable assessment of the cable lifetime depends on accuracy of these correlations. Consequently, synergistic effects well known at this time - dose rate effects and effects resulting from the different sequence of applying radiation and elevated temperature must be taken into account.

  12. Workshop on environmental assessment. [Regulation of applications of nuclear energy and related ancillary systems

    Energy Technology Data Exchange (ETDEWEB)

    Watson, E.C. (comp.)

    1982-07-01

    Objectives of the workshop were: to review and evaluate the state-of-the-art of environmental impact assessments as applied to the regulation of applications of nuclear energy and related ancillary systems; to identify areas where existing technology allows establishing acceptable methods or standard practices that will meet the requirements of the NRC regulations, standards and guides for both normal operations and off-standard conditions including accident considerations; to illuminate topics where existing models or analytical methods are deficient because of unverified assumptions, a paucity of empirical data, conflicting results reported in the literature or a need for observation of operation systems; to compile, analyze and synthesize a prioritized set of research needs to advance the state-of-the-art to the level which will meet all of the requirements of the Commission's regulations, standards and guides; and to develop bases for maintaining the core of regulatory guidance at the optimum level balancing technical capabilities with practical considerations of cost and value to the regulatory process. The discussion held in small group sessions on aquatic, atmospheric, and terrestrial pathways are presented. The following research needs were identified as common to all three groups: validation of models; characterization of source terms; development of screening techniques; basis for de minimis levels of contamination; and updating of objectives for environmental monitoring programs.

  13. Generic Assessment Rubrics for Computer Programming Courses

    Science.gov (United States)

    Mustapha, Aida; Samsudin, Noor Azah; Arbaiy, Nurieze; Mohammed, Rozlini; Hamid, Isredza Rahmi

    2016-01-01

    In programming, one problem can usually be solved using different logics and constructs but still producing the same output. Sometimes students get marked down inappropriately if their solutions do not follow the answer scheme. In addition, lab exercises and programming assignments are not necessary graded by the instructors but most of the time…

  14. Quality Assessment of Research Articles in Nuclear Medicine Using STARD and QUADAS-2 Tools.

    Science.gov (United States)

    Roysri, Krisana; Chotipanich, Chanisa; Laopaiboon, Vallop; Khiewyoo, Jiraporn

    2014-01-01

    Diagnostic nuclear medicine is being increasingly employed in clinical practice with the advent of new technologies and radiopharmaceuticals. The report of the prevalence of a certain disease is important for assessing the quality of that article. Therefore, this study was performed to evaluate the quality of published nuclear medicine articles and determine the frequency of reporting the prevalence of studied diseases. We used Standards for Reporting of Diagnostic Accuracy (STARD) and Quality Assessment of Diagnostic Accuracy Studies (QUADAS-2) checklists for evaluating the quality of articles published in five nuclear medicine journals with the highest impact factors in 2012. The articles were retrieved from Scopus database and were selected and assessed independently by two nuclear medicine physicians. Decision concerning equivocal data was made by consensus between the reviewers. The average STARD score was approximately 17 points, and the highest score was 17.19±2.38 obtained by the European Journal of Nuclear Medicine. QUADAS-2 tool showed that all journals had low bias regarding study population. The Journal of Nuclear Medicine had the highest score in terms of index test, reference standard, and time interval. Lack of clarity regarding the index test, reference standard, and time interval was frequently observed in all journals including Clinical Nuclear Medicine, in which 64% of the studies were unclear regarding the index test. Journal of Nuclear Cardiology had the highest number of articles with appropriate reference standard (83.3%), though it had the lowest frequency of reporting disease prevalence (zero reports). All five journals had the same STARD score, while index test, reference standard, and time interval were very unclear according to QUADAS-2 tool. Unfortunately, data were too limited to determine which journal had the lowest risk of bias. In fact, it is the author's responsibility to provide details of research methodology so that the reader

  15. Self-assessment program implementation plan. Revision A

    Energy Technology Data Exchange (ETDEWEB)

    Quets, A.L.

    1991-10-23

    This implementation plan identifies and describes the tasks that must be completed in order to successfully implement a Self-Assessment (SA) Program. The purpose of the Self-Assessment Program is to comply with applicable Department of Energy (DOE) directives and orders, Federal, State, and local regulations, operate the Pinellas Plant according to best management practices, and achieve excellence in all operating areas. The Self-Assessment Program will be applied to the Pinellas Plant facility which includes buildings, grounds, equipment, operations, and activities under the control of line management. Furthermore, all applicable disciplines under environmental protection, safety, health and management will be covered by the program. The Self-Assessment Program has been designed to accomplish the following tasks: define the scope of the Self-Assessment Program; assign organizational roles and responsibilities; address EH and S functional elements and management issues; develop a Self-Assessment program charter and policy; identify all applicable EH and S codes, regulations and standards; develop self-assessment procedures and instructions; generate a Self-Assessment Manual; develop a master schedule for facility appraisals and audits; design checklists and report formats for recording appraisal data; implement an assessment tracking and reporting system; implement a root cause analysis and corrective action system; implement a trend analysis and lessons learned system; and establish a formal training program.

  16. An Overview of the Los Alamos Program on Asteroid Mitigation by a Nuclear Explosion

    Science.gov (United States)

    Weaver, R.; Gisler, G. R.; Plesko, C. S.; Ferguson, J.

    2014-12-01

    Los Alamos National Laboratory is standing up a new program to address the mitigation of a potentially hazardous objects (PHO) by using nuclear explosives. A series of efforts at Los Alamos have been working this problem for the last few years in an informal fashion. We now have a funded program to dedicate time to this important mission. The goal of our project is to study the effectiveness of using a nuclear explosive to mitigate (alter orbit or destroy) an PHO on an Earth crossing path. We are also pursuing studies of impact hazards should the international leadership decide not to organize a mission for active mitigation of a PHO. Such impact hazards are characterized as local, regional or global. Impact hazards include: a direct hit in an urban area (potentially catastrophic but highly unlikely); the generation a significant tsunami from an ocean impact close to a coastline and regional and global effects from medium to large impactors. Previous studies at Los Alamos have looked at 2D and 3D simulations in the deep ocean from large bolides, as well as impacts that have global consequences. More recent work has included radiation-hydrodynamic simulations of momentum transfer (and enhancement) from a low energy (10 kt) stand-off source, as well as surface and subsurface high energy explosions (100 kt - 10 Mt) for example PHOs. The current program will carefully look at two main aspects of using a standoff nuclear source: 1) a computational study for the optimum height-of-burst (HOB) of a stand-off burst using our best energy coupling techniques for both neutrons and x-rays; and 2) as a function of the nuclear energy produced and the HOB what is the optimum energy field: neutrons or x-rays. This team is also working with NNSA and NASA Goddard to compare numerical results for these complicated simulations on a well defined series of test problems involving both kinetic impactors and stand-off nuclear energy sources. Results will be shown by the co-authors on

  17. A State-of-the-Art Report on Technologies of a Safety Assessment and a Radioactivity Exposure Assessment for the Decommissioning Process of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan Seong; Kang, Young Ae; Lee, Dong Gyu; Lee, Kune Woo; Jung, Chong Hun

    2007-09-15

    This report is to provide the reference contents of research and development for technologies of radioactivity exposure and safety assessment for development of the decommissioning technology for nuclear facilities. This report consists of as follows: - Analyzing and discussing on state-of-the-art technologies of a radioactivity exposure assessment of a decommissioning for nuclear facilities - Analyzing and discussing on state-of-the-art technologies of a safety assessment of a decommissioning for nuclear facilities.

  18. EDISTR: a computer program to obtain a nuclear decay data base for radiation dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Dillman, L.T.

    1980-01-01

    This report provides documentation for the computer program EDISTR. EDISTR uses basic radioactive decay data from the Evaluated Nuclear Structure Data File developed and maintained by the Nuclear Data Project at the Oak Ridge National Laboratory as input, and calculates the mean energies and absolute intensities of all principal radiations associated with the radioactive decay of a nuclide. The program is intended to provide a physical data base for internal dosimetry calculations. The principal calculations performed by EDISTR are the determination of (1) the average energy of beta particles in a beta transition, (2) the beta spectrum as function of energy, (3) the energies and intensities of x-rays and Auger electrons generated by radioactive decay processes, (4) the bremsstrahlung spectra accompanying beta decay and monoenergetic Auger and internal conversion electrons, and (5) the radiations accompanying spontaneous fission. This report discusses the theoretical and empirical methods used in EDISTR and also practical aspects of the computer implementation of the theory. Detailed instructions for preparing input data for the computer program are included, along with examples and discussion of the output data generated by EDISTR.

  19. Comprehensive Auditing in Nuclear Medicine Through the International Atomic Energy Agency Quality Management Audits in Nuclear Medicine Program. Part 2: Analysis of Results.

    Science.gov (United States)

    Dondi, Maurizio; Torres, Leonel; Marengo, Mario; Massardo, Teresa; Mishani, Eyal; Van Zyl Ellmann, Annare; Solanki, Kishor; Bischof Delaloye, Angelika; Lobato, Enrique Estrada; Miller, Rodolfo Nunez; Ordonez, Felix Barajas; Paez, Diana; Pascual, Thomas

    2017-11-01

    The International Atomic Energy Agency has developed a program, named Quality Management Audits in Nuclear Medicine (QUANUM), to help its Member States to check the status of their nuclear medicine practices and their adherence to international reference standards, covering all aspects of nuclear medicine, including quality assurance/quality control of instrumentation, radiopharmacy (further subdivided into levels 1, 2, and 3, according to complexity of work), radiation safety, clinical applications, as well as managerial aspects. The QUANUM program is based on both internal and external audits and, with specifically developed Excel spreadsheets, it helps assess the level of conformance (LoC) to those previously defined quality standards. According to their level of implementation, the level of conformance to requested standards; 0 (absent) up to 4 (full conformance). Items scored 0, 1, and 2 are considered non-conformance; items scored 3 and 4 are considered conformance. To assess results of the audit missions performed worldwide over the last 8 years, a retrospective analysis has been run on reports from a total of 42 audit missions in 39 centers, three of which had been re-audited. The analysis of all audit reports has shown an overall LoC of 73.9 ± 8.3% (mean ± standard deviation), ranging between 56.6% and 87.9%. The highest LoC has been found in the area of clinical services (83.7% for imaging and 87.9% for therapy), whereas the lowest levels have been found for Radiopharmacy Level 2 (56.6%); Computer Systems and Data Handling (66.6%); and Evaluation of the Quality Management System (67.6%). Prioritization of non-conformances produced a total of 1687 recommendations in the final audit report. Depending on the impact on safety and daily clinical activities, they were further classified as critical (requiring immediate action; n = 276; 16% of the total); major (requiring action in relatively short time, typically from 3 to 6 months; n = 604

  20. Toward a common nuclear safety culture. From knowledge creation to competence building in Euratom programs

    Energy Technology Data Exchange (ETDEWEB)

    Goethem, Georges van [EC DG Research J2 / Euratom (Fission), Brussels (Belgium). Innovation in Nuclear Systems, and Education and Training

    2010-11-15

    One of the main goals of the Euratom research and training programs is to contribute to the sustainability of nuclear energy by providing resources, in particular, for research and innovation in Generations II, IIII and IV (knowledge creation). Euratom training programs contribute most notably to competence building while facilitating the mutual recognition of experts and thereby continuously improving the nuclear safety culture. The Sustainable Nuclear Energy Technology Platform (SNE-TP), composed of all stakeholders of nuclear fission and radiation protection (over 75 organizations), is a driving force therein. The emphasis in this paper is on nuclear competence building under the current 7-th Euratom Framework Programme (2007 - 2013). The employers (in particular, the nuclear industry and the technical safety organisations) are naturally involved in this process. According to the IAEA definition, competence means the ability to apply knowledge, skills and attitudes so as to perform a job in an effective and efficient manner and to an established standard (S.S.S. No. RS-G-1.4 / 2001). Knowledge is usually created in higher education institutions (e.g., universities) and in (private and public) research organizations. Skills and attitudes are usually the result of specific training and on-the-job experience throughout professional life. Euratom training activities are traditionally addressed to scientists and experts with higher education. Special attention is devoted to the continuous improvement of their competencies through borderless mobility and lifelong learning in synergy with the main stakeholders. The Euratom training strategy is based on 3 objectives: 1. Analysis of the needs of society and industry with regard to a common nuclear safety culture. This issue raises important questions, for examples: What should be added to existing training schemes? How could Continuous Professional Development (CPD) be improved? Is mobility and mutual recognition of

  1. Preclinical evaluation of nuclear morphometry and tissue topology for breast carcinoma detection and margin assessment.

