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Sample records for program ii 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. 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.

  3. 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)

  4. Startup control of the TOPAZ-II space nuclear reactor

    OpenAIRE

    Astrin, Cal D.

    1996-01-01

    Approved for public release; distribution isunlimited. The Russian designed and manufactured TOPAZ-II Thermionic Nuclear Space Reactor has been supplied to the Ballistic Missile Defense Organization for study as part of the TOPAZ International Program. A Preliminary Nuclear Safety Assessment investigated the readiness to use the TOPAZ-II in support of a Nuclear Electric Propulsion Space Test Mission (NEPSTP). Among the anticipated system modifications required for launching the TOPAZ-II sy...

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. Nuclear emergency buildings of Asco and Vandellos II nuclear power plants; Centros alternativos de emergencias de las centrales nucleares de Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Massuet, J.; Sabater, J.; Mirallas Esteban, S.

    2016-08-01

    The Nuclear Emergency Buildings sited at Asco and Vandellos II Nuclear Power Plants (NPP) are designed to safety manage emergencies in extreme situations, beyond the design basis of the Nuclear Power Plants. Designed in accordance with the requirements of the Spanish Nuclear Regulator (Consejo de Seguridad Nuclear-CSN) these buildings are ready to operate over a period of 72 hours without external assistance and ensure habitability for crews of 120 and 70 people respectively. This article describes the architectural conception, features and major systems of the Nuclear Emergency Buildings sited at Asco and Vandellos II. (Author)

  14. 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.

  15. 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

  16. Experiments with radioactive nuclear beams II; Experimentos con haces nucleares radiactivos II

    Energy Technology Data Exchange (ETDEWEB)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A.; Lizcano C, D.; Garcia M, H.; Rosales M, P. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2001-12-15

    The studies of nuclear reactions with heavy ions have been carried out for years for the group of heavy ions of the laboratory of the Accelerator of the ININ. Especially in the last years the group has intruded in the studies of nuclear reactions with radioactive beams, frontier theme at world level. Presently Technical Report is presented in detailed form the experimental methods and the analysis procedures of the research activities carried out by the group. The chpater II is dedicated to the procedures used in the analysis of the last two experiments with radioactive beams carried out by the group. In the chapter III is presented the procedure followed to carrying out an extended analysis with the CCDEF code, to consider the transfer channel of nucleons in the description of the fusion excitation functions of a good number of previously measured systems by the group. Finally, in the chapter IV the more important steps to continue in the study of the reaction {sup 12}C + {sup 12}C experiment drifted to be carried out using the available resources of the Tandem Accelerator Laboratory of the ININ are described. At the end of each chapter some of the more representative results obtained in the analysis are presented and emphasis on the scientific production generated by the group for each case is made. (Author)

  17. Self-assembly of high-nuclearity metal clusters: programmed expansion of a metallasiloxane cage to an octacopper(II) cluster.

    Science.gov (United States)

    Abbati, Gian Luca; Cornia, Andrea; Caneschi, Andrea; Fabretti, Antonio C; Mortalo, Cecilia

    2004-07-26

    The novel octanuclear copper(II) cluster [Cu6[(PhSiO2)6]2[NCCu(Me6tren)]2(MeOH)4]2+ (1) has been isolated as a perchlorate salt by reacting the hexacopper(II) metallasiloxane cage [Cu6[(PhSiO2)6]2(nBuOH)x] (x = 4, 6) with [Cu(Me6tren)CN]ClO4 in a methanol/chloroform mixture (Me6tren = tris(2-(dimethylamino)ethyl) amine). Crystal data for 1(ClO4)2 x MeOH: monoclinic, space group P2(1)/n (no. 14), a = 16.8490(3) angstroms, b = 22.2966(4) angstroms, c = 17.2508(3) angstroms, beta = 94.7658(5) degrees, V = 6458.3(2) angstroms3, Z = 2. The structure comprises a highly distorted hexagonal Cu6 array linked to two [Cu(Me6tren)] units via cyanide bridges. Magnetic measurements reveal that the addition of the copper cyanide complexes dramatically affects the magnetism of the Cu6 unit, whose ground spin state changes from S = 3 to S = 0. Copyright 2004 American Chemical Society

  18. 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...

  19. Nuclear spectroscopy with direct relations II. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Throw, F. E. [ed.

    1964-03-01

    The Symposium on Nuclear Spectroscopy with Direct Reactions, sponsored and organized by Argonne National Laboratory under the auspices of the U. S. Atomic Energy Commission, was held on 9-11 March 1964 at the Center for Continuing Education, University of Chicago. The present volume contains the invited papers along with abstracts or summaries of the few short papers selected for their special relevance to the topics of the invited lecturers . Edited versions of the discussions are also included.

  20. Topaz II Nuclear Powered SAR Satellite

    OpenAIRE

    Feuerstein, M.; Agrawal, B.N.

    1994-01-01

    The article of record as published may be found at http://dx.doi.org/10.2514/6.1994-4688 The AA4871 Spacecraft Design course is the capstone class for the M.S. in Astronautics at the Naval Postgraduate School. Thc design team integrated a Topaz If nuclear power system with an EOS Synthetic Aperture Radar to design a low Earth orbit, three axis stabilized satellite flying in a gravity gradient stable orientation. The SAR is a high resolution, electronically stecrable, Earth scie...

  1. 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

  2. 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.

  3. 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.

  4. 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.

  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. 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.

  7. 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,…

  8. 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.

  9. 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

  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. 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.

  12. 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.

  13. 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

  14. 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

  15. 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

  16. 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.

  17. 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.

  18. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-08-15

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

  20. 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.

  1. Amelia II: A Program for Missing Data

    Directory of Open Access Journals (Sweden)

    James Honaker

    2011-12-01

    Full Text Available Amelia II is a complete R package for multiple imputation of missing data. The package implements a new expectation-maximization with bootstrapping algorithm that works faster, with larger numbers of variables, and is far easier to use, than various Markov chainMonte Carlo approaches, but gives essentially the same answers. The program also improves imputation models by allowing researchers to put Bayesian priors on individual cell values, thereby including a great deal of potentially valuable and extensive information. Italso includes features to accurately impute cross-sectional datasets, individual time series, or sets of time series for different cross-sections. A full set of graphical diagnostics are also available. The program is easy to use, and the simplicity of the algorithm makes itfar more robust; both a simple command line and extensive graphical user interface are included.

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

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-03-01

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

  3. 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.

  4. Nuclear Technology Series. Course 17: Radiation Protection II.

    Science.gov (United States)

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

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  5. 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.

  6. 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)

  7. Fuel management inside the reactor. Project AZ-101 (ININ). Report of the generation of the nuclear bank 'L1PG3826' of the assemblies GE5 and GE9B 'collapsed' of the CNLV for the FCS-II program of the FMS system; Administracion de combustible dentro del reactor. Proyecto AZ-101 (ININ). Reporte de generacion del banco nuclear 'L1PG3826' de los ensambles GE5 y GE9B 'colapsados' de la CNLV para el programa FCS-II del FMS

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G.; Torres A, C

    1991-06-15

    In order to be able to carry out studies but next to the operation of the reactor of the CNLV with the program FCS-II of the package of codes for the fuel management FMS, it was generated a 'collapsed' nuclear bank integrating the generated information with RECORD of each one of those assemblies of the initial load and of the first recharge. To generate the bank, the different ones RECORD 'cells' that compose each assemble were 'collapsed' to an alone one, representing this, to the one complete assemble in what refers to the fuel bars distribution and enrichments. The one collapsed of each assemble it is made averaging the content of UO{sub 2} and Gd{sub 2}O{sub 3} in each fuel bar by the volumetric fraction occupied by each axial section of the fuel bar where the content of UO{sub 2} and Gd{sub 2}O{sub 3} were constant, by this way the x-y fuel bars arrangement is conserved but a representative fuel cell of all the assemble is obtained. Of the five different assemblies that will be load in the reactor of the CNLV (3 of the initial load and 2 of the first recharge), only 4 were collapsed; the remaining one to be totally formed by natural uranium it was not necessary to collapse. From the collapsing process new enrichment values in U-235 and in content of Gd{sub 2}O{sub 3} for each fuel bar, for what according to the generation procedure of nuclear information it was generated the required information by RECORD for each fuel bar with Gd{sub 2}O{sub 3} with the ECLIPSE code. Once generated this information it was proceeded to generate the homogenized nuclear information, with RECORD, for the whole cell. According to the requirements of nuclear information of FCS-II, the nuclear Information generated with RECORD only was of the defined type as series 1 in the procedure of generation of nuclear banks '6F3/1/CN029/90/P1'; that which means that only it was generated nuclear information as function of the burnup of the fuel and of

  8. (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.

  9. 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)

  10. 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.

  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. 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.

  13. 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.

  14. 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.

  15. Monte Carlo simulation of nuclear energy study (II). Annual report on Nuclear Code Evaluation Committee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-01-01

    In the report, research results discussed in 1999 fiscal year at Nuclear Code Evaluation Committee of Nuclear Code Research Committee were summarized. Present status of Monte Carlo simulation on nuclear energy study was described. Especially, besides of criticality, shielding and core analyses, present status of applications to risk and radiation damage analyses, high energy transport and nuclear theory calculations of Monte Carlo Method was described. The 18 papers are indexed individually. (J.P.N.)

  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. 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.

  18. 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.

  19. 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

  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. 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.

  2. 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.

  3. Nuclear cardiology, Part II: Scintigraphic evaluation of cardiac function.

    Science.gov (United States)

    Hambÿe, A S; Everaert, H; Maes, A; Mesotten, L; Vandevivere, J; Mortelmans, L; Franken, P R

    1998-06-01

    Different methods are currently available to assess cardiac function, especially left ventricular ejection fraction, using either planar or tomographic imaging, first-pass or equilibrium techniques, and blood-pool or myocardial perfusion agents. This is the second article of a four-part series on nuclear cardiology. In this article the authors review the most widely used radiopharmaceuticals and methodologies.

  4. Delays in nuclear power plant construction. Volume II. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Mason, G.E.; Larew, R.E.; Borcherding, J.D.; Okes, S.R. Jr.; Rad, P.F.

    1977-12-14

    The report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts which should minimize or eliminate the identified barriers. The identified barriers include (1) Design and Construction Interfacing Problems; (2) Problems Relating to the Selection and Use of Permanent Materials and Construction Methods; (3) Construction Coordination and Communication Problems; and (4) Problems Associated with Manpower Availability and Productivity.

  5. Commercial Nuclear Steam-Electric Power Plants, Part II

    Science.gov (United States)

    Shore, Ferdinand J.

    1974-01-01

    Presents the pros and cons of nuclear power systems. Includes a discussion of the institutional status of the AEC, AEC regulatory record, routine low-level radiation hazards, transport of radioactive materials, storage of wastes, and uranium resources and economics of supply. (GS)

  6. Measurement of Nuclear Recoils in the CDMS II Dark Matter Search

    Energy Technology Data Exchange (ETDEWEB)

    Fallows, Scott Mathew [Univ. of Minnesota, Minneapolis, MN (United States)

    2014-12-01

    The Cryogenic Dark Matter Search (CDMS) experiment is designed to directly detect elastic scatters of weakly-interacting massive dark matter particles (WIMPs), on target nuclei in semiconductor crystals composed of Si and Ge. These scatters would occur very rarely, in an overwhelming background composed primarily of electron recoils from photons and electrons, as well as a smaller but non-negligible background of WIMP-like nuclear recoils from neutrons. The CDMS II generation of detectors simultaneously measure ionization and athermal phonon signals from each scatter, allowing discrimination against virtually all electron recoils in the detector bulk. Pulse-shape timing analysis allows discrimination against nearly all remaining electron recoils taking place near detector surfaces. Along with carefully limited neutron backgrounds, this experimental program allowed for \\background- free" operation of CDMS II at Soudan, with less than one background event expected in each WIMP-search analysis. As a result, exclusionary upper-limits on WIMP-nucleon interaction cross section were placed over a wide range of candidate WIMP masses, ruling out large new regions of parameter space.

  7. 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

  8. Trichinella spiralis-infected muscle cells: abundant RNA polymerase II in nuclear speckle domains colocalizes with nuclear antigens.

    Science.gov (United States)

    Yao, C; Jasmer, D P

    2001-06-01

    Infection of mammalian skeletal muscle cells by Trichinella spiralis causes host nuclei to become polyploid (ca. 4N) and abnormally enlarged. It has been postulated that this enlargement reflects an infection-induced elevation of host transcription. Anthelmintic treatment of T. spiralis-infected rodents with mebendazole (MBZ) causes a reduction in the size of infected cell nuclei and a significant reduction in the total RNA content of individual infected muscle cells. A monoclonal antibody to the large subunit of RNA polymerase II (Pol II) was used here to assess the effects of infection on Pol II levels in isolated infected cell nuclei. Pol II was localized to speckle domains in isolated infected cell nuclei. Similar domains have been previously localized to sites of RNA synthesis or processing. When compared to the levels in nuclei from other, uninfected host cells, speckle-localized Pol II (SL-Pol II) levels were significantly elevated in infected cell nuclei by a mean of 3.9- to 6.8-fold. Nuclear antigens (NA) recognized by antibodies against T. spiralis localized to infected cell nuclei. By use of confocal microscopy, a subpopulation of NA was found colocalized with most speckle domains defined by Pol II. MBZ treatment of chronically infected mice, which depletes NA from infected cell nuclei, caused a significant depletion of SL-Pol II from infected cell nuclei. Control nuclei had a mean of 70% more SL-Pol II than MBZ-treated nuclei. The mean residual level of Pol II in these polyploid nuclei remained elevated by 120% over the level in 2N control nuclei. These observations may indicate two distinct effects of infection on Pol II levels in host cells.

  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. 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).

  11. A part-time Level II fieldwork program.

    Science.gov (United States)

    Adelstein, L A; Cohn, E S; Baker, R C; Barnes, M A

    1990-01-01

    This paper describes an alternative to the traditional Level II fieldwork program for master's degree students in occupational therapy. In this part-time 9-month program, students complete the fieldwork requirement while simultaneously balancing academic responsibilities. One advantage of this program over the traditional 3-month program is that the extended length of time offers students the opportunity to develop clinical skills beyond the technical level.

  12. Recent applications of nuclear medicine in diagnostics: II part

    Directory of Open Access Journals (Sweden)

    Giorgio Treglia

    2013-04-01

    Full Text Available Introduction: Positron-emission tomography (PET and single photon emission computed tomography (SPECT are effective diagnostic imaging tools in several clinical settings. The aim of this article (the second of a 2-part series is to examine some of the more recent applications of nuclear medicine imaging techniques, particularly in the fields of neurology, cardiology, and infection/inflammation. Discussion: A review of the literature reveals that in the field of neurology nuclear medicine techniques are most widely used to investigate cognitive deficits and dementia (particularly those associated with Alzheimer disease, epilepsy, and movement disorders. In cardiology, SPECT and PET also play important roles in the work-up of patients with coronary artery disease, providing accurate information on the state of the myocardium (perfusion, metabolism, and innervation. White blood cell scintigraphy and FDG-PET are widely used to investigate many infectious/inflammatory processes. In each of these areas, the review discusses the use of recently developed radiopharmaceuticals, the growth of tomographic nuclear medicine techniques, and the ways in which these advances are improving molecular imaging of biologic processes at the cellular level.

  13. 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.

  14. Cofilin Regulates Nuclear Architecture through a Myosin-II Dependent Mechanotransduction Module

    Science.gov (United States)

    Wiggan, O’Neil; Schroder, Bryce; Krapf, Diego; Bamburg, James R.; DeLuca, Jennifer G.

    2017-01-01

    Structural features of the nucleus including shape, size and deformability impact its function affecting normal cellular processes such as cell differentiation and pathological conditions such as tumor cell migration. Despite the fact that abnormal nuclear morphology has long been a defining characteristic for diseases such as cancer relatively little is known about the mechanisms that control normal nuclear architecture. Mounting evidence suggests close coupling between F-actin cytoskeletal organization and nuclear morphology however, mechanisms regulating this coupling are lacking. Here we identify that Cofilin/ADF-family F-actin remodeling proteins are essential for normal nuclear structure in different cell types. siRNA mediated silencing of Cofilin/ADF provokes striking nuclear defects including aberrant shapes, nuclear lamina disruption and reductions to peripheral heterochromatin. We provide evidence that these anomalies are primarily due to Rho kinase (ROCK) controlled excessive contractile myosin-II activity and not to elevated F-actin polymerization. Furthermore, we demonstrate a requirement for nuclear envelope LINC (linker of nucleoskeleton and cytoskeleton) complex proteins together with lamin A/C for nuclear aberrations induced by Cofilin/ADF loss. Our study elucidates a pivotal regulatory mechanism responsible for normal nuclear structure and which is expected to fundamentally influence nuclear function. PMID:28102353

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. Educational Programs and Services: Part II.

    Science.gov (United States)

    American Annals of the Deaf, 1981

    1981-01-01

    The journal section provided information on the programs offered, the students served, and the educational staff employed by U.S. and Canadian schools and classes for deaf children, deaf educators, and the deaf blind. (SB)

  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. Huntington II Simulation Program-POLUT. Teacher's Guide.

    Science.gov (United States)

    Braun, L.; And Others

    This teacher's guide is written to accompany the Huntington II Simulation Program - POLUT. POLUT is a program written in BASIC which provides simulation of the interaction between water and waste. It creates a context within which the user can control specific variables which effect the quality of a water resource. The teacher's guide provides…

  2. Phase II final report and second update of the energy economic data base (EEDB) program. Volume 1 of 1

    Energy Technology Data Exchange (ETDEWEB)

    1981-04-01

    The Energy Economic Data Base (EEDB) Program deals with the development of cost data for nuclear and comparison electric power generating stations. The objective of the USDOE EEDB Program is to provide periodic updates of technical and cost (capital, fuel and operating and maintenance) information of significance to the US Department of Energy. This information is intended to be used by USDOE in evaluating and monitoring US Civilian nuclear power programs, and to provide them with a consistent means of evaluating the nuclear option against alternatives. This report presents the Second Update of the EEDB for a cost and regulation date of January 1, 1979, prepared during Phase II of the EEDB Program. The Second Update is the first of a series of periodic updates marking the beginning of the next step in meeting the objective of the EEDB Program.

  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. International Photovoltaic Program Plan. Volume II. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Costello, D.; Koontz, R.; Posner, D.; Heiferling, P.; Carpenter, P.; Forman, S.; Perelman, L.

    1979-12-01

    This second volume of a two-part report on the International Photovoltaic Program Plan contains appendices summarizing the results of analyses conducted in preparation of the plan. These analyses include compilations of relevant statutes and existing Federal programs; strategies designed to expand the use of photovoltaics abroad; information on the domestic photovoltaic plan and its impact on the proposed international plan; perspectives on foreign competition; industry views on the international photovoltaic market and ideas about how US government actions could affect this market; international financing issues; and information on issues affecting foreign policy and developing countries.

  5. MENC and World War II Programs.

    Science.gov (United States)

    Mark, Michael L.

    1980-01-01

    Like other national organizations from 1939 to 1945, the Music Educators National Conference (MENC) worked to promote national unity in the United States. MENC position statements are quoted in this article and its wartime music education programs outlined. (One of three articles on music in the 1930s-1940s.) (SJL)

  6. CHARACTERIZATION OF FLUORESCENT NUCLEAR TRACK DETECTORS AS CRITICALITY DOSIMETERS II.

    Science.gov (United States)

    Harrison, J; Moreno, B; Van Hoey, O; Mihailescu, L-C; Vanhavere, F; Million, M; Fomenko, V; Akselrod, M

    2017-10-21

    Fluorescent nuclear track detectors (FNTDs) as criticality dosimeters for both neutrons and gamma are further characterized in terms of angular dependence and quick dose assessment. The power spectrum integral depth profiles obtained from stacks of fluorescent images acquired within FNTDs exposed to a broad spectrum neutron field at various angles are analyzed to determine a calibration curve for angular dependence. MCNPX simulations were shown to be in good agreement with experimental results. A prototype triage reader was also designed and tested for quick assessment of dose. An unfolding technique incorporating both energy dependence and angular dependence is discussed. The advantages and shortcomings of using FNTDs in the event of a criticality excursion accident are analyzed. © The Author 2017. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  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. 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.

  15. Proceedings of the 1984 DOE nuclear reactor and facility safety conference. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    1984-01-01

    This report is a collection of papers on reactor safety. The report takes the form of proceedings from the 1984 DOE Nuclear Reactor and Facility Safety Conference, Volume II of two. These proceedings cover Safety, Accidents, Training, Task/Job Analysis, Robotics and the Engineering Aspects of Man/Safety interfaces.

  16. EMPIRE-II code-system with RIPL database as a tool for nuclear spectroscopy

    Energy Technology Data Exchange (ETDEWEB)

    Sin, Mihaela E-mail: msin@pcnet.ro

    2004-07-21

    The paper presents the modular system of nuclear reaction codes EMPIRE-II in conjunction with RIPL-2 database as a valuable tool in the spin-parity assignment for discrete levels of residual nuclei populated in reactions evolving through the compound nucleus mechanism. Several applications illustrating the method and code's predictive power are presented.

  17. 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.

  18. 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.

  19. The progress of nuclear pumped laser in CFBR-II reactor

    Science.gov (United States)

    Yang, Chengde; Chen, Hande; Zheng, Chun; Zhao, Xiaolin; Han, Huilin

    2003-05-01

    Development of nuclear pumped lasers (NPL) in the CFBR-II reactor is briefly reviewed. The results of the two NPL experiments in CFBR-II reactor are described. The first one focused on the principle of nuclear pumped laser, and 4-mW laser output power achieved. The second NPL experiment focused on the small signal gain and the efficiency of the nuclear pumped He-Ar-Xe gas mixture at 1.73 ?m. The maximum laser power measured to be 45 mW when thermal neutron flux rate is 6.9 * 1014 cm^(-2)·s^(-1). The small signal gain at 1.73 ?m by the Rigrod analysis method is to be 0.24%·cm^(-1), and the saturation intensity is fitted to be 36 W/cm^(2).

  20. Multiparticle Production in Particle and Nuclear Collisions. II

    Science.gov (United States)

    Kanki, T.; Kinoshita, K.; Sumiyoshi, H.; Takagi, F.