    Science.gov (United States)

    Nyirenda, Ndeke; Farkas, Daniel L; Ramanujan, V Krishnan

    2011-04-01

    Prevention and early detection of breast cancer are the major prophylactic measures taken to reduce the breast cancer related mortality and morbidity. Clinical management of breast cancer largely relies on the efficacy of the breast-conserving surgeries and the subsequent radiation therapy. A key problem that limits the success of these surgeries is the lack of accurate, real-time knowledge about the positive tumor margins in the surgically excised tumors in the operating room. This leads to tumor recurrence and, hence, the need for repeated surgeries. Current intraoperative techniques such as frozen section pathology or touch imprint cytology severely suffer from poor sampling and non-optimal detection sensitivity. Even though histopathology analysis can provide information on positive tumor margins post-operatively (~2-3 days), this information is of no immediate utility in the operating rooms. In this article, we propose a novel image analysis method for tumor margin assessment based on nuclear morphometry and tissue topology and demonstrate its high sensitivity/specificity in preclinical animal model of breast carcinoma. The method relies on imaging nuclear-specific fluorescence in the excised surgical specimen and on extracting nuclear morphometric parameters (size, number, and area fraction) from the spatial distribution of the observed fluorescence in the tissue. We also report the utility of tissue topology in tumor margin assessment by measuring the fractal dimension in the same set of images. By a systematic analysis of multiple breast tissues specimens, we show here that the proposed method is not only accurate (~97% sensitivity and 96% specificity) in thin sections, but also in three-dimensional (3D) thick tissues that mimic the realistic lumpectomy specimens. Our data clearly precludes the utility of nuclear size as a reliable diagnostic criterion for tumor margin assessment. On the other hand, nuclear area fraction addresses this issue very

  2. The Program Sustainability Assessment Tool: a new instrument for public health programs.

    Science.gov (United States)

    Luke, Douglas A; Calhoun, Annaliese; Robichaux, Christopher B; Elliott, Michael B; Moreland-Russell, Sarah

    2014-01-23

    Public health programs can deliver benefits only if they are able to sustain programs, policies, and activities over time. Although numerous sustainability frameworks and models have been developed, there are almost no assessment tools that have demonstrated reliability or validity or have been widely disseminated. We present the Program Sustainability Assessment Tool (PSAT), a new and reliable instrument for assessing the capacity for program sustainability of various public health and other programs. A measurement development study was conducted to assess the reliability of the PSAT. Program managers and staff (n = 592) representing 252 public health programs used the PSAT to rate the sustainability of their program. State and community-level programs participated, representing 4 types of chronic disease programs: tobacco control, diabetes, obesity prevention, and oral health. The final version of the PSAT contains 40 items, spread across 8 sustainability domains, with 5 items per domain. Confirmatory factor analysis shows good fit of the data with the 8 sustainability domains. The subscales have excellent internal consistency; the average Cronbach's α is 0.88, ranging from 0.79 to 0.92. Preliminary validation analyses suggest that PSAT scores are related to important program and organizational characteristics. The PSAT is a new and reliable assessment instrument that can be used to measure a public health program's capacity for sustainability. The tool is designed to be used by researchers, evaluators, program managers, and staff for large and small public health programs.

  3. Assessment of Learning and Program Evaluation in Health Professions Education Programs

    Science.gov (United States)

    Moore, Donald E., Jr.

    2018-01-01

    This chapter proposes approaches for assessing learners and evaluating courses and curriculum that could be used by directors of health professions education (HPE) programs to determine the effectiveness and impact of their programs.

  4. Meta-Review: Systematic Assessment of Program Review

    Science.gov (United States)

    Harlan, Brian

    2012-01-01

    Over 20 years ago, Robert J. Barak and Barbara E. Breier suggested incorporating a regular assessment of the entire program review system into the review schedule in order to ensure that the system itself is as efficient and effective as the programs under review. Barak and Breier's seminal book on the goals and processes of program review has…

  5. Intergenerational Programming in Extension: Needs Assessment as Planning Tool.

    Science.gov (United States)

    Kaplan, Matthew; Liu, Shih-Tsen; Radhakrishna, Rama B.

    2003-01-01

    A needs assessment of 161 Extension educators in family and consumer science and 4-H/youth development received 28 responses indicating preferences regarding intergenerational program content and delivery format. Results were used to develop curriculum and program delivery strategies and begin planning for a statewide intergenerational program.…

  6. Adaptive Assessment of Student's Knowledge in Programming Courses

    Science.gov (United States)

    Chatzopoulou, D. I.; Economides, A. A.

    2010-01-01

    This paper presents Programming Adaptive Testing (PAT), a Web-based adaptive testing system for assessing students' programming knowledge. PAT was used in two high school programming classes by 73 students. The question bank of PAT is composed of 443 questions. A question is classified in one out of three difficulty levels. In PAT, the levels of…

  7. Douglas United Nuclear, Inc., sponsored research and development programs, FY-1967

    Energy Technology Data Exchange (ETDEWEB)

    Reid, R.W.; Stringer, J.T.

    1966-07-12

    Douglas United Nuclear, Inc., has allocated to the Pacific Northwest Laboratory $542,000 of 02 Research and Development funds and $455,000 of Process Technology funds for FY-1967. Of these, $392,000 of 02 Research and Development funds and $420,000 of Process Technology funds are the responsibility of the Research and Engineering Section. The balance in each case is the responsibility of the Production Fuels Section. Representatives of these Sections have met with Pacific Northwest Laboratory personnel to develop programs to be undertaken in FY-1967. This document briefly summarizes the results of the discussions and delineates the work to be accomplished.

  8. Materials technology for an advanced space power nuclear reactor concept: Program summary

    Science.gov (United States)

    Gluyas, R. E.; Watson, G. K.

    1975-01-01

    The results of a materials technology program for a long-life (50,000 hr), high-temperature (950 C coolant outlet), lithium-cooled, nuclear space power reactor concept are reviewed and discussed. Fabrication methods and compatibility and property data were developed for candidate materials for fuel pins and, to a lesser extent, for potential control systems, reflectors, reactor vessel and piping, and other reactor structural materials. The effects of selected materials variables on fuel pin irradiation performance were determined. The most promising materials for fuel pins were found to be 85 percent dense uranium mononitride (UN) fuel clad with tungsten-lined T-111 (Ta-8W-2Hf).

  9. Fatality Assessment and Control Evaluation (FACE) Program

    Data.gov (United States)

    U.S. Department of Health & Human Services — Each day, between 12 to 13 U.S. workers die as a result of a traumatic injury on the job. Investigations conducted through the FACE program allow the identification...

  10. Outcomes Assessment in Accredited Health Information Management Programs

    Science.gov (United States)

    Bennett, Dorine

    2010-01-01

    The purpose of this study was to determine the use and perceived usefulness of outcomes assessment methods in health information management programs. Additional characteristics of the outcomes assessment practices were recognized. The findings were evaluated for significant differences in results based on age of the program, type of institution,…

  11. Enhancing Assessments of Mental Health Programs and Program Planning

    Science.gov (United States)

    2012-06-01

    300 studies are in progress. Some are close to completion.  RAND found major barriers to efficiency in DOD PH programs:  Proliferation: RAND... efficiency of the DC System:  Establish data systems to measure the probabilities at each major branch of the military and clinical flow charts shown in...significantly effective  One study showed acupuncture very effective 64 Only significant 1st and 2nd level categories are shown. – Watts, Schnurr et al

  12. Assessment of military population-based psychological resilience programs.

    Science.gov (United States)

    Morgan, Brenda J; Bibb, Sandra C Garmon

    2011-09-01

    Active duty service members' (ADSMs) seemingly poor adaptability to traumatic stressors is a risk to force health. Enhancing the psychological resilience of ADSMs has become a key focus of Department of Defense (DoD) leaders and the numbers of military programs for enhancing psychological resilience have increased. The purpose of this article is to describe the results of an assessment conducted to determine comprehensiveness of current psychological resilience building programs that target ADSMs. A modified six-step, population-based needs assessment was used to evaluate resilience programs designed to meet the psychological needs of the ADSM population. The assessment results revealed a gap in published literature regarding program outcomes. DoD leaders may benefit from targeted predictive research that assesses program effectiveness outcomes. The necessity of including preventive, evidence-based interventions in new programs, such as positive emotion interventions shown to enhance psychological resilience in civilian samples, is also recommended.

  13. Defense Acquisitions: Assessments of Selected Weapon Programs

    Science.gov (United States)

    2017-03-01

    current Interim Polar System and serve as a polar adjunct to the Advanced EHF (AEHF) system. EPS consists of three segments : two EHF payloads hosted on...area on GAO’s high- risk list. DOD and Congress have taken steps to improve the acquisition of weapon systems. Still some programs continue to...DOD’s Selected Acquisition Reports from 2010, 2014, and 2015. GAO also collected program office data through two questionnaires on technology

  14. Defense Acquisitions: Assessments of Selected Weapon Programs

    Science.gov (United States)

    2008-03-01

    Missile Defense ICAP Improved Capability IMU inertial measurement units ISR intelligence, surveillance, and reconnaissance JNN-N Joint Network Node...Aeronautics and Space Administration NLOS-C Non-Line-of-Sight Cannon NOAA National Oceanic and Atmospheric Administration NSS AP National Security Space... turbulence . Sixty-three percent of the programs we received data from had requirement changes after system development began. These programs

  15. An updated dose assessment for a U.S. Nuclear Test Site - Bikini Atoll

    Energy Technology Data Exchange (ETDEWEB)

    Robison, W.L.; Bogen, K.T.; Conrado, C.L.

    1995-10-01

    On March 1, 1954, a nuclear weapon test, code-named BRAVO, conducted at Bikini Atoll in the northern Marshall Islands contaminated the major residence island. There has been a continuing effort since 1977 to refine dose assessments for resettlement options at Bikini Atoll. Here we provide a radiological dose assessment for the main residence island, Bikini, using extensive radionuclide concentration data derived from analysis of food crops, ground water, cistern water, fish and other marine species, animals, air, and soil collected at Bikini Island as part of our continuing research and monitoring program that began in 1975. The unique composition of coral soil greatly alters the relative contribution of cesium-137 ({sup 137}Cs) and strontium-90 ({sup 90}Sr) to the total estimated dose relative to expectations based on North American and European soils. Without counter measures, cesium-137 produces 96% of the estimated dose for returning residents, mostly through uptake from the soil to terrestrial food crops but also from external gamma exposure. The doses are calculated assuming a resettlement date of 1999. The estimated maximum annual effective dose for current island conditions is 4.0 mSv when imported foods, which are now an established part of the diet, are available. The corresponding 30-, 50-, and 70-y integral effective doses are 9.1 cSv, 13 cSv, and 15 cSv, respectively. A corresponding uncertainty analysis showed that after about 5 y of residence, the 95% confidence limits on population-average dose would be {plus_minus}35% of its expected value. We have evaluated various countermeasures to reduce {sup 137}Cs in food crops. Treatment with potassium reduces the uptake of {sup 137}Cs into food crops, and therefore the ingestion dose, to about 5% of pretreatment levels and has essentially no negative environmental consequences.