    The dominant phenomenon in high-energy particle and nuclear collisions is multiple production of hadrons. This had attracted may physicists in 1950's, the period of the first remarkable development of particle physics. Multiparticle production was already observed in cosmic-ray experiments and expected to be explained as a natural consequence of the strong Yukawa interaction. Statistical and hydrodynamical models were then proposed by Fermi, Landau and others. These theories are still surviving even today as a prototype of modern ``fire-ball'' models. After twenty years, a golden age came in this field of physics. It was closely related to the rapid development of accelerator facilities, especially, the invention of colliding-beam machines which yield high enough center-of-mass energies for studying reactions with high multiplicity. Abundant data on final states of multiparticle production have been accumulated mainly by measuring inclusive cross sections and multiplicity distributions. In super high-energy bar{p}p collisions at CERN S pmacr pS Collider, we confirmed the increasing total cross section and found violations of many scaling laws which seemed to be valid at lower energies. This suggests a fundamental complexity of the multiparticle phenomena and offers new materials for further development of theoretical investigations. In the same period, studies of constituent (quark-gluon) structure of hadrons had also been develped. Nowadays, pysicists believe that the quantum chromodynamics (QCD) is the fundamental law of the hadronic world. Multiparticle dynamics should also be described by QCD. We have known that the hard-jet phenomena are well explained by the perturbative QCD. On the other hand, the soft processes are considered to be non-perturbative phenomena which have not yet been solved, and related to the mechanism of the color confinement and formation of strings or color-flux tubes. Multiparticle production would offer useful information on this

  1. Human Reliability Analysis for Digitized Nuclear Power Plants: Case Study on the LingAo II Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Yanhua Zou

    2017-03-01

    Full Text Available The main control room (MCR in advanced nuclear power plants (NPPs has changed from analog to digital control system (DCS. Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

  2. 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).

  3. 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

  4. 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.

  5. 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

  6. Nuclear reactions with radioactive and stable beams (Part II); Reacciones nucleares con haces radiactivos y estables (Parte II)

    Energy Technology Data Exchange (ETDEWEB)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A.; Lizcano, D. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2005-12-15

    At the present time there is a great interest at world level in experiments, with accelerated nuclei of short half life. The dispersion, fusion, transfer and break processes in the interaction of weakly light projectiles bounded with targets of Z great its have been object of intense recent investigation, at world level. Our group, in collaboration with the University of Notre Dame, it has measured and analyzed these processes for weakly bound systems as: {sup 6}He + {sup 209}Bi, {sup 8}Li + {sup 208}Pb, {sup 10}Be + {sup 208}Pb. On the other hand a research line that has wakened up great interest, it is that of studies of resonant reactions using the Inverse Kinematics technique with thick targets. The use of this technique allows to measure an entire excitation function with a single bombardment. Our group has carried out, in the ININ, preliminary bombardments for the system {sup 12}C + {sup 4}He. This allowed to establish the feasibility of implementing this technique in our Laboratory. The application of this and other techniques to different systems like {sup 18}O + {sup 4}He, {sup 12}C + {sup 12}C, {sup 12}C + {sup 16}O, {sup 16}O + {sup 16}O, it opens the possibility to measure the fusion of these systems at very low energy and to deepen in the knowledge of the nuclear structure and the nuclear astrophysics. In this technical report, the activities carried out by our group during the second stage of this project, considered for 2005 are described. Also in that year, our group carries out a research stay in the University of Notre Dame, during this stay, the angular distribution of the projectiles of {sup 8}B dispersed in an enriched target of {sup 58}Ni was measured. The same as in the previous experiments, in this occasion it was also possible to measure those angular distributions of the projectiles of {sup 7}Be and {sup 6}Li dispersed in this same target. In this same one our stay group participates in other three experiments proposed by collaborators of

  7. 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

  8. 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

  9. Perceptual Skills Curriculum: Auditory-motor Skills, Program II.

    Science.gov (United States)

    Rosner, Jerome

    This curriculum is designed primarily for use in individualized classrooms where the teacher is working with an assistant, but it has also been proven effective in traditional classrooms and in remedial situations. Program II focuses on the basic abilities used in analyzing and organizing acoustical patterns, with special emphasis on verbal…

  10. Mathematics Programming on the Apple II and IBM PC.

    Science.gov (United States)

    Myers, Roy E.; Schneider, David I.

    1987-01-01

    Details the features of BASIC used in mathematics programming and provides the information needed to translate between the Apple II and IBM PC computers. Discusses inputing a user-defined function, setting scroll windows, displaying subscripts and exponents, variable names, mathematical characters and special symbols. (TW)

  11. Adaptation-II of the surrogate methods for linear programming ...

    African Journals Online (AJOL)

    Adaptation-II of the surrogate methods for linear programming problems. SO Oko. Abstract. No Abstract. Global Journal of Mathematical Sciences Vol. 5(1) 2006: 63-71. Full Text: EMAIL FULL TEXT EMAIL FULL TEXT · DOWNLOAD FULL TEXT DOWNLOAD FULL TEXT · http://dx.doi.org/10.4314/gjmas.v5i1.21381.

  12. 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.

  13. 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

  14. 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.

  15. 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

  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. Nuclear Shell Structure and Beta Decay I. Odd A Nuclei II. Even A Nuclei

    Science.gov (United States)

    Mayer, M.G.; Moszkowski, S.A.; Nordheim, L.W.

    1951-05-01

    In Part I a systematics is given of all transitions for odd A nuclei for which sufficiently reliable data are available. The allowed or forbidden characters of the transitions are correlated with the positions of the initial and final odd nucleon groups in the nuclear shell scheme. The nuclear shells show definite characteristics with respect to parity of the ground states. The latter is the same as the one obtained from known spins and magnetic moments in a one-particle interpretation. In Part II a systematics of the beta transitions of even-A nuclei is given. An interpretation of the character of the transitions in terms of nuclear shell structure is achieved on the hypothesis that the odd nucleon groups have the same structure as in odd-A nuclei, together with a simple coupling rule between the neutron and proton groups in odd-odd nuclei.

  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. Pol II-directed short RNAs suppress the nuclear export of mRNA.

    Science.gov (United States)

    Komarova, Tatiana V; Schwartz, Anton M; Frolova, Olga Y; Zvereva, Anna S; Gleba, Yuri Y; Citovsky, Vitaly; Dorokhov, Yuri L

    2010-12-01

    The synthesis and subsequent nuclear export of non-coding RNA (ncRNA) directed by RNA polymerase (Pol) II is very sensitive to abiotic and biotic external stimuli including pathogen challenges. To assess whether stress-induced ncRNAs may suppress the nuclear export of mRNA, we exploited the ability of Agrobacterium tumefaciens to co-deliver Pol I, II and III promoter-based vectors for the transcription of short (s) ncRNAs, GFP mRNA or genomic RNA of plant viruses (Tobacco mosaic virus, TMV; or Potato virus X, PVX) into the nucleus of Nicotiana benthamiana cells. We showed that, in contrast to Pol I- and Pol III-derived sncRNAs, all tested Pol II-derived sncRNAs (U6 RNA, tRNA or artificial RNAs) resulted in decreased expression of GFP and host mRNA. The level of this inhibitory effect depended on the non-coding transcript length and promoter strength. Short coding RNA (scRNA) can also compete with mRNA for nuclear export. We showed that scRNA, an artificial 117-nt short sequence encoding Elastin-Like peptide element tandems with FLAG sequence (ELF) and the 318-nt N. benthamiana antimicrobial peptide thionin (defensin) gene efficiently decreased GFP expression. The stress-induced export of Pol II-derived sncRNA and scRNA into the cytoplasm via the mRNA export pathway may block nucleocytoplasmic traffic including the export of mRNA responsible for antivirus protection. Consistent with this model, we observed that Pol II-derived sncRNAs as well as scRNA, thionin and ELF strongly enhanced the cytoplasmic reproduction of TMV and PVX RNA.

  3. 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.)

  4. 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

  5. The Bacillus cereus spoIIS programmed cell death system

    Directory of Open Access Journals (Sweden)

    Jana eMelnicakova

    2015-08-01

    Full Text Available Programmed cell death in bacteria is generally associated with two¬ component toxin antitoxin systems. The SpoIIS toxin-antitoxin system, consisting of a membrane bound SpoIISA toxin and a small, cytosolic antitoxin SpoIISB, was originally identified in Bacillus subtilis. In this work we describe the Bacillus cereus SpoIIS system which is a three-component system, harbouring an additional gene spoIISC. Its protein product serves as an antitoxin, and similarly as SpoIISB, is able to bind SpoIISA and abolish its toxic effect. Our results indicate that SpoIISC seems to be present not only in B. cereus but also in other Bacilli containing a SpoIIS toxin antitoxin system. In addition, we show that B. cereus SpoIISA can form higher oligomers and we discuss the possible role of this multimerization for the protein’s toxic function.

  6. UGV/Demo II Program: status through Demo C and Demo II preparations

    Science.gov (United States)

    Munkeby, Steve H.; Spofford, John R.

    1996-05-01

    The unmanned ground vehicle (UGV) demonstration C was completed in July of 1995. This was the third of four planned UGV/Demo II demonstrations. Demonstration C highlighted multivehicle premission planning, mission execution monitoring, multivehicle mobility cooperation, target detection from moving and stationary platforms, obstacle avoidance, obstacle map sharing, stealthy movement, autonomous turnaround, formation control/zone security, cooperative reconnaissance, surveillance, and target acquisition, and hill cresting. This demonstration was the first to have two autonomous vehicles working cooperatively while performing a militarily relevant mission. This paper begins with a background of the UGV program and then focuses on Demo C. The paper finishes with an overview of the Demo II missions.

  7. 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.

  8. 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.

  9. Phase I Report, US DOE GRED II Program

    Energy Technology Data Exchange (ETDEWEB)

    Fairbank Engineering Ltd.

    2003-04-23

    Noramex Corporation Inc, a Nevada company, owns a 100% interest in geothermal leases at the Blue Mountain Geothermal Area, Humboldt County, Nevada. The company is exploring the site for a geothermal resource suitable for development for electric power generation or In the spring of 2002, Noramex drilled the first geothermal observation hole at Blue Mountain, under a cost-share program with the U.S Department of Energy (DOE), under the DOE's Geothermal Exploration and Resource Definition (GRED) program, (Cooperative Agreement No. DE-FC04-00AL66972). DEEP BLUE No.1 was drilled to a total depth of 672.1 meters (2205 feet) and recorded a maximum temperature of 144.7 C (292.5 F). Noramex Corporation will now drill a second slim geothermal observation test hole at Blue Mountain, designated DEEP BLUE No.2. The hole will be drilled under a cost-share program with the DOE, under the DOE's Geothermal Exploration and Resource Definition II (GRED II) program, (Cooperative Agreement No. DE-FC04-2002AL68297). This report comprises Phase I of Cooperative Agreement No. DE-FC04-2002AL68297 of the GRED II program. The report provides an update on the status of resource confirmation at the Blue Mountain Geothermal Area, incorporating the results from DEEP BLUE No.1, and provides the technical background for a second test hole. The report also outlines the proposed drilling program for slim geothermal observation test hole DEEP BLUE No.2.

  10. 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.

  11. 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.

  12. 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,…

  13. 48 CFR 1852.219-81 - Limitation on subcontracting-SBIR Phase II program.

    Science.gov (United States)

    2010-10-01

    ... subcontracting-SBIR Phase II program. 1852.219-81 Section 1852.219-81 Federal Acquisition Regulations System... CLAUSES Texts of Provisions and Clauses 1852.219-81 Limitation on subcontracting—SBIR Phase II program. As prescribed in 1819.7302(b), insert the following clause: Limitation on Subcontracting—SBIR Phase II Program...