  16. Summary of seismic assessment of underground and buried nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    1977-09-01

    A preliminary assessment is presented of the earthquake engineering implications of siting nuclear power facilities underground, as requested by The Aerospace Corporation. The study is a review of the major aspects of the seismic design problem for underground structures. Seismic design criteria suitable as input to conceptual design and cost studies are presented.

  17. Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-08-01

    OAK B188 Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report. The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-formed approach for the design and regulation of nuclear power plants. This approach will include the development and/or confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRS) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go further by focusing on the design of new plants.

  18. Exploring Stochastic Sampling in Nuclear Data Uncertainties Assessment for Reactor Physics Applications and Validation Studies

    Directory of Open Access Journals (Sweden)

    Alexander Vasiliev

    2016-12-01

    Full Text Available The quantification of uncertainties of various calculation results, caused by the uncertainties associated with the input nuclear data, is a common task in nuclear reactor physics applications. Modern computation resources and improved knowledge on nuclear data allow nowadays to significantly advance the capabilities for practical investigations. Stochastic sampling is the method which has received recently a high momentum for its use and exploration in the domain of reactor design and safety analysis. An application of a stochastic sampling based tool towards nuclear reactor dosimetry studies is considered in the given paper with certain exemplary test evaluations. The stochastic sampling not only allows the input nuclear data uncertainties propagation through the calculations, but also an associated correlation analysis performance with no additional computation costs and for any parameters of interest can be done. Thus, an example of assessment of the Pearson correlation coefficients for several models, used in practical validation studies, is shown here. As a next step, the analysis of the obtained information is proposed for discussion, with focus on the systems similarities assessment. The benefits of the employed method and tools with respect to practical reactor dosimetry studies are consequently outlined.

  19. Climate considerations in long-term safety assessments for nuclear waste repositories.

    Science.gov (United States)

    Näslund, Jens-Ove; Brandefelt, Jenny; Liljedahl, Lillemor Claesson

    2013-05-01

    For a deep geological repository for spent nuclear fuel planned in Sweden, the safety assessment covers up to 1 million years. Climate scenarios range from high-end global warming for the coming 100 000 years, through deep permafrost, to large ice sheets during glacial conditions. In contrast, in an existing repository for short-lived waste the activity decays to low levels within a few tens of thousands of years. The shorter assessment period, 100 000 years, requires more focus on climate development over the coming tens of thousands of years, including the earliest possibility for permafrost growth and freezing of the engineered system. The handling of climate and climate change in safety assessments must be tailor-made for each repository concept and waste type. However, due to the uncertain future climate development on these vast time scales, all safety assessments for nuclear waste repositories require a range of possible climate scenarios.

  20. Climate Considerations in Long-Term Safety Assessments for Nuclear Waste Repositories

    Energy Technology Data Exchange (ETDEWEB)

    Naeslund, Jens-Ove; Brandefelt, Jenny; Claesson Liljedahl, Lillemor [Svensk Kaernbraenslehantering AB, Stockholm (Sweden)], E-mail: jens-ove.naslund@skb.se

    2013-05-15

    For a deep geological repository for spent nuclear fuel planned in Sweden, the safety assessment covers up to 1 million years. Climate scenarios range from high-end global warming for the coming 100 000 years, through deep permafrost, to large ice sheets during glacial conditions. In contrast, in an existing repository for short-lived waste the activity decays to low levels within a few tens of thousands of years. The shorter assessment period, 100 000 years, requires more focus on climate development over the coming tens of thousands of years, including the earliest possibility for permafrost growth and freezing of the engineered system. The handling of climate and climate change in safety assessments must be tailor-made for each repository concept and waste type. However, due to the uncertain future climate development on these vast time scales, all safety assessments for nuclear waste repositories require a range of possible climate scenarios.

  1. Science Plan for the Nuclear Electric Propulsion Space Test Program (NEPSTP)

    Science.gov (United States)

    Mauk, B. H.; Bythrow, P. F.; Gatsonis, N. A.; McNutt, R. L., Jr.

    1993-06-01

    NEPSTP is an unclassified, international space mission sponsored by the Ballistic Missile Defense Organization (BMDO) as a testbed for the development of Nuclear Electric Propulsion (NEP) technologies. The mission will utilize the Russian manufactured Topaz II thermionic nuclear reactor and a variety of advanced experimental electric thrusters from international sources. The NEPSTP Spacecraft will be inserted into a nuclear safe circular orbit, and the electric thrusters will be utilized to drive the spacecraft in a spiral pattern to high earth orbit. This paper gives an overview of the Science Plan for the NEPSTP mission. The science activities discussed incude: (1) Evaluation of the performance of the Topaz II reactor in orbit; (2) Evaluation of the performances and degradations of the electric thrusters; (3) Evaluation of the so-called 'induced environment' around the NEPSTP Spacecraft; and, (4) Science of opportunity consistent with (1), (2), and (3). With regard to the third goal, the environment induced in the vicinity of an NEP driven spacecraft is unique, and its severity may degrade the performances of advanced sensors and some spacecraft subsystems. Thus, NEPSTP has an aggressive program to diagnose induced environment effects and develop predictive understanding of that environment for future systems. The Science Plan includes: (A) The utilization on the spacecraft of suite of science instruments, a science boom, and other spacecraft liens; (B) A data analysis and evaluation plan; (C) Various operational experiments; and, (D) The development of theoretical and empirical models.

  2. Nuclear medicine program progress report for quarter ending December 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Beets, A.L.; Boll, R.; Luo, H.; McPherson, D.W.; Mirzadeh, S.

    1997-03-20

    In this report the authors describe the use of an effective method for concentration of the rhenium-188 bolus and the results of the first Phase 1 clinical studies for bone pain palliation with rhenium-188 obtained from the tungsten-188/rhenium-188 generator. Initial studies with therapeutic levels of Re-188-HEDP at the Clinic for Nuclear Medicine at the University of Bonn, Germany, have demonstrated the expected good metastatic uptake of Re-188-HEDP in four patients who presented with skeletal metastases from disseminated prostatic cancer with good pain palliation and minimal marrow suppression. In addition, skeletal metastatic targeting of tracer doses of Re-188(V)-DMSA has been evaluated in several patients with metastases from prostatic cancer at the Department of Nuclear Medicine at the Canterbury and Kent Hospital in Canterbury, England. In this report the authors also describe further studies with the E-(R,R)-IQNP ligand developed in the ORNL Nuclear Medicine Program as a potential imaging agent for detection of changes which may occur in the cerebral muscarinic-cholinergic receptors (mAChR) in Alzheimer`s and other diseases.

  3. Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

    Energy Technology Data Exchange (ETDEWEB)

    Brandstetter, A.; Harwell, M.A.; Howes, B.W.; Benson, G.L.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.; Schilling, A.H.

    1979-07-01

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) 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. Progress on the following tasks is reported: release scenario analysis, waste form release rate analysis, release consequence analysis, sorption-desorption analysis, and societal acceptance analysis. (DC)

  4. What Campuses Assess When They Assess Their Learning Community Programs: Selected Findings from a National Survey of Learning Community Programs

    Science.gov (United States)

    Lardner, Emily

    2014-01-01

    In spring 2013, the Washington Center administered a national survey to find what campuses assessed when they assessed their learning community programs, how they assessed those outcomes, and what they did with the results. Sixty-six campuses responded to the survey. Most campuses assess at least one measure of student success (pass rates, course…

  5. Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John Russell; Danneels, Jeffrey John

    2009-03-01

    Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21

  6. Assessment of the level of knowledge of Physicians in Bushehr Province about preparedness and response for Nuclear Emergency

    Directory of Open Access Journals (Sweden)

    Eshagh Abbasi

    2005-02-01

    Full Text Available Responses to recent incidents involving radiation indicate that most general practitioners are uncertain about the health consequences of exposure to ionizing radiation and the medical management of exposed patients. Acute radiation syndrome is an acute illness caused by irradiation of the entire body by a high dose of penetrating radiation in a very short period of time. In order to assess the level of knowledge of physicians in Bushehr province about preparedness and response for nuclear emergency, we used a questionnaire based on IAEA-WHO protocol. A total of 233 doctors (47 of specialist and 186 of general practitioners participated in a cross-sectional study. The mean of score for doctors was 3.99 (from 13 3.7 score for general practitioners and 4.28 scores for specialists. Overall, the doctors did not gain the acceptable scores in subjects like physics of radiation, diagnosis and management of acute radiation syndrome, triage and management of nuclear accidents. In conclusion, the level of doctors’ knowledge in Bushehr province about preparedness and response to nuclear or radiological emergency is deficient. Therefore, medical education and postgraduate training programs for doctors should be designed.

  7. Korean round-robin result for new international program to assess the reliability of emerging nondestructive techniques

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyung Cho; Kim, Jin Gyum; Kang, Sung Sik; Jhung, Myung Jo [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2017-04-15

    The Korea Institute of Nuclear Safety, as a representative organization of Korea, in February 2012 participated in an international Program to Assess the Reliability of Emerging Nondestructive Techniques initiated by the U.S. Nuclear Regulatory Commission. The goal of the Program to Assess the Reliability of Emerging Nondestructive Techniques is to investigate the performance of emerging and prospective novel nondestructive techniques to find flaws in nickel-alloy welds and base materials. In this article, Korean round-robin test results were evaluated with respect to the test blocks and various nondestructive examination techniques. The test blocks were prepared to simulate large-bore dissimilar metal welds, small-bore dissimilar metal welds, and bottom-mounted instrumentation penetration welds in nuclear power plants. Also, lessons learned from the Korean round-robin test were summarized and discussed.

  8. Korean Round-Robin Tests Result for New International Program to Assess the Reliability of Emerging Nondestructive Techniques

    Directory of Open Access Journals (Sweden)

    Kyung Cho Kim

    2017-04-01

    Full Text Available The Korea Institute of Nuclear Safety, as a representative organization of Korea, in February 2012 participated in an international Program to Assess the Reliability of Emerging Nondestructive Techniques initiated by the U.S. Nuclear Regulatory Commission. The goal of the Program to Assess the Reliability of Emerging Nondestructive Techniques is to investigate the performance of emerging and prospective novel nondestructive techniques to find flaws in nickel-alloy welds and base materials. In this article, Korean round-robin test results were evaluated with respect to the test blocks and various nondestructive examination techniques. The test blocks were prepared to simulate large-bore dissimilar metal welds, small-bore dissimilar metal welds, and bottom-mounted instrumentation penetration welds in nuclear power plants. Also, lessons learned from the Korean round-robin test were summarized and discussed.

  9. Using the Program Sustainability Assessment Tool to Assess and Plan for Sustainability

    Science.gov (United States)

    Mainor, Avia; Moreland-Russell, Sarah; Maier, Ryan C.; Brossart, Laura; Luke, Douglas A.

    2014-01-01

    Implementing and growing a public health program that benefits society takes considerable time and effort. To ensure that positive outcomes are maintained over time, program managers and stakeholders should plan and implement activities to build sustainability capacity within their programs. We describe a 3-part sustainability planning process that programs can follow to build their sustainability capacity. First, program staff and stakeholders take the Program Sustainability Assessment Tool to measure their program’s sustainability across 8 domains. Next, managers and stakeholders use results from the assessment to inform and prioritize sustainability action planning. Lastly, staff members implement the plan and keep track of progress toward their sustainability goals. Through this process, staff can more holistically address the internal and external challenges and pressures associated with sustaining a program. We include a case example of a chronic disease program that completed the Program Sustainability Assessment Tool and engaged in program sustainability planning. PMID:24456644

  10. Annual radiological environmental monitoring report: Watts Bar Nuclear Plant, 1992. Operations Services/Technical Programs

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

    This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. Exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment as a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment.

  11. Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

    2007-09-01

    DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 950°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, TRISO-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Some of the general and administrative aspects of the R&D Plan include: • Expand American Society of Mechanical Engineers (ASME) Codes and American Society for Testing and Materials (ASTM) Standards in support of the NGNP Materials R&D Program. • Define and develop inspection needs and the procedures for those inspections. • Support selected university materials related R&D activities that would be of direct benefit to the NGNP Project. • Support international materials related collaboration activities through the DOE sponsored Generation IV International Forum (GIF) Materials and Components (M&C) Project Management Board (PMB). • Support document review activities through the Materials Review Committee (MRC) or other suitable forum.

  12. North Korea's nuclear weapons program:verification priorities and new challenges.

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Duk-ho (Korean Consulate General in New York)

    2003-12-01

    A comprehensive settlement of the North Korean nuclear issue may involve military, economic, political, and diplomatic components, many of which will require verification to ensure reciprocal implementation. This paper sets out potential verification methodologies that might address a wide range of objectives. The inspection requirements set by the International Atomic Energy Agency form the foundation, first as defined at the time of the Agreed Framework in 1994, and now as modified by the events since revelation of the North Korean uranium enrichment program in October 2002. In addition, refreezing the reprocessing facility and 5 MWe reactor, taking possession of possible weapons components and destroying weaponization capabilities add many new verification tasks. The paper also considers several measures for the short-term freezing of the North's nuclear weapon program during the process of negotiations, should that process be protracted. New inspection technologies and monitoring tools are applicable to North Korean facilities and may offer improved approaches over those envisioned just a few years ago. These are noted, and potential bilateral and regional verification regimes are examined.

  13. The role of PRA in the safety assessment of VVER Nuclear Power Plants in Ukraine.

    Energy Technology Data Exchange (ETDEWEB)

    Kot, C.

    1999-05-10

    Ukraine operates thirteen (13) Soviet-designed pressurized water reactors, VVERS. All Ukrainian plants are currently operating with annually renewable permits until they update their safety analysis reports (SARs), in accordance with new SAR content requirements issued in September 1995, by the Nuclear Regulatory Authority and the Government Nuclear Power Coordinating Committee of Ukraine. The requirements are in three major areas: design basis accident (DBA) analysis, probabilistic risk assessment (PRA), and beyond design-basis accident (BDBA) analysis. The last two requirements, on PRA and BDBA, are new, and the DBA requirements are an expanded version of the older SAR requirements. The US Department of Energy (USDOE), as part of its Soviet-Designed Reactor Safety activities, is providing assistance and technology transfer to Ukraine to support their nuclear power plants (NPPs) in developing a Western-type technical basis for the new SARs. USDOE sponsored In-Depth Safety Assessments (ISAs) are in progress at three pilot nuclear reactor units in Ukraine, South Ukraine Unit 1, Zaporizhzhya Unit 5, and Rivne Unit 1, and a follow-on study has been initiated at Khmenytskyy Unit 1. The ISA projects encompass most areas of plant safety evaluation, but the initial emphasis is on performing a detailed, plant-specific Level 1 Internal Events PRA. This allows the early definition of the plant risk profile, the identification of risk significant accident sequences and plant vulnerabilities and provides guidance for the remainder of the safety assessments.

  14. Is our residency program successful? Structuring an outcomes assessment system as a component of program evaluation.

    Science.gov (United States)

    Torbeck, Laura; Canal, David F; Choi, Jennifer

    2014-01-01

    In an attempt to better define the success of our residency program with regard to resident development, we committed to develop an ongoing assessment of residency performance and devised an outcomes assessment system. We describe the process and structure that we used to construct an outcomes assessment system. We discuss the process we used to discern whether or not our program is successful as well as offer tips on what data to collect and track should other residency programs decide to devise a similar outcomes assessment database. Taking time to "step back" to take inventory of a residency program and ensure year over year and at the end of training residents have developed and matured as planned is an educationally sound practice. Structuring an outcomes assessment system like the one that we discuss here can aid program directors with this important task. Copyright © 2014 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

  15. NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-04-01

    At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories.

  16. Migrant Education Program. Comprehensive Needs Assessment

    Science.gov (United States)

    Minnesota Department of Education, 2013

    2013-01-01

    The primary purpose of the Minnesota Migrant Education Program (MEP) is to help migrant children and youth overcome challenges of mobility, frequent absences, late enrollment into school, social isolation, and other difficulties associated with a migratory life, in order that they might succeed in school. Furthermore, the Minnesota MEP must give…

  17. Secondary Vocational Horticulture Programs--An Assessment.

    Science.gov (United States)

    Burnett, Michael F.; Smith, Charles W.

    1983-01-01

    The objectives of the study were to determine characteristics of secondary horticulture teachers, the structure of horticulture departments, funding sources, nature and scope of facilities, types of supervised occupational experience programs in which horticulture students participated, and curriculum characteristics of vocational horticulture…

  18. Study of virtual reality application in training programs on nuclear technology; Estudo da aplicacao de realidade virtual em programas de treinamento sobre tecnologia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Pastura, Valeria da Fonseca e Silva

    2016-07-01

    The activities developed in the units which organize the National Nuclear Energy Commission (CNEN) are present in various sectors of the Brazilian society, being them in medicine, industry, electricity generation, mining, and among the others. Based on the assumption that the employees are CNEN's mayor differential and the training programs play an important role in the process of organizational development, because they align the professionals with the strategies of the institution properly. Focusing on these matters, this master's thesis aimed to evaluate the training programs which are applied by CNEN, in order to propose and evaluate the use of the Virtual Reality (VR) expertise as a new method to be applied in the training programs. To accomplish this purpose, we performed two methodological approaches through questionnaires. And from the analysis of the results obtained, we could realize that there was no efficient training program which is systematically applied by CNEN, and the use of the RV technique improves the training programs in the understanding of themes whose assimilation is challengeable, such as those related to nuclear power. In this sense, for a better functional performance, the training programs adopted by CNEN must be structured so as to enable the development of each server's skills as well as abilities and, it is actually hoped that the virtual reality tools could be inserted in these programs to pursue only this purpose. (author)

  19. Web-Based Programs Assess Cognitive Fitness

    Science.gov (United States)

    2009-01-01

    The National Space Biomedical Research Institute, based in Houston and funded by NASA, began funding research for Harvard University researchers to design Palm software to help astronauts monitor and assess their cognitive functioning. The MiniCog Rapid Assessment Battery (MRAB) was licensed by the Criteria Corporation in Los Angeles and adapted for Web-based employment testing. The test battery assesses nine different cognitive functions and can gauge the effect of stress-related deficits, such as fatigue, on various tasks. The MRAB can be used not only for pre-employment testing but also for repeat administrations to measure day-to-day job readiness in professions where alertness is critical.

  20. Assessment program for Kentucky traffic records.

    Science.gov (United States)

    2015-02-01

    During 2013, the Kentucky Transportation Center identified 117 potential performance metrics for the ten databases in : the Kentucky Traffic Records System. This report summarizes the findings of three main tasks completed in 2014: (1) : assessment o...

  1. On the future of civilian plutonium: An assessment of technological impediments to nuclear terrorism and proliferation

    Science.gov (United States)

    Avedon, Roger Edmond

    . The opportunity cost of such events is prohibitively difficult to assess. Instead, recent nonproliferation efforts and long term funding of organizations with nonproliferation objectives suggest a willingness-to-pay to avoid breaches in nuclear security. The cancellation of the Integral Fast Reactor in 1994 is analyzed using the methodology developed in the dissertation.

  2. Assessment method for analyzing and developing human resource management practices in the nuclear power industry

    Energy Technology Data Exchange (ETDEWEB)

    Maeki, Eerikki [Aalto Univ. (Finland). Dept. of Industrial Engineering and Management; Pahkin, Krista; Lindstroem, S.; Kurki, Anna-Leena [Finnish Institue of Occupational Health, Helsinki (Finland). Centre of Expertise for the Development of Work and Organizations

    2015-04-15

    Implementation of HRM practices is often devolved from the HRM unit to front line managers and supervisors. However, the implementation of these practices by line managers and supervisors may vary significantly. They may, for example, be unaware of how to implement HRM practices or sceptical towards the effectiveness of the intended practices. Based on the literature, interviews and workshops in the nuclear power industry, a self-assessment method of HRM practices for intra-organizational use was developed. The assessment method was piloted in four nuclear power organizations. The assessment method seems to be a good tool for generating fruitful discussion on HRM practices, finding areas of HRM practices that need to be developed, and triggering peer-to-peer knowledge sharing and learning on HRM practices.

  3. Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Egidijus Babilas

    2015-01-01

    Full Text Available The decommissioning of nuclear facilities requires adequate planning and demonstration that dismantling and decontamination activities can be conducted safely. Existing safety standards require that an appropriate safety assessment be performed to support the decommissioning plan for each facility (International Atomic Energy Agency, 2006. This paper presents safety assessment approach used in Lithuania during the development of the first dismantling and decontamination project for Ignalina NPP. The paper will mainly focus on the identification and assessment of the hazards raised due to dismantling and decontamination activities at Ignalina Nuclear Power Plant and on the assessment of the nonradiological and radiological consequences of the indicated most dangerous initiating event. The drop of heavy item was indicated as one of most dangerous initiating events for the discussed Ignalina Nuclear Power Plant dismantling and decontamination project. For the analysis of the nonradiological impact the finite element model for the load drop force calculation was developed. The radiological impact was evaluated in those accident cases which would lead to the worst radiological consequences. The assessments results show that structural integrity of the building and supporting columns of building structures will be maintained and radiological consequences are lower than the annual regulatory operator dose limit.

  4. EFFICIENT QUALITY ASSURANCE PROGRAMS IN RADIOLOGY AND NUCLEAR MEDICINE IN ÖSTERGÖTLAND, SWEDEN

    OpenAIRE

    Sandborg, Michael; Nilsson Althen, Jonas; Gustafsson, Agneta

    2010-01-01

    Owners of imaging modalities using ionising radiation should have a documented quality assurance (QA) program, as well as methods to justify new radiological procedures to ensure safe operation and adequate clinical image quality. This includes having a system for correcting divergences, written imaging protocols, assessment of patient and staff absorbed doses and a documented education and training program. In this work, how some aspects on QA have been implemented in the County of Östergötl...

  5. Student Learning Outcomes Assessment in College Foreign Language Programs

    Science.gov (United States)

    Norris, John M., Ed.; Davis, John McE., Ed.