  14. Combined Electrical, Optical and Nuclear Investigations of Impurities and Defects in II-VI Semiconductors

    CERN Multimedia

    2002-01-01

    % IS325 \\\\ \\\\ To achieve well controlled bipolar conductivity in II-VI semiconductors represents a fundamental problem in semiconductor physics. The doping problems are controversely discussed, either in terms of self compensation or of compensation and passivation by unintentionally introduced impurities. \\\\ \\\\It is the goal of our experiments at the new ISOLDE facility, to shed new light on these problems and to look for ways to circumvent it. For this aim the investigation of impurities and native defects and the interaction between each other shall be investigated. The use of radioactive ion beams opens the access to controlled site selective doping of only one sublattice via nuclear transmutation. The compensating and passivating mechanisms will be studied by combining nuclear, electrical and optical methods like Perturbed Angular Correlation~(PAC), Hall Effect~(HE), Deep Level Transient Spectroscopy~(DLTS), Photoluminescence Spectroscopy~(PL) and electron paramagnetic resonance (EPR). \\\\ \\\\We intend to ...

  15. 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

  16. Seismic II over I Drop Test Program results and interpretation

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, B.

    1993-03-01

    The consequences of non-seismically qualified (Category 2) objects falling and striking essential seismically qualified (Category 1) objects has always been a significant, yet analytically difficult problem, particularly in evaluating the potential damage to equipment that may result from earthquakes. Analytical solutions for impact problems are conservative and available for mostly simple configurations. In a nuclear facility, the {open_quotes}sources{close_quotes} and {open_quotes}targets{close_quotes} requiring evaluation are frequently irregular in shape and configuration, making calculations and computer modeling difficult. Few industry or regulatory rules are available on this topic even though it is a source of considerable construction upgrade costs. A drop test program was recently conducted to develop a more accurate understanding of the consequences of seismic interactions. The resulting data can be used as a means to improve the judgment of seismic qualification engineers performing interaction evaluations and to develop realistic design criteria for seismic interactions. Impact tests on various combinations of sources and targets commonly found in one Savannah River Site (SRS) nuclear facility were performed by dropping the sources from various heights onto the targets. This report summarizes results of the Drop Test Program. Force and acceleration time history data are presented as well as general observations on the overall ruggedness of various targets when subjected to impacts from different types of sources.

  17. Seismic II over I Drop Test Program results and interpretation

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, B.

    1993-03-01

    The consequences of non-seismically qualified (Category 2) objects falling and striking essential seismically qualified (Category 1) objects has always been a significant, yet analytically difficult problem, particularly in evaluating the potential damage to equipment that may result from earthquakes. Analytical solutions for impact problems are conservative and available for mostly simple configurations. In a nuclear facility, the [open quotes]sources[close quotes] and [open quotes]targets[close quotes] requiring evaluation are frequently irregular in shape and configuration, making calculations and computer modeling difficult. Few industry or regulatory rules are available on this topic even though it is a source of considerable construction upgrade costs. A drop test program was recently conducted to develop a more accurate understanding of the consequences of seismic interactions. The resulting data can be used as a means to improve the judgment of seismic qualification engineers performing interaction evaluations and to develop realistic design criteria for seismic interactions. Impact tests on various combinations of sources and targets commonly found in one Savannah River Site (SRS) nuclear facility were performed by dropping the sources from various heights onto the targets. This report summarizes results of the Drop Test Program. Force and acceleration time history data are presented as well as general observations on the overall ruggedness of various targets when subjected to impacts from different types of sources.

  18. 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).

  19. 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)

  20. 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.

  1. Phase II: Field Detector Development For Undeclared/Declared Nuclear Testing For Treaty Verfiation Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Kriz, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hunter, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Riley, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-10-02

    Radioactive xenon isotopes are a critical part of the Comprehensive Nuclear Test Ban Treaty (CTBT) for the detection or confirmation of nuclear weapons tests as well as on-site treaty verification monitoring. On-site monitoring is not currently conducted because there are no commercially available small/robust field detector devices to measure the radioactive xenon isotopes. Xenon is an ideal signature to detect clandestine nuclear events since they are difficult to contain and can diffuse and migrate through soils due to their inert nature. There are four key radioxenon isotopes used in monitoring: 135Xe (9 hour half-life), 133mXe (2 day half-life), 133Xe (5 day half-life) and 131mXe (12 day half-life) that decay through beta emission and gamma emission. Savannah River National Laboratory (SRNL) is a leader in the field of gas collections and has developed highly selective molecular sieves that allow for the collection of xenon gas directly from air. Phase I assessed the development of a small, robust beta-gamma coincidence counting system, that combines collection and in situ detection methodologies. Phase II of the project began development of the custom electronics enabling 2D beta-gamma coincidence analysis in a field portable system. This will be a significant advancement for field detection/quantification of short-lived xenon isotopes that would not survive transport time for laboratory analysis.

  2. Multi-Nuclear NMR Investigation of Nickel(II), Palladium(II), Platinum(II) and Ruthenium(II) Complexes of an Asymmetrical Ditertiary Phosphine

    Energy Technology Data Exchange (ETDEWEB)

    Raj, Joe Gerald Jesu [Institut National de la Recherche Scientifique, Quebec (China); Pathak, Devendra Deo [Indian School of Mines, Dhanbad (India); Kapoor, Pramesh N. [Univ. of Delhi, Delhi (India)

    2013-12-15

    Complexes synthesized by reacting alkyl and aryl phosphines with different transition metals are of great interest due to their catalytic properties. Many of the phosphine complexes are soluble in polar solvents as a result they find applications in homogeneous catalysis. In our present work we report, four transition metal complexes of Ni(II), Pd(II), Pt(II) and Ru(II) with an asymmetrical ditertiaryphosphine ligand. The synthesized ligand bears a less electronegative substituent such as methyl group on the aromatic nucleus hence makes it a strong σ-donor to form stable complexes and thus could effectively used in catalytic reactions. The complexes have been completely characterized by elemental analyses, FTIR, {sup 1}HNMR, {sup 31}PNMR and FAB Mass Spectrometry methods. Based on the spectroscopic evidences it has been confirmed that Ni(II), Pd(II) and Pt(II) complexes with the ditertiaryphosphine ligand showed cis whereas the Ru(II) complex showed trans geometry in their molecular structure.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 20 CFR 628.530 - Referrals of participants to non-title II programs.

    Science.gov (United States)

    2010-04-01

    ... LABOR PROGRAMS UNDER TITLE II OF THE JOB TRAINING PARTNERSHIP ACT Program Design Requirements for... Rehabilitation, State or local education, substance abuse treatment center, and/or dislocated worker programs...

  9. 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).

  10. 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.

  11. 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

  12. 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.

  13. 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

  14. Commissioning of the water demineralization plant of Atucha II Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Schonbrod, B.; Grasso, G.; Ormando, M., E-mail: bschonbrod@na-sa.com.ar, E-mail: ggrasso@na-sa.com.ar, E-mail: mormando@na-sa.com.ar [Nucleoelectrica Argentina S.A., Central Nuclear Atucha II, Lima/Zarate, Provincia de Buenos Aires (Argentina); Chocron, M.; Rodriguez, I.; Lagamma, A.M., E-mail: chocron@cnea.gov.ar, E-mail: irodriguez@cnea.gov.ar, E-mail: lagamma@cnea.gov.ar [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

    2010-07-01

    In Argentina there are two operating Nuclear Power Reactors and a third one is being constructed. Embalse NPP is a 648 Mwe CANDU®-600 type pressurized heavy water reactor (PHWR), designed and built by Atomic Energy of Canada (AECL) and in commercial operation since 1984. Atucha I is a Pressurized Vessel Heavy Water Reactor (PVHWR) of 340 Mwe, in operation since 1974, and Atucha II (also PHWR) of 740 Mwe is in advanced construction state, both of them designed by SIEMENS-KWU. All of these Nuclear Power Plants are operated by Nucleoelectrica Argentina (N.A.S.A.). The Comision Nacional de Energia Atomica (C.N.E.A.) is the R and D nuclear institution in the country that, among many other topics, provides technical support to the plants. Although the Atucha II project has suffered some years of delay, pressure tests are expected to be carried out by the end of the year 2010 and in that sense, water chemistry related activities, specifications, chemistry manuals, laboratories organization and personnel training are acquiring importance. The demineralized water needed for the secondary and auxiliary systems is obtained by means of a demineralization plant, which purifies water from Parana River up to nuclear grade. This plant was designed by Degremont in 1979 and consists of a preliminary treatment by coagulation - flocculation and gravel filters, and subsequent demineralization with ion exchange resins. For the commissioning of the demineralization plant, preliminary tests in the chemical laboratory are performed. The flocculator is simulated using a Jar-Test, different coagulants and coagulation aids are tested with the objective of selecting the best product and defining its optimum dosage. The coagulated water is filtered by means of a funnel with filtration paper and sand. The clarified water thus obtained is treated by ion exchange resins, the train consisting of a cationic, an anionic and a mixed bed. The purpose of the laboratory experiments is to test the resins

  15. 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.

  16. 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.

  17. TRU Waste Sampling Program: Volume II. Gas generation studies

    Energy Technology Data Exchange (ETDEWEB)

    Clements, T.L. Jr.; Kudera, D.E.

    1985-09-01

    Volume II of the TRU Waste Sampling Program report contains the data generated from evaluating the adequacy of venting/filtering devices for maintaining safe hydrogen levels in plutonium contaminated waste drums. Additional studies reported in this volume include gas generation rates, selected waste form monitoring, and evaluation of hydrogen migration from sealed 90-mil rigid polyethylene drum liners containing /sup 238/Pu-contaminated wastes. All wastes used in the studies were newly-generated, and the waste drums were under controlled, experimental conditions. Studies using /sup 239/Pu-contaminated wastes were conducted at the Rocky Flats Plant. Studies using /sup 238/Pu-contaminated wastes were conducted at the Los Alamos National Laboratory.

  18. 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.

  19. 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.

  20. 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

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. The Gpn3 Q279* cancer-associated mutant inhibits Gpn1 nuclear export and is deficient in RNA polymerase II nuclear targeting.

    Science.gov (United States)

    Barbosa-Camacho, Angel A; Méndez-Hernández, Lucía E; Lara-Chacón, Bárbara; Peña-Gómez, Sonia G; Romero, Violeta; González-González, Rogelio; Guerra-Moreno, José A; Robledo-Rivera, Angélica Y; Sánchez-Olea, Roberto; Calera, Mónica R

    2017-11-01

    Gpn3 is required for RNA polymerase II (RNAPII) nuclear targeting. Here, we investigated the effect of a cancer-associated Q279* nonsense mutation in Gpn3 cellular function. Employing RNAi, we replaced endogenous Gpn3 by wt or Q279* RNAi-resistant Gpn3R in epithelial model cells. RNAPII nuclear accumulation and transcriptional activity were markedly decreased in cells expressing only Gpn3R Q279*. Wild-type Gpn3R localized to the cytoplasm but a fraction of Gpn3R Q279* entered the cell nucleus and inhibited Gpn1-EYFP nuclear export. This property and the transcriptional deficit in Gpn3R Q279*-expressing cells required a PDZ-binding motif generated by the Q279* mutation. We conclude that an acquired PDZ-binding motif in Gpn3 Q279* caused Gpn3 nuclear entry, and inhibited Gpn1 nuclear export and Gpn3-mediated RNAPII nuclear targeting. © 2017 Federation of European Biochemical Societies.

  8. Halon Replacement Program for Aviation, Aircraft Engine Nacelle Application Phase II - Operational Comparison of Selected Extinguishants

    National Research Council Canada - National Science Library

    Bennett, John A

    1997-01-01

    This report documents the work performed under Phase II - Operational Comparison of Selected Extinguishants - of the Halon Replacement Program for Aviation for the Aircraft Engine Nacelle Application...