    2015-01-01

    Changes in accreditation policies and institutional practices have led to the emergence of student learning outcomes assessment as an important, increasingly common expectation in U.S. college foreign language programs. This volume investigates contemporary outcomes assessment activity, with a primary focus on useful assessment, that is,…

  6. A Nordic approach to impact assessment of accidents with nuclear-propelled vessels

    Energy Technology Data Exchange (ETDEWEB)

    Reistad, O. [Institute for Energy Technology, Kjeller (Norway); Hustveit, S. [Norwegian Radiation Protection Authority, Oesteraes (Norway); Palsson, S.E. [Icelandic Radiation Safety Authority, Reykjavik (Iceland); Hoe, S. [Danish Emergency Management Agency, Birkeroed (Denmark); Lahtinen, J. [STUK, Helsinki (Finland)

    2012-11-15

    The MareNuc project has identified the parameters in a graded approach to impact assessment for marine nuclear reactors. The graded approach is founded on the following elements: 1) More detailed understanding of previous accidents in nuclear-propelled vessels (initiating events, accident developments, release fractions), including release mechanisms (radionuclide retention in vessel construction); 2) Bench-marking of release scenarios using modelling tools applied in the Nordic countries, in addition to demonstration of generally accessible and free software developed by the IAEA; 3) Other systematic approaches to safety assessments of vessel port calls, and to the design and maintenance of emergency preparedness systems; More specifically, increased emphasis compared to earlier analysis after the Kursk accident is given to the engineered vessel barriers. Relevant standards from impact assessments for commercial nuclear power plants have been identified, such as from the NUREG series. The Nordic approaches to safety evaluation, impact assessments and emergency preparedness organisation was also reported as part of the project. The Canadian approach for international port calls was carefully reported and assessed as part of the project, and commended for its broad and comprehensive approach to reactor and vessel design for the nationalities involved, to the design and maintenance of emergency preparedness systems, and the well-structured and broad cooperation between civilian and military institutions. This approach goes beyond the current approach in the Nordic countries, also in the case of Norway, which experience regular port calls from allied nuclear navies. The overall result is a broader understanding in the Nordic countries for the importance of the various parameters for impact assessment of releases from marine reactors, and to the design and maintenance of an emergency preparedness organisation without detailed knowledge of the installation in question

  7. Assessment of Accelerated Acquisition of Defense Programs

    Science.gov (United States)

    2016-09-01

    117A Stealth Attack Aircraft Crash /rapid/time constrained/spiral Mine-Resistant/Ambush-Protected Vehicle (MRAP) Rapid/time constrained Stryker...contractor. The Air Force delivered the aircraft directly from the factory to the front lines with no developmental or operational testing . Prior...availability: 1. Time-constrained acquisition 2. “ Crash ” program 3. Rapid acquisition 4. Early fielding experiments 5. Spiral/evolutionary

  8. Defense Acquisitions. Assessments of Selected Weapon Programs

    Science.gov (United States)

    2007-03-01

    System (MRUUVS) 113 Mobile User Objective System (MUOS) 115 National Polar- orbiting Operational Environmental Satellite System (NPOESS) 117 P-8A Multi...production decisions (5/05-8/08) Initial capabilities (10/07-9/10)Program Essentials Prime contractor: Arete Associates, Boeing, EDO Defense Systems...infrared seeker; EKV discrimination; the Orbital Sciences Corporation booster; the Cobra Dane radar; the Beale radar; the sea-based X-band radar

  9. Defense Acquisitions: Assessments of Selected Weapon Programs

    Science.gov (United States)

    2017-03-01

    67 low-rate production vehicles. The program official also stated that the SPH’s current steel cannon tube will be replaced with a chrome- plated ...four unique technologies required development—a dual pulse solid rocket motor, thermal batteries, an ignition safety device, and insensitive munitions...Recommended actions included, returning to a "Blue/ Gold " crew rotation model; merging the seaframe and mission package crew into a single

  10. Baselines for Assessment of Choice Programs

    Directory of Open Access Journals (Sweden)

    Paul T. Hill

    2003-10-01

    Full Text Available Critics of choice argue that it will allow alert and aggressive parents to get the best of everything for their children, leaving poor and minority children concentrated in the worst schools. (Note 1 But choice is not the only mechanism whereby this occurs. Alert and aggressive parents work the bureaucracy to get the best for their children. Thus, choice programs should be compared against the real performance of the current public education system, not its idealized aspirations.

  11. Defense Acquisitions: Assessments of Selected Weapon Programs

    Science.gov (United States)

    2014-03-01

    29Open systems architecture is a design approach that includes standard interfaces and the use of modular components within a product (like a computer ...releases for the total ship computing environment have been completed and certified to support lead ship activation and delivery and a software spiral...commenting on a draft of this assesment , the program office noted that in October 2011, G/ATOR’s performance requirements were revised, which resulted

  12. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix C, Savannah River Site Spent Nuclear Fuel Mangement Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures.

  13. The Nuclear program of Navy: an approach from the budget; O programa nuclear da Marinha: uma abordagem a partir do orcamento

    Energy Technology Data Exchange (ETDEWEB)

    Alves, Marco Antonio

    2014-07-01

    After the initiatives arising in the 50s, to conduct scientific research in Brazil, in the nuclear sector, the Brazilian government decided to invest resources in the early '70s, to provide the country with full training in the nuclear fuel cycle, producing reactors research and power and reprocessing of spent nuclear fuel in the reactors. This course of action was intended to guarantee the necessary to make stronger our energy matrix, with the use of natural resources (uranium and thorium mines whose reserves are among the largest in the world) for the production of electricity, within view particularly development programs in effect at the time. Meanwhile, the Navy of Brazil, identifying the need to operate nuclear-powered submarines in the security and defense of the South Atlantic, institutionalized in 1979, a nuclear program which aimed to the complete domination independently of the nuclear cycle. Since then, what is realized is that the trajectory of the development of this program, in addition to external difficulties imposed by countries holders of this technology, budget internal issue became relevant. The irregularity of financial transfers caused the delay and the lack of guarantees of future budgets led to the unpredictability of strategic planning, leading the program to the 'vegetative' state for nearly a decade. However, from the 2000s, the possibility of economic exploitation by the expansion of the Brazilian Continental Shelf and the new discoveries of oil in the pre-salt tier shifted the vision balance then attributed to the use of nuclear technology as an energy source only, or intended for research and development in areas such as health and agriculture, reinforced the argument that Brazil must have this technology to 'discourage the concentration of hostile forces within the limits of Brazilian territorial waters'. In this context, the paper describes and analyzes how the Navy Nuclear Program (PNM) amounted to the

  14. A multiaspect program integrity assessment of the cognitive-behavioral program EQUIP for incarcerated offenders

    NARCIS (Netherlands)

    Helmond, P.; Overbeek, G.; Brugman, D.

    2014-01-01

    Studies on the effectiveness of correctional treatment have widely failed to assess program integrity. This study examined the program integrity of EQUIP in 34 treatment groups of incarcerated offenders, using a new multiaspect program integrity instrument (MIPIE). The first aim of our study was to

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

    Energy Technology Data Exchange (ETDEWEB)

    Okrent, D.

    1997-06-23

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

  16. DOE role in nuclear policies and programs: official transcript of public briefing. Addendum December 13, 1977, Washington, D. C

    Energy Technology Data Exchange (ETDEWEB)

    1978-02-01

    A total of 24 questions were read into the official record at the public briefing on nuclear policies and programs. The answers published were researched and written by personnel of DOE's Office of Energy Research, Office of Energy Technology, and the Secretary's Office. A few questions were sent to the Nuclear Regulatory Commission for review and for preparation of answers.

  17. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, July 1--September 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A J [comp.

    1989-02-01

    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 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 June 30, 1988. 71 figs., 24 tabs.

  18. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, October 1--December 31, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A J; Azarm, A; Baum, J W; Boccio, J L; Carew, J; Diamond, D J; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Haber, S B

    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.

  19. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--March 31, 1989

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A.J. (comp.)

    1989-08-01

    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 December 31, 1988.

  20. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--June 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Baum, J W; Boccio, J L; Diamond, D; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Hall, R E; Higgins, J C; Weiss, A J [comp.

    1988-12-01

    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 December 31, 1987.

  1. Socioeconomic impact assessment and nuclear power plant licensing, Greene County, New York

    Energy Technology Data Exchange (ETDEWEB)

    Peelle, E

    1980-01-01

    The paper reviews the setting, participants and status of the joint federal-state hearings, findings of the FES, problems of conducting social impact assessment (SIA) for the GCNPP, and the nature and effect of public participation in the formal, legalistic hearings process. The GCNPP is evaluated in terms of trends in Atomic Energy Commission-Nuclear Regulatory Commission social impact assessments from 1972 to 1979. Progress in the adequacy and relevance of social impact assessment is defined according to steps in a lengthy, evolutionary legitimation process.

  2. Study on the code system for the off-site consequences assessment of severe nuclear accident

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sora; Mn, Byung Il; Park, Ki Hyun; Yang, Byung Mo; Suh, Kyung Suk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-12-15

    The importance of severe nuclear accidents and probabilistic safety assessment (PSA) were brought to international attention with the occurrence of severe nuclear accidents caused by the extreme natural disaster at Fukushima Daiichi nuclear power plant in Japan. In Korea, studies on level 3 PSA had made little progress until recently. The code systems of level 3 PSA, MACCS2 (MELCORE Accident Consequence Code System 2, US), COSYMA (COde SYstem from MAria, EU) and OSCAAR (Off-Site Consequence Analysis code for Atmospheric Releases in reactor accidents, JAPAN), were reviewed in this study, and the disadvantages and limitations of MACCS2 were also analyzed. Experts from Korea and abroad pointed out that the limitations of MACCS2 include the following: MACCS2 cannot simulate multi-unit accidents/release from spent fuel pools, and its atmospheric dispersion is based on a simple Gaussian plume model. Some of these limitations have been improved in the updated versions of MACCS2. The absence of a marine and aquatic dispersion model and the limited simulating range of food-chain and economic models are also important aspects that need to be improved. This paper is expected to be utilized as basic research material for developing a Korean code system for assessing off-site consequences of severe nuclear accidents.

  3. Assessment of possible airborne impact from nuclear risk sites - Part I: methodology for probabilistic atmospheric studies

    Science.gov (United States)

    Baklanov, A. A.; Mahura, A. G.

    2003-10-01

    The main purpose of this study is to develop a methodology for a multidisciplinary nuclear risk and vulnerability assessment, and to test this methodology through estimation of a nuclear risk to population in the Northern European countries in case of a severe accident at the nuclear risk sites. For assessment of the probabilistic risk and vulnerability, a combination of social-geophysical factors and probabilities are considered. The main focus of this paper is the description of methodology for evaluation of the atmospheric transport of radioactive releases from the risk site regions. The suggested methodology is given from the probabilistic point of view. The main questions stated are: What are probabilities and times for radionuclide atmospheric transport to different neighbouring countries and territories in case of the hypothetical accidental release at the nuclear risk site? Which geographical territories or countries are at the highest risk from the hypothetical accidental releases? To answer this question we suggest applying the following research tools for probabilistic atmospheric studies. First, it is atmospheric modelling to calculate multiyear forward trajectories originated over the sites. Second, it is statistical analysis tools to explore temporal and spatial structure of calculated trajectories in order to evaluate different probabilistic impact indicators: atmospheric transport pathways, airflow, fast transport, typical transport time, maximum possible impact zone, maximum reaching distance, etc. These indicators are applicable for further GIS-analysis and integration to estimate regional risk and vulnerability in case of accidental releases at the risk sites and for planning the emergency response and preparedness systems.

  4. 10 CFR 1.43 - Office of Nuclear Reactor Regulation.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Office of Nuclear Reactor Regulation. 1.43 Section 1.43... Program Offices § 1.43 Office of Nuclear Reactor Regulation. The Office of Nuclear Reactor Regulation— (a... health and safety, the environment, or the safeguarding of nuclear reactor facilities; (c) Assesses and...

  5. Safeguard assessment for life extension in nuclear power plants (NPPs) using a production function

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Tae-Ho, E-mail: thw@snu.ac.k [Department of Nuclear Engineering, Seoul National University, Gwanak 599, Gwanak-ro, Gwanak-gu, Seoul 151-742 (Korea, Republic of); Lee, Un-Chul [Department of Nuclear Engineering, Seoul National University, Gwanak 599, Gwanak-ro, Gwanak-gu, Seoul 151-742 (Korea, Republic of)

    2011-03-15

    Research highlights: The numerical value is constructed for the secure operation. As the power increases, the NSEF increases. Specific month could be indicated by the relative value of NSEF. It is suggested for the better power in NPPs. There is another possibility for the secure operation factors. - Abstract: Life extension is investigated as a safeguard assessment for the stability on the operation of the nuclear power plants (NPPs). The Cobb-Douglas function, one of the production functions, is modified for the nuclear safeguard in NPPs, which was developed for the life quality of the social and natural objects. Nuclear Safeguard Estimator Function (NSEF) is developed for the application in NPPs. The cases of NPPs are compared with each other in the aspect of the secure performance. The results are obtained by the standard productivity comparisons with the designed power operations. The range of secure life extension is between 1.008 and 5.353 in 2000 MW{sub e} and the range is between 0.302 and 0.994 in 600 MW{sub e}. So, the successfulness of the power operation increases about 5 times higher than that of the interested power in this study, which means that the safeguard assessment has been performed in the life extension of the NPPs. The technology assessment (TA) is suggested for the safe operation which is an advanced method comparing conventional probabilistic safety assessment (PSA).

  6. CNN's evaluation of the radiological monitoring special programs at the sites of nuclear installations; Evalluacion por el CSN de los programas especiales de vigilancia radiologica en los emplazamientos de las instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lareyne, O.; Marugan Tovar, I.; Martinez Moreno, M.; Sanz Alduan, M. T.

    2011-07-01

    In 2008, occurred in the Spanish plants various events related to the existence on the sites of the Spanish nuclear facilities or areas dotted with radioactive contamination outside the buildings, events that were reported to the Nuclear Safety Council (CSN) in accordance with the provisions of the regulation, as a result of the analysis of those events, the CSN issued in July 2008, a complementary technique instruction requiring the implementation of environmental monitoring programs in outdoor areas within sites nuclear facilities. First, the CSN nuclear facilities referred to the programs and methodologies intended to perform such monitoring, and, in late 2009, reports of program results.

  7. A probabilistic seismic risk assessment procedure for nuclear power plants: (II) Application

    Science.gov (United States)

    Huang, Y.-N.; Whittaker, A.S.; Luco, N.

    2011-01-01

    This paper presents the procedures and results of intensity- and time-based seismic risk assessments of a sample nuclear power plant (NPP) to demonstrate the risk-assessment methodology proposed in its companion paper. The intensity-based assessments include three sets of sensitivity studies to identify the impact of the following factors on the seismic vulnerability of the sample NPP, namely: (1) the description of fragility curves for primary and secondary components of NPPs, (2) the number of simulations of NPP response required for risk assessment, and (3) the correlation in responses between NPP components. The time-based assessment is performed as a series of intensity-based assessments. The studies illustrate the utility of the response-based fragility curves and the inclusion of the correlation in the responses of NPP components directly in the risk computation. ?? 2011 Published by Elsevier B.V.

  8. Assessment of modular construction for safety-related structures at advanced nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Braverman, J.; Morante, R.; Hofmayer, C.

    1997-03-01

    Modular construction techniques have been successfully used in a number of industries, both domestically and internationally. Recently, the use of structural modules has been proposed for advanced nuclear power plants. The objective in utilizing modular construction is to reduce the construction schedule, reduce construction costs, and improve the quality of construction. This report documents the results of a program which evaluated the proposed use of modular construction for safety-related structures in advanced nuclear power plant designs. The program included review of current modular construction technology, development of licensing review criteria for modular construction, and initial validation of currently available analytical techniques applied to concrete-filled steel structural modules. The program was conducted in three phases. The objective of the first phase was to identify the technical issues and the need for further study in order to support NRC licensing review activities. The two key findings were the need for supplementary review criteria to augment the Standard Review Plan and the need for verified design/analysis methodology for unique types of modules, such as the concrete-filled steel module. In the second phase of this program, Modular Construction Review Criteria were developed to provide guidance for licensing reviews. In the third phase, an analysis effort was conducted to determine if currently available finite element analysis techniques can be used to predict the response of concrete-filled steel modules.

  9. Program Educational Objectives Definition and Assessment for Accreditation Purposes

    Directory of Open Access Journals (Sweden)

    Noureddine Abbadeni

    2013-07-01

    Full Text Available Academic accreditation of degree programs is becoming an important mean for many institutions to improve the quality of their degree programs. Many programs, in particular computing and engineering, offered by many schools have engaged in the accreditation process with different accreditation bodies. The most known accreditation body in the Unites States of America for engineering, computing, technology, and applied science programs is ABET (Accreditation Board for Engineering and Technology. A key problem towards the satisfaction of ABET accreditation criteria is the appropriate definition and assessment of program educational objectives for a specific degree program. Program Educational Objectives are important as they represent the ultimate mean to judge the quality of a program. They related directly to student outcomes and curriculum of a degree program. We propose a set of guidelines to help understand how program educational objectives can be defined and assessed. We relate and use examples from our practical experience acquired while working on the ABET accreditation of a Software Engineering program;

  10. Pacific Northwest regional assessment program 1975 annual report

    Energy Technology Data Exchange (ETDEWEB)

    1976-06-01

    The objective of the Pacific Northwest Regional Assessment Program is to establish and exercise an integrated analytical assessment program for evaluation of potential changes that may result from various energy development or conservation scenarios. Such scenarios may themselves result from Federal development policies and programs, from regionally specific actions by the states and energy industries, or from actions taken by international factors currently importing energy resources into the region. After consideration of a variety of approaches to integrated assessment at a regional level, Battelle Pacific Northwest Laboratories (BNW) has concluded that dynamic simulation techniques provide the best available approach to evaluating the issues pertinent to the Northwest. As a result, the Pacific Northwest 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.

  11. Teaching and Assessing Professionalism in Ophthalmology Residency Training Programs

    NARCIS (Netherlands)

    Lee, Andrew G.; Beaver, Hilary A.; Boldt, H. Culver; Olson, Richard; Oetting, Thomas A.; Abramoff, Michael; Carter, Keith

    2007-01-01

    The Accreditation Council for Graduate Medical Education (ACGME) has mandated that all residency training programs teach and assess new competencies including professionalism. This article reviews the literature on medical professionalism, describes good practices gleaned from published works, and

  12. Environmental Monitoring and Assessment Program (EMAP) National Coastal Database

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Environmental Monitoring and Assessment Program (EMAP) National Coastal Database contains estuarine and coastal data that EMAP and Regional-EMAP have collected...

  13. Notification: Review of the Contract Management Assessment Program

    Science.gov (United States)

    Project #OA-FY14-0034, October 30, 2013. The Office of Inspector General plans to begin the preliminary research phase of an audit evaluating the Office of Acquisition Management’s Contract Management Assessment Program (CMAP).

  14. DOE/DHS INDUSTRIAL CONTROL SYSTEM CYBER SECURITY PROGRAMS: A MODEL FOR USE IN NUCLEAR FACILITY SAFEGUARDS AND SECURITY

    Energy Technology Data Exchange (ETDEWEB)

    Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

    2011-07-01

    Many critical infrastructure sectors have been investigating cyber security issues for several years especially with the help of two primary government programs. The U.S. Department of Energy (DOE) National SCADA Test Bed and the U.S. Department of Homeland Security (DHS) Control Systems Security Program have both implemented activities aimed at securing the industrial control systems that operate the North American electric grid along with several other critical infrastructure sectors (ICS). These programs have spent the last seven years working with industry including asset owners, educational institutions, standards and regulating bodies, and control system vendors. The programs common mission is to provide outreach, identification of cyber vulnerabilities to ICS and mitigation strategies to enhance security postures. The success of these programs indicates that a similar approach can be successfully translated into other sectors including nuclear operations, safeguards, and security. The industry regulating bodies have included cyber security requirements and in some cases, have incorporated sets of standards with penalties for non-compliance such as the North American Electric Reliability Corporation Critical Infrastructure Protection standards. These DOE and DHS programs that address security improvements by both suppliers and end users provide an excellent model for nuclear facility personnel concerned with safeguards and security cyber vulnerabilities and countermeasures. It is not a stretch to imagine complete surreptitious collapse of protection against the removal of nuclear material or even initiation of a criticality event as witnessed at Three Mile Island or Chernobyl in a nuclear ICS inadequately protected against the cyber threat.

  15. A program in medium-energy nuclear physics. Progress report, September 1, 1992--June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Berman, B.L.; Dhuga, K.S.

    1993-08-01

    This report reviews progress on our nuclear-physics program for the last ten months, and includes as well copies of our publications and other reports for that time period. The structure of this report follows that of our 1992 Progress Report: Sec. II outlines our research activities aimed at future experiments at CEBAF, NIKHEF, and Bates; Sec. III gives results of our recent research activities at NIKHEF, LAMPF, and elsewhere; Sec. IV provides an update of our laboratory activities at GWU, including those at our new Nuclear Detector Laboratory at our Virginia Campus; and Sec. V is a list of our publications, proposals, and other reports. Copies of those on medium-energy nuclear physics are reproduced in the Appendix. The highlight of the year has been the approval by the NIKHEF and CEBAF PACs of all three of the proposals we have submitted. These are ``Recoil Polarization of the Neutron in the Reactions {sup 3}He(e,e{prime}n) and {sup 4}He(e,e{prime}n),`` NIKHEF Proposal 93-09, ``Photoreactions on {sup 3}He,`` CEBAF Proposal 93-044, and ``Photoabsorption and Photofission of Nuclei,`` CEBAF Proposal 93-019. The NIKHEF experiment involves the use of the High-Acceptance Recoil Polarimeter for detection and measurement of the polarization of the emitted neutron. We, together with our colleagues at Grenoble, are responsible for the design and construction of the wire chambers for this device; we have largely completed the design phase this past year. The CEBAF experiments involve the use of the Hall-B Photon Tagger for production of the monochromatic photon beam. We are responsible for the 432-scintillator focal-plane detector array for this device; again, most of the design work and some prototype testing have been completed this past year. In addition, we have continued to make progress on data analysis and publication of results of previous measurements at Bates, LAMPF, and NIKHEF.

  16. A program in medium-energy nuclear physics. Progress report, September 1, 1992--June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Berman, B.L.; Dhuga, K.S.

    1998-06-01

    This report reviews progress on our nuclear-physics program for the last ten months, and includes as well copies of our publications and other reports for that time period. The structure of this report follows that of our 1992 Progress Report: Sec. II outlines our research activities aimed at future experiments at CEBAF, NIKHEF, and Bates; Sec. III gives results of our recent research activities at NIKHEF, LAMPF, and elsewhere; Sec. IV provides an update of our laboratory activities at GWU, including those at our new Nuclear Detector Laboratory at our Virginia Campus; and Sec. V is a list of our publications, proposals, and other reports. Copies of those on medium-energy nuclear physics are reproduced in the Appendix. The highlight of the year has been the approval by the NIKHEF and CEBAF PACs of all three of the proposals we have submitted. These are {open_quotes}Recoil Polarization of the Neutron in the Reactions {sup 3}He(e,e{prime}) and {sup 4}He(e,e{prime}n),{close_quotes} NIKHEF Proposal 93-09 {open_quotes}Photoreactions on {sup 3}He,{close_quotes} CEBAF Proposal 93-044, and {open_quotes}Photoabsorption and Photofission of Nuclei,{close_quotes} CEBAF Proposal 93-019. The NIKHEF experiment involves the use of the High-Acceptance Recoil Polarimeter (HARP) for detection and measurement of the polarization of the emitted neutron. We, together with our colleagues at Grenoble, are responsible for the design and construction of the wire chambers for this device; we have largely completed the design phase this part year. The CEBAF experiments involve the use of the Hall-B Photon Tagger for production of the monochromatic photon beam. We are responsible for the 432-scintillator focal-plane detector array for this device; again, most of the design work and some prototype testing have been completed this past year.