  9. RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste; Fud-program 2010. Program foer forskning, utveckling och demonstration av metoder foer hantering och slutfoervaring av kaernavfall

    Energy Technology Data Exchange (ETDEWEB)

    2010-09-15

    The RD and D programme 2010 gives an account of SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas - the programme for Low and Intermediate Level Waste (the Loma program) and the Nuclear Fuel Program. The RD and D Programme 2010 consists of five parts: Part I: Overall Plan, Part II: Loma program, Part III: Nuclear Fuel Program, Part IV: Research on analysis of long-term safety, Part V: Social Science Research. The 2007 RD and D programme was focused primarily on technology development to realize the final repository for spent nuclear fuel. The actions described were aimed at increasing awareness of long-term safety and to obtain technical data for application under the Nuclear Activities Act for the final repository for spent fuel and under the Environmental Code of the repository system. Many important results from these efforts are reported in this program. An overall account of the results will be given in the Licensing application in early 2011. The authorities' review of RD and D programme in 2007 and completion of the program called for clarification of plans and programs for the final repository for short-lived radioactive waste, SFR, and the final repository for waste, SFL. This RD and D program describes these plans in a more detailed way

  10. 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.

  11. VERIFIKASI PAKET PROGRAM MVP-II DAN SRAC2006 PADA KASUS TERAS REAKTOR VERA BENCHMARK.

    Directory of Open Access Journals (Sweden)

    Jati Susilo

    2015-03-01

    Full Text Available Dalam penelitian ini dilakukan verifikasi perhitungan benchmark VERA pada kasus Zero Power Physical Test (ZPPT teras reaktor Watts Bar 1. Reaktor tersebut merupakan jenis PWR kelas 1000 MWe yang didesain oleh Westinghouse, tersusun dari 193 perangkat bahan bakar 17×17 dengan 3 jenis pengkayaan UO2 yaitu 2,1wt%, 2,619wt% dan 3,1wt%. Perhitungan nilai k-eff dan distribusi faktor daya dilakukan pada siklus operasi pertama teras dengan kondisi beginning of cycle (BOC dan hot zero power (HZP. Posisi batang kendali dibedakan menjadi uncontrolled (semua batang kendali berada di luar teras, dan controlled (batang kendali Bank D didalam teras. Paket program komputer yang digunakan dalam perhitungan adalah MVP-II dan SRAC2006 modul CITATION dengan data pustaka tampang lintang ENDF/B-VII.0. Hasil perhitungan menunjukkan bahwa perbedaan nilai k-eff teras pada kondisi controlled dan uncontrolled antara referensi dengan MVP-II (-0,07% dan -0,014% dan SRAC2006 (0,92% dan 0,99% sangat kecil atau masih dibawah 1%. Perbedaan faktor daya maksimum teras pada kondisi controlled dan uncontrolled dengan referensi dengan MVP-II adalah 0,38% dan 1,53%, sedangkan dengan SRAC2006 adalah 1,13% dan -2,45%. Dapat dikatakan bahwa kedua paket program komputer menunjukkan hasil perhitungan yang sesuai dengan nilai referensi. Dalam hal penentuan kekritisan teras, maka hasil perhitungan MVP-II lebih konservatif dibandingkan dengan SRAC2006. Kata kunci : MVP-II, SRAC2006, PWR, VERA   In this research, verification calculation for VERA core physics benchmark on the Zero Power Physical Test (ZPPT of the nuclear reactor Watts Bar 1. The reactor is a 1000 MWe class of PWR designed by Westinghouse, arranged from 193 unit of 17×17 fuel assembly consisting 3 type enrichment of UO2 that are 2.1wt%, 2.619wt% and 3.1wt%. Core power factor distribution and k-eff calculation has been done for the first cycle operation of the core at beginning of cycle (BOC and hot zero power (HZP. In this

  12. Genetic association analysis of 13 nuclear-encoded mitochondrial candidate genes with type II diabetes mellitus : the DAMAGE study

    NARCIS (Netherlands)

    Reiling, Erwin; van Vliet-Ostaptchouk, Jana V.; van't Riet, Esther; van Haeften, Timon W.; Arp, Pascal A.; Hansen, Torben; Kremer, Dennis; Groenewoud, Marlous J.; van Hove, Els C.; Romijn, Johannes A.; Smit, Jan W. A.; Nijpels, Giel; Heine, Robert J.; Uitterlinden, Andre G.; Pedersen, Oluf; Slagboom, P. Eline; Maassen, Johannes A.; Hofker, Marten H.; 't Hart, Leen M.; Dekker, Jacqueline M.

    Mitochondria play an important role in many processes, like glucose metabolism, fatty acid oxidation and ATP synthesis. In this study, we aimed to identify association of common polymorphisms in nuclear-encoded genes involved in mitochondrial protein synthesis and biogenesis with type II diabetes

  13. Genetic association analysis of 13 nuclear-encoded mitochondrial candidate genes with type II diabetes mellitus: The DAMAGE study

    DEFF Research Database (Denmark)

    Reiling, Erwin; van Vliet-Ostaptchouk, Jana V; van 't Riet, Esther

    2009-01-01

    Mitochondria play an important role in many processes, like glucose metabolism, fatty acid oxidation and ATP synthesis. In this study, we aimed to identify association of common polymorphisms in nuclear-encoded genes involved in mitochondrial protein synthesis and biogenesis with type II diabetes...

  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. Coal dust alters β-naphthoflavone-induced aryl hydrocarbon receptor nuclear translocation in alveolar type II cells

    Directory of Open Access Journals (Sweden)

    Castranova Vincent

    2009-08-01

    Full Text Available Abstract Background Many polycyclic aromatic hydrocarbons (PAHs can cause DNA adducts and initiate carcinogenesis. Mixed exposures to coal dust (CD and PAHs are common in occupational settings. In the CD and PAH-exposed lung, CD increases apoptosis and causes alveolar type II (AT-II cell hyperplasia but reduces CYP1A1 induction. Inflammation, but not apoptosis, appears etiologically associated with reduced CYP1A1 induction in this mixed exposure model. Many AT-II cells in the CD-exposed lungs have no detectable CYP1A1 induction after PAH exposure. Although AT-II cells are a small subfraction of lung cells, they are believed to be a potential progenitor cell for some lung cancers. Because CYP1A1 is induced via ligand-mediated nuclear translocation of the aryl hydrocarbon receptor (AhR, we investigated the effect of CD on PAH-induced nuclear translocation of AhR in AT-II cells isolated from in vivo-exposed rats. Rats received CD or vehicle (saline by intratracheal (IT instillation. Three days before sacrifice, half of the rats in each group started daily intraperitoneal injections of the PAH, β-naphthoflavone (BNF. Results Fourteen days after IT CD exposure and 1 day after the last intraperitoneal BNF injection, AhR immunofluorescence indicated that proportional AhR nuclear expression and the percentage of cells with nuclear AhR were significantly increased in rats receiving IT saline and BNF injections compared to vehicle controls. However, in CD-exposed rats, BNF did not significantly alter the nuclear localization or cytosolic expression of AhR compared to rats receiving CD and oil. Conclusion Our findings suggest that during particle and PAH mixed exposures, CD alters the BNF-induced nuclear translocation of AhR in AT-II cells. This provides an explanation for the modification of CYP1A1 induction in these cells. Thus, this study suggests that mechanisms for reduced PAH-induced CYP1A1 activity in the CD exposed lung include not only the

  16. 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.

  17. 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.

  18. 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.

  19. 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…

  20. 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)

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. National Registry of Cardiac Rehabilitation Programs in Mexico II (RENAPREC II).

    Science.gov (United States)

    Ilarraza-Lomelí, Hermes; García-Saldivia, Marianna; Rojano-Castillo, Jessica; Justiniano, Samuel; Cerón, Norma; Aranda-Ayala, Zulema-L; Rodríguez, Azucena; Hernández, Alejandro; Cassaigne, María-Elena; Cantero, Raúl; Gasca, Pablo; Hinojosa, Tania; Alonso, Jesús; Romo, Ricardo; Lara, Jorge; Pimentel, Elizabeth; Zavala, Juana; Rius-Suárez, María-Dolores; Cherebetiu, Gabriel; Cortés, Othniel; Almaraz, Alejandro; Mendoza, Pedro; Silva, Jesús; Tirado, Enrique; Martínez, Leonel

    The aim of this paper is to compare the state of Cardiac Rehabilitation Programs (CRP) in 2009 with 2015. Focus is directed on health care, training of health-providers, research, and the barriers to their implementation. All authors of RENAPREC-2009, and other cardiac rehabilitation leaders in Mexico were requested to participate. These centres were distributed into two groups: RENAPREC-2009 centres that participated in 2015, and the new CRP units. In 2009 there were 14 centres, two of which disappeared and another two did not respond. CRP-units increased by 71% (n=24), and their geographic distribution shows a centripetal pattern. The coverage of CRP-units was 0.02 centres per 100,000 inhabitants. Only 4.4% of eligible patients were referred to CRP, with a rate of 10.4 patients/100,000 inhabitants in 2015. The ratio of Clinical Cardiologists to Cardiac Rehabilitation Specialists was 94:1, and the ratio of Intervention Specialists to cardiac rehabilitation experts was 16:1. Cardiac rehabilitation activities and costs varied widely. Patient dropout rate in phase II was 12%. Several barriers were identified: financial crisis (83%), lack of skilled personnel (67%), deficient equipment (46%), inadequate areas (42%), and a reduced number of operating centres (38%). CRPs in Mexico are still in the process of maturing. Mexican CRP-centres have several strengths, like the quality of the education of the professionals and the multidisciplinary programs. However, the lack of referral of patients and the heterogeneity of procedures are still their main weaknesses. Copyright © 2016 Instituto Nacional de Cardiología Ignacio Chávez. Publicado por Masson Doyma México S.A. All rights reserved.

  16. 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.

  17. Analysis of Radionuclide Releases from the Fukushima Dai-ichi Nuclear Power Plant Accident Part II

    Science.gov (United States)

    Achim, Pascal; Monfort, Marguerite; Le Petit, Gilbert; Gross, Philippe; Douysset, Guilhem; Taffary, Thomas; Blanchard, Xavier; Moulin, Christophe

    2014-03-01

    The present part of the publication (Part II) deals with long range dispersion of radionuclides emitted into the atmosphere during the Fukushima Dai-ichi accident that occurred after the March 11, 2011 tsunami. The first part (Part I) is dedicated to the accident features relying on radionuclide detections performed by monitoring stations of the Comprehensive Nuclear Test Ban Treaty Organization network. In this study, the emissions of the three fission products Cs-137, I-131 and Xe-133 are investigated. Regarding Xe-133, the total release is estimated to be of the order of 6 × 1018 Bq emitted during the explosions of units 1, 2 and 3. The total source term estimated gives a fraction of core inventory of about 8 × 1018 Bq at the time of reactors shutdown. This result suggests that at least 80 % of the core inventory has been released into the atmosphere and indicates a broad meltdown of reactor cores. Total atmospheric releases of Cs-137 and I-131 aerosols are estimated to be 1016 and 1017 Bq, respectively. By neglecting gas/particulate conversion phenomena, the total release of I-131 (gas + aerosol) could be estimated to be 4 × 1017 Bq. Atmospheric transport simulations suggest that the main air emissions have occurred during the events of March 14, 2011 (UTC) and that no major release occurred after March 23. The radioactivity emitted into the atmosphere could represent 10 % of the Chernobyl accident releases for I-131 and Cs-137.

  18. 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

    For nuclear energy to remain sustainable in the United States, economically viable sources of uranium beyond terrestrial ores must be developed. The goal of this program is to develop advanced adsorbents that can extract uranium from seawater at twice the capacity of the best adsorbent developed by researchers at the Japan Atomic Energy Agency (JAEA), 1.5 mg U/g adsorbent. A multidisciplinary team from Oak Ridge National Laboratory, Lawrence Berkeley National Laboratory, Pacific Northwest National Laboratory, and the University of Texas at Austin was assembled to address this challenging problem. Polymeric adsorbents, based on the radiation grafting of acrylonitrile and methacrylic acid onto high surface-area polyethylene fibers followed by conversion of the nitriles to amidoximes, have been developed. These poly(acrylamidoxime-co-methacrylic acid) fibers showed uranium adsorption capacities for the extraction of uranium from seawater that exceed 3 mg U/g adsorbent in testing at the Pacific Northwest National Laboratory Marine Sciences Laboratory. The essence of this novel technology lies in the unique high surface-area trunk material that considerably increases the grafting yield of functional groups without compromising its mechanical properties. This technology received an R&D100 Award in 2012. In addition, high surface area nanomaterial adsorbents are under development with the goal of increasing uranium adsorption capacity by taking advantage of the high surface areas and tunable porosity of carbon-based nanomaterials. Simultaneously, de novo structure-based computational design methods are being used to design more selective and stable ligands and the most promising candidates are being synthesized, tested and evaluated for incorporation onto a support matrix. Fundamental thermodynamic and kinetic studies are being carried out to improve the adsorption efficiency, the selectivity of uranium over other metals, and the stability of the adsorbents. Understanding

  19. MAP kinase-signaling controls nuclear translocation of tripeptidyl-peptidase II in response to DNA damage and oxidative stress

    Energy Technology Data Exchange (ETDEWEB)

    Preta, Giulio; Klark, Rainier de; Chakraborti, Shankhamala [Center for Molecular Medicine (CMM), Department of Medicine, Karolinska Institutet, Karolinska University Hospital, 171 76 Stockholm (Sweden); Glas, Rickard, E-mail: rickard.glas@ki.se [Center for Molecular Medicine (CMM), Department of Medicine, Karolinska Institutet, Karolinska University Hospital, 171 76 Stockholm (Sweden)

    2010-08-27

    Research highlights: {yields} Nuclear translocation of TPPII occurs in response to different DNA damage inducers. {yields} Nuclear accumulation of TPPII is linked to ROS and anti-oxidant enzyme levels. {yields} MAPKs control nuclear accumulation of TPPII. {yields} Inhibited nuclear accumulation of TPPII decreases DNA damage-induced {gamma}-H2AX expression. -- Abstract: Reactive oxygen species (ROS) are a continuous hazard in eukaroytic cells by their ability to cause damage to biomolecules, in particular to DNA. Previous data indicated that the cytosolic serine peptidase tripeptidyl-peptidase II (TPPII) translocates into the nucleus of most tumor cell lines in response to {gamma}-irradiation and ROS production; an event that promoted p53 expression as well as caspase-activation. We here observed that nuclear translocation of TPPII was dependent on signaling by MAP kinases, including p38MAPK. Further, this was caused by several types of DNA-damaging drugs, a DNA cross-linker (cisplatinum), an inhibitor of topoisomerase II (etoposide), and to some extent also by nucleoside-analogues (5-fluorouracil, hydroxyurea). In the minority of tumor cell lines where TPPII was not translocated into the nucleus in response to DNA damage we observed reduced intracellular ROS levels, and the expression levels of redox defense systems were increased. Further, treatment with the ROS-inducer {gamma}-hexa-chloro-cyclohexane ({gamma}-HCH, lindane), an inhibitor of GAP junctions, restored nuclear translocation of TPPII in these cell lines upon {gamma}-irradiation. Moreover, blocking nuclear translocation of TPPII in etoposide-treated cells, by using a peptide-derived inhibitor (Z-Gly-Leu-Ala-OH), attenuated expression of {gamma}-H2AX in {gamma}-irradiated melanoma cells. Our results indicated a role for TPPII in MAPK-dependent DNA damage signaling.

  20. 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.

  1. 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.

  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. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. The phosphatidylserine receptor from Hydra is a nuclear protein with potential Fe(II dependent oxygenase activity

    Directory of Open Access Journals (Sweden)

    Stiening Beate

    2004-06-01

    Full Text Available Abstract Background Apoptotic cell death plays an essential part in embryogenesis, development and maintenance of tissue homeostasis in metazoan animals. The culmination of apoptosis in vivo is the phagocytosis of cellular corpses. One morphological characteristic of cells undergoing apoptosis is loss of plasma membrane phospholipid asymmetry and exposure of phosphatidylserine on the outer leaflet. Surface exposure of phosphatidylserine is recognised by a specific receptor (phosphatidylserine receptor, PSR and is required for phagocytosis of apoptotic cells by macrophages and fibroblasts. Results We have cloned the PSR receptor from Hydra in order to investigate its function in this early metazoan. Bioinformatic analysis of the Hydra PSR protein structure revealed the presence of three nuclear localisation signals, an AT-hook like DNA binding motif and a putative 2-oxoglutarate (2OG-and Fe(II-dependent oxygenase activity. All of these features are conserved from human PSR to Hydra PSR. Expression of GFP tagged Hydra PSR in hydra cells revealed clear nuclear localisation. Deletion of one of the three NLS sequences strongly diminished nuclear localisation of the protein. Membrane localisation was never detected. Conclusions Our results suggest that Hydra PSR is a nuclear 2-oxoglutarate (2OG-and Fe(II-dependent oxygenase. This is in contrast with the proposed function of Hydra PSR as a cell surface receptor involved in the recognition of apoptotic cells displaying phosphatidylserine on their surface. The conservation of the protein from Hydra to human infers that our results also apply to PSR from higher animals.

  11. Titan II. Reliability and Aging Surveillance Program (RASP) Management Plan

    Science.gov (United States)

    1974-12-02

    IC. ISTIBUTON TATEE TApproved for Public Release; Distribution Unlimited II- SUPPLEMENTARY NOTES 112. SPONSORING MILITARY AC TIVITY ___________jN/A I...following organizations: SAC OGDEN ALC * LGBT *MMER XPQM *MMCO BM MMCP V DEFS MMCR DOKM MMCT DOTM MMEW ~- V -~ -DOXX S • ,. _ X PQ T * Indicates...age and service on the Titan II Weapon System. This responsibility includes publication and dissemina- tion of reports and information. CINCSAC/ LGBT

  12. 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.

  13. 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.

  14. 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

  15. 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

  16. Antimicrobial Exposure Assessment Task Force II (AEATF II) Volume 5: Governing Document for a Multi-Year Antimicrobial Chemical Exposure Monitoring Program (interim draft document with changes)

    Science.gov (United States)

    This document describes the overall scope of the AEATF II program, demonstrates the need for additional human exposure monitoring data and explains the proposed methodology for the exposure monitoring studies proposed for conduct by the AEATF II.

  17. Antimicrobial Exposure Assessment Task Force II (AEATF II) Volume 5: Governing Document for a Multi-Year Antimicrobial Chemical Exposure Monitoring Program (interim draft document)

    Science.gov (United States)

    Describes the overall scope of the AEATF II program, demonstrates the need for additional human exposure monitoring data and explains the proposed methodology for the exposure monitoring studies proposed for conduct by the AEATF II.

  18. TRIGA Mark II nuclear reactor facility. Final report, 1 July 1980--30 June 1995

    Energy Technology Data Exchange (ETDEWEB)

    Ryan, B.C.

    1997-05-01

    This report is a final culmination of activities funded through the Department of Energy`s (DOE) University Reactor Sharing Program, Grant DE-FG02-80ER10273, during the period 1 July 1980 through 30 June 1995. Progress reports have been periodically issued to the DOE, namely the Reactor Facility Annual Reports C00-2082/2219-7 through C00-2082/10723-21, which are contained as an appendix to this report. Due to the extent of time covered by this grant, summary tables are presented. Table 1 lists the fiscal year financial obligations of the grant. As listed in the original grant proposals, the DOE grant financed 70% of project costs, namely the total amount spent of these projects minus materials costs and technical support. Thus the bulk of funds was spent directly on reactor operations. With the exception of a few years, spending was in excess of the grant amount. As shown in Tables 2 and 3, the Reactor Sharing grant funded a immense number of research projects in nuclear engineering, geology, animal science, chemistry, anthropology, veterinary medicine, and many other fields. A list of these users is provided. Out of the average 3000 visitors per year, some groups participated in classes involving the reactor such as Boy Scout Merit Badge classes, teacher`s workshops, and summer internships. A large number of these projects met the requirements for the Reactor Sharing grant, but were funded by the University instead.

  19. The Argonne Radiological Impact Program (ARIP). Part II. MONITOR: A Program and Data Base for Retrieval and Utilization of Pollutant Monitoring Data

    Energy Technology Data Exchange (ETDEWEB)

    Eckerman, Keith F.; Stowe, Ralph F.; Frigerio, Norman A.

    1977-02-01

    The Argonne Radiological Impact Program (ARIP) is an ongoing project of the Laboratory's Division of Environmental Impact Studies that aims at developing methodologies for assessing the carcinogenic hazards associated with nuclear power development. The project's first report (ANL/ES-26, Part I), published in September.l973, discussed models of radiation carcinogenesis and the contribution of U .. S. background radiation levels to hazardous dose rates. The current report (Part II) treats the storage and access of available data on radiation and radioactivity levels in the u. S. A compute-r code. (the MONITOR program) is prf!sented, which can serve as a ready-access data. bank for all monitoring data acquired over the past two decades. The MONITOR program currently stores data on monitoring locations, types of monitoring efforts, and types of monitoring data. reported in Radiation Data and Reports by the various state and federal ne-tworks; expansion of this data base to include nuclear power facilities in operation or on order is ongoing ·. The MONITOR code retrieves information within a search radius, or rectangl.e ,. circumscribed by parameters of latitude and longitude, and l:.ists or maps the data_as: requested. The code, with examples, is given in full in the report ..

  20. 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

  1. 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.

  2. Organization and management of maintenance in the NPP's Asco and Vandellos II; Organizacion y gestion del mantenimiento en las centrales nucleares Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Folguera, M.; Corral, A.

    2014-04-01

    The article starts with a description of the international framework that, using technical instructions, guides and guidelines, regulates the maintenance of nuclear power plants. It also outlines the characteristics of the organization and management of maintenance in the NPP's operated by ANAV. Such management is supported in a variety of processes and programs among which are: work management, training and qualification, operational experience, supervision, foreign material exclusion, work management in RP areas and outage preparation. (Author)

  3. 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.

  4. 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.

  5. 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.

  6. 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).

  7. 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.

  8. 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.

  9. 1992 Resource Program, 10 Year Plan : Draft II.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1992-05-01

    The Resource Program is the Bonneville Power Administration's primary process for deciding how to meet future electricity resource needs, how much new resources to develop, which types of resources to acquire or option and how to go about acquiring them, and how much BPA will have to spend for these resources. Recognizing that BPA must make a long-term commitment to acquiring conservation effectively, the 1992 Resource Program outlines a 10-year plan. Draft 2 of the 1992 Resource Program provides a framework for discussing the funding levels proposed in the Programs in Perspective (PIP) process. Previous final resource programs have been released prior to the PIP process. This version of the Resource Program recognizes that the PIP discussions are an integral part of the resource decision-making process and, therefore, it will be finalized after PIP.