  17. Proliferation resistance assessment of various methods of spent nuclear fuel storage and disposal

    Science.gov (United States)

    Kollar, Lenka

    Many countries are planning to build or already are building new nuclear power plants to match their growing energy needs. Since all nuclear power plants handle nuclear materials that could potentially be converted and used for nuclear weapons, they each present a nuclear proliferation risk. Spent nuclear fuel presents the largest build-up of nuclear material at a power plant. This is a proliferation risk because spent fuel contains plutonium that can be chemically separated and used for a nuclear weapon. The International Atomic Energy Agency (IAEA) safeguards spent fuel in all non-nuclear weapons states that are party to the Non-Proliferation Treaty. Various safeguards methods are in use at nuclear power plants and research is underway to develop safeguards methods for spent fuel in centralized storage or underground storage and disposal. Each method of spent fuel storage presents different proliferation risks due to the nature of the storage method and the safeguards techniques that are utilized. Previous proliferation resistance and proliferation risk assessments have mainly compared nuclear material through the whole fuel cycle and not specifically focused on spent fuel storage. This project evaluates the proliferation resistance of the three main types of spent fuel storage: spent fuel pool, dry cask storage, and geological repository. The proliferation resistance assessment methodology that is used in this project is adopted from previous work and altered to be applicable to spent fuel storage. The assessment methodology utilizes various intrinsic and extrinsic proliferation-resistant attributes for each spent fuel storage type. These attributes are used to calculate a total proliferation resistant (PR) value. The maximum PR value is 1.00 and a greater number means that the facility is more proliferation resistant. Current data for spent fuel storage in the United States and around the world was collected. The PR values obtained from this data are 0.49 for

  18. Operational Risk Factors Assessment in non-nominally and transitory running regimes for Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    TONŢ Gabriela

    2010-05-01

    Full Text Available Using interdisciplinary approach andmodeling techniques the paper bridged the disciplinaryviewpoints towards supporting the system in operationwith the aim of facilitating effective decision-makingduring the task. The paper focuses on the modelingrisk using Bayesian associated analysis technique as acomplements tool for Probabilistic Risk Assessments(PRA. Examining the likelihood of event occurrencethrough fault tree analysis, this methodology evaluatescenarios which can emerge taking account of themore complex causal interrelationships. The proposedmethod tries to solve a risk assessment problemthrough analysis and modeling the influences of thecritical operating parameters in the high hazard, lowrisk system such as the nuclear plant. The case ofstudy, developed in terms of operational performanceof a nuclear power plant validates, analytically andexperimentally, the effectiveness of the proposedmethod for quantifying risk in systems.

  19. 75 FR 4098 - Section 8 Management Assessment Program (SEMAP) Certification

    Science.gov (United States)

    2010-01-26

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT Section 8 Management Assessment Program (SEMAP) Certification AGENCY: Office of the... Program (SEMAP) Certification. OMB Approval Number: 2577-0215. Form Numbers: HUD-52648. Description of the...

  20. Environmental Hazards Assessment Program: Quarterly report, October--December 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    This report describes activities and reports on progress for the second quarter (October 93 - December 93) of the second year of the grant to support the Environmental Hazards Assessment Program (EHAP). It reports progress against grant objectives and the Program Implementation Plan published at the end of the first year of the grant.

  1. International Code Assessment and Applications Program: Summary of code assessment studies concerning RELAP5/MOD2, RELAP5/MOD3, and TRAC-B. International Agreement Report

    Energy Technology Data Exchange (ETDEWEB)

    Schultz, R.R. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

    1993-12-01

    Members of the International Code Assessment Program (ICAP) have assessed the US Nuclear Regulatory Commission (USNRC) advanced thermal-hydraulic codes over the past few years in a concerted effort to identify deficiencies, to define user guidelines, and to determine the state of each code. The results of sixty-two code assessment reviews, conducted at INEL, are summarized. Code deficiencies are discussed and user recommended nodalizations investigated during the course of conducting the assessment studies and reviews are listed. All the work that is summarized was done using the RELAP5/MOD2, RELAP5/MOD3, and TRAC-B codes.

  2. Nuclear Science Division annual report for 1991

    Energy Technology Data Exchange (ETDEWEB)

    Myers, W.D. (ed.)

    1992-04-01

    This paper discusses research being conducted under the following programs: Low energy research program; bevalac research program; ultrarelativistic research program; nuclear theory program; nuclear theory program; nuclear data evaluation program; and 88-inch cyclotron operations.

  3. Implementing the Verbal Behavior Milestones Assessment and Placement Program (VB-MAPP): Teaching Assessment Techniques

    National Research Council Canada - National Science Library

    Barnes, Clarissa S; Mellor, James R; Rehfeldt, Ruth Anne

    2014-01-01

    The Verbal Behavior Milestones Assessment and Placement Program (VB-MAPP) is an assessment tool used with individuals diagnosed with autism spectrum disorder and other language delays (Sundberg 2008...

  4. Pspace: a program that assesses protein space

    Directory of Open Access Journals (Sweden)

    Zhou Ming-Ming

    2007-10-01

    Full Text Available Abstract Background We describe a computer program named Pspace designed to a obtain a reliable basis for the description of three-dimensional structures of a given protein family using homology modeling through selection of an optimal subset of the protein family whose structure would be determined experimentally; and b aid in the search of orthologs by matching two sets of sequences in three different ways. Methods The prioritization is established dynamically as new sequences and new structures are becoming available through ranking proteins by their value in providing structural information about the rest of the family set. The matching can give a list of potential orthologs or it can deduce an overall optimal matching of two sets of sequences. Results The various covering strategies and ortholog searches are tested on the bromodomain family. Conclusion The possibility of extending this approach to the space of all proteins is discussed.

  5. An overview of the Nuclear Electric Propulsion Space Test Program (NEPSTP) satellite

    Science.gov (United States)

    Voss, Susan S.; Reynolds, Edward L.

    Early in 1992 the idea of purchasing a Russian designed and fabricated space reactor power system and integrating it with a US designed satellite went from fiction to reality with the purchase of the first two Topaz II reactors by the Strategic Defense Initiative Organization (now the Ballistic Missile Defense Organization (BMDO). The New Mexico Alliance was formed to establish a ground test facility in which to perform nonnuclear systems testing of the Topaz II, and to evaluate the Topaz 11 system for flight testing with respect to safety, performance, and operability. In conjunction, SDIO requested that the Applied Physics Laboratory in Laurel, MD propose a mission and design a satellite in which the Topaz II could be used as the power source. The outcome of these two activities was the design of the Nuclear Electric Propulsion Space Test Program (NEPSTP) satellite which combines a modified Russian Topaz II power system with a US designed satellite to achieve a specified mission. Due to funding reduction within the SDIO, the Topaz II flight program was postponed indefinitely at the end of Fiscal Year 1993. The purpose of this paper is to present an overview of the NEPSTP mission and the satellite design at the time the flight program ended.

  6. Unit and integration testing of Lustre programs: a case study from the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Thevenod-Fosse, P

    1998-12-31

    LUSTRE belongs to the class of synchronous data flow languages which have been designed for programming reactive and real-time systems having safety-critical requirements. It is implemented in the SCADE tool. SCADE is a software development environment for real-time systems which consists of a graphical and textual editor, and a C code generator. In previous work, a testing approach specific to LUSTRE programs has been defined, which may be applied at either the unit or integration testing levels of a gradual testing process. The paper reports on an industrial case study we have performed to exemplify the feasibility of the testing strategy. The software module, called SRIC (Source Range Instrumentation channel), was developed by SCHNEIDER ELECTRIC in the SCADE environment. SRIC is extracted from a monitoring software system of a nuclear reactor: it approximates 2600 lines of C code automatically generated by SCADE. Section 2 outlines the testing strategy. Then, Section 3 presents the results related to the program SRIC, for which four testing levels were defined (unit testing followed by three successive integration testing levels). First conclusions and direction for future work are proposed in Section 4. (author)

  7. Nuclear ubiquitin proteasome degradation affects WRKY45 function in the rice defense program.

    Science.gov (United States)

    Matsushita, Akane; Inoue, Haruhiko; Goto, Shingo; Nakayama, Akira; Sugano, Shoji; Hayashi, Nagao; Takatsuji, Hiroshi

    2013-01-01

    The transcriptional activator WRKY45 plays a major role in the salicylic acid/benzothiadiazole-induced defense program in rice. Here, we show that the nuclear ubiquitin-proteasome system (UPS) plays a role in regulating the function of WRKY45. Proteasome inhibitors induced accumulation of polyubiquitinated WRKY45 and transient up-regulation of WRKY45 target genes in rice cells, suggesting that WRKY45 is constantly degraded by the UPS to suppress defense responses in the absence of defense signals. Mutational analysis of the nuclear localization signal indicated that UPS-dependent WRKY45 degradation occurs in the nuclei. Interestingly, the transcriptional activity of WRKY45 after salicylic acid treatment was impaired by proteasome inhibition. The same C-terminal region in WRKY45 was essential for both transcriptional activity and UPS-dependent degradation. These results suggest that UPS regulation also plays a role in the transcriptional activity of WRKY45. It has been reported that AtNPR1, the central regulator of the salicylic acid pathway in Arabidopsis, is regulated by the UPS. We found that OsNPR1/NH1, the rice counterpart of NPR1, was not stabilized by proteasome inhibition under uninfected conditions. We discuss the differences in post-translational regulation of salicylic acid pathway components between rice and Arabidopsis. © 2012 The Authors The Plant Journal © 2012 Blackwell Publishing Ltd.

  8. Unified description of structure and reactions: implementing the nuclear field theory program

    Science.gov (United States)

    Broglia, R. A.; Bortignon, P. F.; Barranco, F.; Vigezzi, E.; Idini, A.; Potel, G.

    2016-06-01

    The modern theory of the atomic nucleus results from the merging of the liquid drop model of Niels Bohr and Fritz Kalckar, and of the shell model of Marie Goeppert Meyer and Hans Jensen. The first model contributed the concepts of collective excitations. The second, those of independent-particle motion. The unification of these apparently contradictory views in terms of the particle-vibration and particle-rotation couplings carried out by Aage Bohr and Ben Mottelson has allowed for an ever more complete, accurate and detailed description of nuclear structure. Nuclear field theory (NFT), developed by the Copenhagen-Buenos Aires collaboration, provided a powerful quantal embodiment of this unification. Reactions are not only at the basis of quantum mechanics (statistical interpretation, Max Born), but also the specific tools to probe the atomic nucleus. It is then natural that NFT is being extended to deal with processes which involve the continuum in an intrinsic fashion, so as to be able to treat them on an equal footing with those associated with bound states (structure). As a result, spectroscopic studies of transfer to continuum states could eventually make use of the NFT rules, properly extended to take care of recoil effects. In the present contribution we review the implementation of the NFT program of structure and reactions, setting special emphasis on open problems and outstanding predictions.

  9. Feed-forward transcriptional programming by nuclear receptors: regulatory principles and therapeutic implications.

    Science.gov (United States)

    Sasse, Sarah K; Gerber, Anthony N

    2015-01-01

    Nuclear receptors (NRs) are widely targeted to treat a range of human diseases. Feed-forward loops are an ancient mechanism through which single cell organisms organize transcriptional programming and modulate gene expression dynamics, but they have not been systematically studied as a regulatory paradigm for NR-mediated transcriptional responses. Here, we provide an overview of the basic properties of feed-forward loops as predicted by mathematical models and validated experimentally in single cell organisms. We review existing evidence implicating feed-forward loops as important in controlling clinically relevant transcriptional responses to estrogens, progestins, and glucocorticoids, among other NR ligands. We propose that feed-forward transcriptional circuits are a major mechanism through which NRs integrate signals, exert temporal control over gene regulation, and compartmentalize client transcriptomes into discrete subunits. Implications for the design and function of novel selective NR ligands are discussed. Copyright © 2014 Elsevier Inc. All rights reserved.

  10. Development of a Pilot Program for Human Factors Management in Operating Nuclear Power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung-Woon; Lee, Yong-Hee; Jang, Tong-Il; Kim, Dae-Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    The human factors of operating NPPs have been reviewed as a part of Periodic Safety Reviews (PSRs). This human factors PSR covers a wide range of human factors including control room man-machine interfaces (MMIs), procedures, working conditions, qualification, training, information requirements and workload. Korea Atomic Energy Research Institute (KAERI) has performed human factors PSRs from the first PSR for Kori 1. It was determined in 2005 that for a Continuous Operation of the Korean NPPs an enhanced PSR should be performed and issues raised from the PSRs should be resolved. From the results of the PSR for Kori 1, several safety enhancement issues related to human factors were raised. KAERI is working on a resolution of some of the human factors issues for the Korea Hydro and Nuclear Power Co. (KHNP). As a part of the resolution, we are developing a human factors management program (HFMP) for Kori 1. This paper introduces the status of our development of HFMP.

  11. A development of the Human Factors Assessment Guide for the Study of Erroneous Human Behaviors in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Yeon Ju; Lee, Yong Hee; Jang, Tong Il; Kim, Sa Kil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-08-15

    The aim of this paper is to describe a human factors assessment guide for the study of the erroneous characteristic of operators in nuclear power plants (NPPs). We think there are still remaining the human factors issues such as an uneasy emotion, fatigue and stress, varying mental workload situation by digital environment, and various new type of unsafe response to digital interface for better decisions, although introducing an advanced main control room. These human factors issues may not be resolved through the current human reliability assessment which evaluates the total probability of a human error occurring throughout the completion of a specific task. This paper provides an assessment guide for the human factors issues a set of experimental methodology, and presents an assessment case of measurement and analysis especially from neuro physiology approach. It would be the most objective psycho-physiological research technique on human performance for a qualitative analysis considering the safety aspects. This paper can be trial to experimental assessment of erroneous behaviors and their influencing factors, and it can be used as an index for recognition and a method to apply human factors engineering V and V, which is required as a mandatory element of human factor engineering program plan for a NPP design.

  12. Patents Assessed through Sectoral Operational Programs

    Directory of Open Access Journals (Sweden)

    Paula – Angela VIDRAȘCU

    2014-06-01

    Full Text Available According to the International Accounting Standards – IAS 38 „Intangible assets”; these assets are identifiable non-monetary assets under construction were considered without physical substance. Lack actual physical form must not be understood that an intangible asset would have no material support, because the presence of any intangible asset can be demonstrated only by a support material form. Exmple: frequently encounter compact-disc (in case a software, legal documentation (in the case of licences, trade marks and patents of invention, contracts, permits and licences, technical documentation or films. Nowadays we are constantly subjected to the changing flow of information that is found in a perpetual technological change which started the emergence of a new stage in the society development that which carries the name of knowledge. The object of my research is the patent for the structural funds reimbursable project submitted in the "Operational Program, Economic Competitiveness" Operation 2.3.1. "Support for start-ups and innovative spin-offs. Patent is an official document certifying the inventor, the exclusive right to produce a certain good or product or use a particular process. Remember that evaluation of intangible assets is the most complex and systematic procedure.

  13. [Nuclear techniques in nutrition: assessment of body fat and intake of human milk in breast-fed infants].

    Science.gov (United States)

    Pallaro, Anabel; Tarducci, Gabriel

    2014-12-01

    The application of nuclear techniques in the area of nutrition is safe because they use stable isotopes. The deuterium dilution method is used in body composition and human milk intake analysis. It is a reference method for body fat and validates inexpensive tools because of its accuracy, simplicity of application in individuals and population and the background of its usefulness in adults and children as an evaluation tool in clinical and health programs. It is a non-invasive technique as it uses saliva, which facilitates the assessment in pediatric populations. Changes in body fat are associated with non-communicable diseases; moreover, normal weight individuals with high fat deposition were reported. Furthermore, this technique is the only accurate way to determine whether infants are exclusively breast-fed and validate conventional methods based on surveys to mothers.

  14. Development and operation of the network system for nuclear safety - Improvement of the following accident dose assessment system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Enn Han; Han, Moon Hee; Suh, Kyung Suk; Hwang, Won Tae [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-12-01

    The FADAS has been updates for calculating the real-time wind fields continuously at the nuclear sites in Korea. The system has been constructed to compute the wind fields using its own process for the dummy meteorological data, and does not effect on the overall wind field module. If the radioactive materials are released into the atmosphere in real situation, the calculations of wind fields and exposure dose in the previous FADAS are performed in the case of the recognition of the above situation in the source term evaluation module. The current version of FADAS includes the program for evaluating the effect of the predicted accident and the assumed scenario together. The dose assessment module is separated into the real-time and the supposed accident respectively. 8 refs., 17 figs., 10 tabs. (Author)

  15. Assessment of Tritium Activity in Groundwater at the Nuclear Objects Sites in Lithuania

    Directory of Open Access Journals (Sweden)

    Vigilija Cidzikienė

    2014-01-01

    Full Text Available The assessment of nuclear objects sites in Lithuania, including groundwater characterization, took place in the last few years. Tritium activity in groundwater is a very useful tool for determining how groundwater systems function. Natural and artificial tritium was measured in 8 wells in different layers (from 1.5 to 15 meters depth. The results were compared with other regions of Lithuania also. The evaluated tritium activities varied from 1.8 to 6.4 Bq/L at nuclear objects sites in Lithuania and they are coming to background level (1.83 Bq/L and other places in Lithuania. The data show, that groundwater at the nuclear power objects sites is not contaminated with artificial tritium. In this work, the vertical tritium transfer from soil water to the groundwater well at nuclear objects site was estimated. The data show that the main factor for vertical tritium transfer to the well depends on the depth of wells.

  16. Scenario Analysis for the Safety Assessment of Nuclear Waste Repositories: A Critical Review.

    Science.gov (United States)

    Tosoni, Edoardo; Salo, Ahti; Zio, Enrico

    2017-09-05

    A major challenge in scenario analysis for the safety assessment of nuclear waste repositories pertains to the comprehensiveness of the set of scenarios selected for assessing the safety of the repository. Motivated by this challenge, we discuss the aspects of scenario analysis relevant to comprehensiveness. Specifically, we note that (1) it is necessary to make it clear why scenarios usually focus on a restricted set of features, events, and processes; (2) there is not yet consensus on the interpretation of comprehensiveness for guiding the generation of scenarios; and (3) there is a need for sound approaches to the treatment of epistemic uncertainties. © 2017 Society for Risk Analysis.

  17. Complementary Safety Margin Assessment f the Nuclear Installations of the research reactor in Petten, Netherlands

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

    On March 11, 2011, a large part of the Japanese eastern coastal area was devastated by an earthquake, followed by an immense tsunami. As a result, thousands of people were killed, injured or made homeless. In the days that followed, the situation was further complicated because of the failing nuclear reactors on the Fukushima coast. The local environment suffered from radioactive releases, requiring evacuation zones, and generating international concerns about nuclear safety. In the wake of this disaster the European Union decided to assess safety on all operating nuclear reactors in its member states. This safety evaluation initiated by the European Union focusses on extreme natural hazards, beyond the standard safety evaluations which regularly have to be performed to demonstrate the safety of a nuclear power plant. Consequences of these extreme hazards for the research reactor in Petten, Netherlands, have been evaluated based on available safety analyses, supplemented by engineering judgement. In this way, the robustness of the existing plant has been assessed and possible measures to further increase the safety margins have been identified. This document presents the results of the Complementary Safety margin Assessment (CSA) performed for the 'Onderzoekslocatie Petten'. The distinct difference between this report and former risk analysis reports in general and the existing Safety Report of the Petten reactor is that the maximum resistance of the plant against redefined and more challenging events has been investigated, whereas traditionally the plant design is investigated against certain events that are determined on a historical basis. This different approach requires different analyses and studies, which in turn presents new insights into the robustness of the plant. The main purpose of this report is to answer the questions posed by the Ministry of Economic Affairs, Agriculture and Innovation. It was decided to write at the same time a report in

  18. Nuclear Analysis and Technology Assessment of Radar Concepts. Volume II. Radiation Vulnerability Assessment of Radar Components.

    Science.gov (United States)

    1981-05-20

    q( Vak ’b)) _i] where u = minority-carrier mobil iv = minority-carrier lifetime Va acolied voltage Vb = potential drop across built-in region Neutron...cavity is well known. 1 56 In fact, this effect has been used to monitor power levels inside reactor cores. 1 57𔃻 58𔃻 59 It has been shown that the...1971). 157.) "Microwave Diagnosis of a Plasma Generated in a Reactor and its Use as a Reactor Power Monitor"M. Voth and E. Kenny; Nuclear Instruments

  19. Chemical Stockpile Disposal Program rapid accident assessment

    Energy Technology Data Exchange (ETDEWEB)

    Chester, C.V.

    1990-08-01

    This report develops a scheme for the rapid assessment of a release of toxic chemicals resulting from an accident in one of the most chemical weapon demilitarization plants or storage areas. The system uses such inputs as chemical and pressure sensors monitoring the plant and reports of accidents radioed to the Emergency Operations Center by work parties or monitoring personnel. A size of release can be estimated from previous calculations done in the risk analysis, from back calculation from an open-air chemical sensor measurement, or from an estimated percentage of the inventory of agent at the location of the release. Potential consequences of the estimated release are calculated from real-time meteorological data, surrounding population data, and properties of the agent. In addition to the estimated casualties, area coverage and no-death contours vs time would be calculated. Accidents are assigned to one of four categories: community emergencies, which are involve a threat to off-site personnel; on-post emergencies, which involve a threat only to on-site personnel; advisory, which involves a potential for threat to on-site personnel; and chemical occurrence, which can produce an abnormal operating condition for the plant but no immediate threat to on-site personnel. 9 refs., 20 tabs.

  20. The impact of the Fukushima nuclear accident on marine biota: Retrospective assessment of the first year and perspectives

    NARCIS (Netherlands)

    Vives i Battle, Jordi; Aono, Tatsuo; Brown, Justin E.; Hosseini, Ali; Garnier-Laplace, Jacqueline; Sazykina, Tatiana; Steenhuisen, Frits; Strand, Per

    2014-01-01

    An international study under the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) was performed to assess radiological impact of the nuclear accident at the Fukushima-Daiichi Nuclear Power Station (FDNPS) on the marine environment. This work constitutes the first