  10. 1992 Resource Program, 10 Year Plan : Draft II.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1992-05-01

    The Resource Program is the Bonneville Power Administration`s primary process for deciding how to meet future electricity resource needs, how much new resources to develop, which types of resources to acquire or option and how to go about acquiring them, and how much BPA will have to spend for these resources. Recognizing that BPA must make a long-term commitment to acquiring conservation effectively, the 1992 Resource Program outlines a 10-year plan. Draft 2 of the 1992 Resource Program provides a framework for discussing the funding levels proposed in the Programs in Perspective (PIP) process. Previous final resource programs have been released prior to the PIP process. This version of the Resource Program recognizes that the PIP discussions are an integral part of the resource decision-making process and, therefore, it will be finalized after PIP.

  11. 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.

  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. Nuclear dawn F. E. Simon and the race for atomic weapons in World War II

    CERN Document Server

    McRae, Kenneth D

    2014-01-01

    This book provides a rounded biography of Franz (later Sir Francis) Simon, his early life in Germany, his move to Oxford in 1933, and his experimental contributions to low temperature physics approximating absolute zero. After 1939 he switched his research to nuclear physics, and is credited with solving the problem of uranium isotope separation by gaseous diffusion for the British nuclear programme Tube Alloys. The volume is distinctive for its inclusion of source materials not available to previous researchers, such as Simon's diary and his correspondence with his wife, and for a fresh, well-informed insider voice on the five-power nuclear rivalry of the war years. The work also draws on a relatively mature nuclear literature to attempt a comparison and evaluation of the five nuclear rivals in wider political and military context, and to identify the factors, or groups of factors, that can explain the results.

  14. Endoplasmic reticulum and oxidant stress mediate nuclear factor-κB activation in the subfornical organ during angiotensin II hypertension.

    Science.gov (United States)

    Young, Colin N; Li, Anfei; Dong, Frederick N; Horwath, Julie A; Clark, Catharine G; Davisson, Robin L

    2015-05-15

    Endoplasmic reticulum (ER) stress and reactive oxygen species (ROS) generation in the brain circumventricular subfornical organ (SFO) mediate the central hypertensive actions of Angiotensin II (ANG II). However, the downstream signaling events remain unclear. Here we tested the hypothesis that angiotensin type 1a receptors (AT1aR), ER stress, and ROS induce activation of the transcription factor nuclear factor-κB (NF-κB) during ANG II-dependent hypertension. To spatiotemporally track NF-κB activity in the SFO throughout the development of ANG II-dependent hypertension, we used SFO-targeted adenoviral delivery and longitudinal bioluminescence imaging in mice. During low-dose infusion of ANG II, bioluminescence imaging revealed a prehypertensive surge in NF-κB activity in the SFO at a time point prior to a significant rise in arterial blood pressure. SFO-targeted ablation of AT1aR, inhibition of ER stress, or adenoviral scavenging of ROS in the SFO prevented the ANG II-induced increase in SFO NF-κB. These findings highlight the utility of bioluminescence imaging to longitudinally track transcription factor activation during the development of ANG II-dependent hypertension and reveal an AT1aR-, ER stress-, and ROS-dependent prehypertensive surge in NF-κB activity in the SFO. Furthermore, the increase in NF-κB activity before a rise in arterial blood pressure suggests a causal role for SFO NF-κB in the development of ANG II-dependent hypertension. Copyright © 2015 the American Physiological Society.

  15. 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)

  16. 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.

  17. 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.

  18. Modeling transducer impulse responses for predicting calibrated pressure pulses with the ultrasound simulation program Field II

    DEFF Research Database (Denmark)

    Bæk, David; Jensen, Jørgen Arendt; Willatzen, Morten

    2010-01-01

    FIELD II is a simulation software capable of predicting the field pressure in front of transducers having any complicated geometry. A calibrated prediction with this program is, however, dependent on an exact voltage-to-surface acceleration impulse response of the transducer. Such impulse response...... is not calculated by FIELD II. This work investigates the usability of combining a one-dimensional multilayer transducer modeling principle with the FIELD II software. Multilayer here refers to a transducer composed of several material layers. Measurements of pressure and current from Pz27 piezoceramic disks...... transducer model and the FIELD II software in combination give good agreement with measurements....

  19. 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

  20. 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.

  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.

    1991-01-01

    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.

  2. Management of Urban Construction Programs. Volume II : Supplemental Information

    Science.gov (United States)

    1981-06-01

    This report is part of a program sponsored by the Office of Rail and Construction Technology of the Urban Mass Transportation Administration. The overall objective of the study is to develop guidelines that can be used by local government authorities...

  3. Assessment of the basic energy sciences program. Volume II. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    1982-03-01

    A list of experts reviewing the Basic Energy Sciences (BES) program and their organizations are given. The assessment plan is explained; the program examined the following: quality of science being conducted in the program, quality of performers supported by the Basic Energy Sciences (BES) program, and the impact of the research on mission oriented needs. The intent of the assessment is to provide an indication of general status relative to these questions for the BES divisions. The approach to the assessment is described. The sampling plan which was used as a guide in determining the sample size and selecting the sample to evaluate the research program of the Office of Basic Energy Sciences are discussed. Special analyses were conducted on the dispersion of reviewers' ratings, the ratings of the lower funded projects, and the amount of time the principal investigator devoted to the project. These are presented in the final appendix together with histograms for individual rating variables for each program area. (MCW)

  4. 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.

  5. 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.

  6. 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.

  7. Cofilin Regulates Nuclear Architecture through a Myosin-II Dependent Mechanotransduction Module

    OpenAIRE

    Wiggan, O?Neil; Schroder, Bryce; Krapf, Diego; Bamburg, James R.; DeLuca, Jennifer G.

    2017-01-01

    Structural features of the nucleus including shape, size and deformability impact its function affecting normal cellular processes such as cell differentiation and pathological conditions such as tumor cell migration. Despite the fact that abnormal nuclear morphology has long been a defining characteristic for diseases such as cancer relatively little is known about the mechanisms that control normal nuclear architecture. Mounting evidence suggests close coupling between F-actin cytoskeletal ...

  8. 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.

  9. 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.

  10. 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...

  11. 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)

  12. 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.

  13. 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.

  14. 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

  15. Program Design Report of the CNC Machine Tool(II)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Kiun; Youm, K. U.; Kim, K. S.; Lee, I. B.; Yoon, K. B.; Lee, C. K.; Youm, J. H

    2007-06-15

    The application of CNC machine tool being widely expanded according to variety of machine work method and rapid promotion of machine tool, cutting tool, for high speed efficient machine work. In order to conduct of the project of manufacture and maintenance of laboratory equipment, production design and machine work technology are continually developed, especially the application of CNC machine tool is very important for the improvement of productivity, quality and clearing up a manpower shortage. We publish technical report which it includes CNC machine tool program and drawing, it contributes to the systematic development of CNC program design and machine work technology.

  16. Specification and verification of nuclear-power-plant training-simulator response characteristics. Part II. Conclusions and recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Haas, P M; Selby, D L; Kerlin, T W; Felkins, L

    1982-05-01

    The nuclear industry should adopt and NRC regulatory and research actions should support the systems approach to training as a structured framework for development and validation of personnel training systems. Potential exists for improving the ability to assess simulator fidelity. Systems Identification Technology offers a potential framework for model validation. Installation of the data collection/recording equipment required by NUREG-0696 could provide a vastly improved source of data for simulator fidelity assessment. The NRC needs to continue its post-TMI actions to involve itself more rigorously and more formally in the entire process of NPP personnel training system development. However, this involvement should be a participative one with industry. The existing similator standards and guidelines should be reorganized to support the use of systems approach to training. The standards should require and support a holistic approach to training system development that recognizes simulators and simulator training as only parts of the complete training program and full-scope, high-fidelity, site-specific simulators as only one useful training device. Some recommendations for adapting the SAT/ISD process to the nuclear industry are: The formation of an NRC/industry planning/coordination group, a program planning study to develop a programmatic plan, development of a user's guide and NRC/industry workshops to establish common terminology and practice, and a pilot study applying the adopted SAT/ISD methodology to an actual nuclear industry training program.

  17. 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.

  18. 40 CFR 147.2800 - State-administered program-Class I, II, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ... I, II, III, IV, and V wells. The UIC program for Class I, II, III, IV, and V wells in the... 40 Protection of Environment 22 2010-07-01 2010-07-01 false State-administered program-Class I, II, III, IV, and V wells. 147.2800 Section 147.2800 Protection of Environment ENVIRONMENTAL PROTECTION...

  19. China Public Budget Reform Program (CPBR) - Phase II | IDRC ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    The Government of China has adopted a national reform program aimed at making budgeting more transparent and accountable through public involvement and enhanced oversight. Building on work carried out under Phase I (102965), the China Development Research Foundation (CDRF) will analyze China's current ...

  20. China Public Budget Reform Program (CPBR) - Phase II | CRDI ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    The Government of China has adopted a national reform program aimed at making budgeting more transparent and accountable through public involvement and enhanced oversight. Building on work carried out under Phase I (102965), the China Development Research Foundation (CDRF) will analyze China's current ...

  1. 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...

  2. 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)

  3. 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.

  4. 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.

  5. 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.

  6. 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)

  7. Direct contact membrane distillation for nuclear desalination, Part II: experiments with radioactive solutions

    Energy Technology Data Exchange (ETDEWEB)

    Khayet, M. [Department of Applied Physics I, Faculty of Physics, University Complutense of Madrid, Madrid (Spain)]. E-mail: khayetm@fis.ucm.es; Mengual, J.I. [Department of Applied Physics I, Faculty of Physics, University Complutense of Madrid, Madrid (Spain)]. E-mail: mengual@fis.ucm.es; Zakrzewska-Trznadel, G. [Department of Nuclear Methods in Process Engineering, Institute of Nuclear Chemistry and Technology, Warsaw (Poland)]. E-mail: gzakrzew@orange.ichtj.waw.pl

    2006-07-01

    This paper proposes the application of Direct Contact Membrane Distillation (DCMD) coupled with a nuclear reactor for water desalination and for low- and medium-level radioactive liquid waste concentration. Both laboratory and pilot plant experiments were carried out using the membranes reviewed in Part I of this paper. The effects of process parameters on the productivity and quality of DCMD systems are discussed. Distilled water, non-active solutions of inorganic salts and solutions with admixtures of radionuclides and simulated and real radioactive waste samples were used as feed solutions. Employing DCMD for liquid low- and medium-level radioactive waste processing is an alternative to traditional methods used in nuclear technology. The combination of radioactive waste processing and water desalination creates an economical integrated system for water and wastewater management in nuclear power plants. (author)

  8. 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…

  9. 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.

  10. 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.

  11. Energy extension service pilot program evaluation report: the first year. Volume II: pilot state reports

    Energy Technology Data Exchange (ETDEWEB)

    1979-09-01

    Volume II of the Energy Extension Service Evaluation presents a discussion of the operations of the ten EES pilot-state programs during the period from October 1, 1977 through September 30, 1978. Each of the ten pilot states - Alabama, Connecticut, Michigan, New Mexico, Pennsylvania, Tennessee, Texas, Washington, Wisconsin, and Wyoming - received a grant of approximately $1.1 million to develop and implement a 19-month program beginning on October 1, 1977. Volume II provides a case-study description of the operations of the pilot program in each state, with special attention given to the two programs selected in each state for more detailed study and survey research. Some survey data and analysis are presented for the emphasis programs.

  12. Neutron measurements in the Vandellòs II nuclear power plant with a Bonner sphere system.

    Science.gov (United States)

    Fernández, F; Bakali, M; Tomás, M; Muller, H; Pochat, J L

    2004-01-01

    In some Spanish nuclear power plants of pressurised water reactor (PWR) type, albedo thermoluminescence dosemeters are used for personal dosimetry while survey meters, based on a thermal-neutron detector inside a cylindrical or spherical moderator, are used for dose rate assessment in routine monitoring. The response of both systems is highly dependent on the energy of the existing neutron fields. They are usually calibrated by means of ISO neutron sources with energy distributions quite different from those encountered at these installations. Spectrometric measurements with a Bonner sphere system (BSS) allow us to determine the reference dosimetric values. The UAB group, under request from the National Coordinated Research Action, was in charge of characterising the neutron fields and evaluating the response of personal dosemeters at several measurement points inside the containment building of the Catalan Nuclear Power Plant Vandellòs II. The neutron fields were characterised at five places using the UAB-BSS and a home made unfolding code called MITOM. The results obtained confirm the presence of low-energy components in the neutron field in most of the selected points. Moreover, we have found no influence of the nuclear fuel burning on the shape of the spectrum.

  13. Nuclear abnormalities in buccal mucosa cells of patients with type I and II diabetes treated with folic acid.

    Science.gov (United States)

    Gómez-Meda, B C; Zamora-Perez, A L; Muñoz-Magallanes, T; Sánchez-Parada, M G; García Bañuelos, J J; Guerrero-Velázquez, C; Sánchez-Orozco, L V; Vera-Cruz, J M; Armendáriz-Borunda, J; Zúñiga-González, G M

    2016-02-01

    Diabetes mellitus (DM) is characterized by high blood glucose. Excessive production of free radicals may cause oxidative damage to DNA and other molecules, leading to complications of the disease. It may be possible to delay or reduce such damage by administration of antioxidants such as folic acid (FA). The objective of this study was to determine the effect of FA on nuclear abnormalities (NAs) in the oral mucosa of patients with DM. NAs (micronucleated cells, binucleated cells, pyknotic nuclei, karyorrhexis, karyolysis, abnormally condensed chromatin, and nuclear buds) were analyzed in 2000 cells from 45 healthy individuals (control group) and 55 patients with controlled or uncontrolled type I or II DM; 35 patients in the latter group were treated with FA. Samples were taken from the FA group before and after treatment. An increased rate of NAs was found in patients with DM in comparison with that of the control group (Pabnormally condensed chromatin, karyolysis, and nuclear buds produced by FA supplementation in DM patients (P<0.02) are consistent with the idea that free radicals are responsible for the increased frequency of NAs in DM patients. Copyright © 2015 Elsevier B.V. All rights reserved.

  14. 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

  15. 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.

  16. '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.

  17. 40 CFR 147.1050 - State-administered program-Class I, II, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ... CONTROL PROGRAMS Maryland § 147.1050 State-administered program—Class I, II, III, IV, and V wells. The UIC program for Class I, II, III, IV, and V wells in the State of Maryland, except those wells on Indian lands... 40 Protection of Environment 22 2010-07-01 2010-07-01 false State-administered program-Class I, II...

  18. Health effects models for off-site radiological consequence analysis on nuclear reactor accidents (II)

    Energy Technology Data Exchange (ETDEWEB)

    Homma, Toshimitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Takahashi, Tomoyuki [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst; Yonehara, Hidenori [National Inst. of Radiological Sciences, Chiba (Japan)] [eds.

    2000-12-01

    This report is a revision of JAERI-M 91-005, 'Health Effects Models for Off-Site Radiological Consequence Analysis of Nuclear Reactor Accidents'. This revision provides a review of two revisions of NUREG/CR-4214 reports by the U.S. Nuclear Regulatory Commission which is the basis of the JAERI health effects models and other several recent reports that may impact the health effects models by international organizations. The major changes to the first version of the JAERI health effects models and the recommended parameters in this report are for late somatic effects. These changes reflect recent changes in cancer risk factors that have come from longer followup and revised dosimetry in major studies on the Japanese A-bomb survivors. This report also provides suggestions about future revisions of computational aspects on health effects models. (author)

  19. Nuclear medicine in diagnosis and treatment of diseases of the head and neck: II

    Energy Technology Data Exchange (ETDEWEB)

    Blahd, W.H.; Rose, J.G.

    The advent of both improved imaging systems and new radioactive agents has increased the effectiveness of nuclear medicine in diagnosing and treating diseases of the head and neck. In this second of two articles, researchers discuss radionuclide bone imaging and the role of nuclear medicine in the management of thyroid disease. Radionuclide bone imaging is useful in the differential diagnosis of sinusitis, the early detection of head and neck fracture, the assessment of temporomandibular joint disease, and the identification of local extension of primary head and neck carcinoma. In the management of thyroid disease, radionuclide technology is uniquely helpful in the diagnostic evaluation of the thyroid nodule and radioactive iodine continues to play a major role in thyroid cancer therapy.

  20. Analytical mass formula and nuclear surface properties in the ETF approximation. Part II: asymmetric nuclei

    Science.gov (United States)

    Aymard, François; Gulminelli, Francesca; Margueron, Jérôme

    2016-08-01

    We have recently addressed the problem of the determination of the nuclear surface energy for symmetric nuclei in the framework of the extended Thomas-Fermi (ETF) approximation using Skyrme functionals. We presently extend this formalism to the case of asymmetric nuclei and the question of the surface symmetry energy. We propose an approximate expression for the diffuseness and the surface energy. These quantities are analytically related to the parameters of the energy functional. In particular, the influence of the different equation of state parameters can be explicitly quantified. Detailed analyses of the different energy components (local/non-local, isoscalar/isovector, surface/curvature and higher order) are also performed. Our analytical solution of the ETF integral improves previous models and leads to a precision of better than 200 keV per nucleon in the determination of the nuclear binding energy for dripline nuclei.

  1. Treatment of non-nuclear attractors within the theory of atoms in molecules II: Energy decompositions

    Science.gov (United States)

    Alcoba, Diego R.; Lain, Luis; Torre, Alicia; Bochicchio, Roberto C.

    2006-08-01

    This work describes the partitioning of the electronic energy in systems in which the atoms in molecules theory predicts the existence of non-nuclear attractors. The procedure is based on our previous proposals within studies of topological population analysis [D.R. Alcoba, L. Lain, A. Torre, R.C. Bochicchio, Chem. Phys. Lett. 407 (2005) 379]. Numerical determinations in the acetylene and dilithium molecules are reported and compared with those arising from other approaches.

  2. Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Fellows, W.S.; Sharp, J.M.; Benator, B.I.

    1978-06-01

    A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis.

  3. 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

  4. Solar energy research and development: program balance. Annex, Volume II

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-02-01

    Each of the seven solar energy technologies that have been assessed in the study are treated: photovoltaic devices, solar thermal power systems, wind energy systems, solar heating and cooling systems, agricultural and industrial heat processes, biomass conversion technologies, and ocean thermal energy conversion systems. A brief technical overview of storage for solar electric technologies is presented and some principles concerning how different levels of success on electrical storage can affect the commercial viability of solar electric options are discussed. A description is given of the solar penetration model that was developed and applied as an analytical tool in the study. This computer model has served the primary purpose of evaluating the competiveness of the solar energy systems in the markets in which they are expected to compete relative to that of the alternative energy sources. This is done under a variety of energy supply, demand, and price conditions. The seven sections treating the solar energy technologies contain discussions on each of six subject areas: description of the technology; economic projections; the potential contribution of the technology in different marketplaces; environmental considerations; international potential; and the present and possible future emphases within the RD and D program. The priority item for each of the technology sections has been the documentation of the economic projections.

  5. 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.

  6. 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.

  7. 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).

  8. F-35 Lightning II Joint Strike Fighter (JSF) Program: Background, Status, and Issues

    National Research Council Canada - National Science Library

    Bolkcom, Christopher

    2009-01-01

    The Defense Department's F-35 Lightning II Joint Strike Fighter (JSF) is one of three aircraft modernization programs in tactical aviation, the others being the Air Force F-22A fighter and the Navy F/A-18E/F fighter/attack plane...

  9. F-35 Lightning II Joint Strike Fighter (JSF) Program: Background, Status, and Issues

    National Research Council Canada - National Science Library

    Bolkcom, Christopher; Murch, Anthony

    2008-01-01

    The Defense Department's F-35 Lightning II Joint Strike Fighter (JSF) is one of three aircraft modernization programs in tactical aviation, the others being the Air Force F-22A fighter and the Navy F/A-18E/F fighter/attack plane...

  10. F-35 Lightning II Joint Strike Fighter "JSF" Program: Background, Status, and Issues

    National Research Council Canada - National Science Library

    Murch, Anthony; Bolkcom, Christopher

    2007-01-01

    The Defense Department's F-35 Lightning II Joint Strike Fighter (JSF) is one of three aircraft modernization programs in tactical aviation, the others being the Air Force F-22A fighter and the Navy F/A-18E/F fighter/attack plane...

  11. Proceedings of the 1995 U.S. DOE hydrogen program review. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The 1995 US DOE Hydrogen Program Review was held April 18-21, 1995 in Coral Gables, FL. Volume II of the Proceedings contains 8 papers presented under the subject of hydrogen storage and 17 papers presented on hydrogen production. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  12. Multifragmentation of a very heavy nuclear system (II): bulk properties and spinodal decomposition

    CERN Document Server

    Frankland, J D; Bacri, C O; Bellaize, N; Bocage, F; Borderie, B; Bougault, R; Brou, R; Buchet, P; Chbihi, A; Chomaz, P; Colin, J; Colonna, M; Cussol, D; Dayras, R; Demeyer, A N; Doré, D; Durand, D; Galíchet, E; Genouin-Duhamel, E; Gerlic, E; Guarnera, A; Guinet, D; Lautesse, P; Laville, J L; Le Neindre, N; Lecolley, J F; Legrain, R; Louvel, M; Maskay, A M; Nalpas, L; Nguyen, A D; Plagnol, E; Pârlog, M; Rivet, M F; Rosato, E; Saint-Laurent, F; Salou, S; Squalli, M; Steckmeyer, J C; Tabacaru, G; Tamain, B; Tassan-Got, L; Tirel, O; Vient, E; Volant, C; Wieleczko, J P

    2001-01-01

    The properties of fragments and light charged particles emitted in multifragmentation of single sources formed in central 36 A MeV Gd+U collisions are reviewed. Most of the products are isotropically distributed in the reaction c.m. Fragment kinetic energies reveal the onset of radial collective energy. A bulk effect is experimentally evidenced from the similarity of the charge distribution with that from the lighter 32 A MeV Xe+Sn system. Spinodal decomposition of finite nuclear matter exhibits the same property in simulated central collisions for the two systems, and appears therefore as a possible mechanism at the origin of multifragmentation in this incident energy domain.

  13. Multifragmentation of a very heavy nuclear system (II): bulk properties and spinodal decomposition

    Energy Technology Data Exchange (ETDEWEB)

    Frankland, J.D. E-mail: frankland@ganil.fr; Borderie, B.; Colonna, M.; Rivet, M.F.; Bacri, Ch.O.; Chomaz, Ph.; Durand, D.; Guarnera, A.; Parlog, M.; Squalli, M.; Tabacaru, G.; Auger, G.; Bellaize, N.; Bocage, F.; Bougault, R.; Brou, R.; Buchet, P.; Chbihi, A.; Colin, J.; Cussol, D.; Dayras, R.; Demeyer, A.; Dore, D.; Galichet, E.; Genouin-Duhamel, E.; Gerlic, E.; Guinet, D.; Lautesse, P.; Laville, J.L.; Lecolley, J.F.; Legrain, R.; Le Neindre, N.; Lopez, O.; Louvel, M.; Maskay, A.M.; Nalpas, L.; Nguyen, A.D.; Plagnol, E.; Rosato, E.; Saint-Laurent, F.; Salou, S.; Steckmeyer, J.C.; Tamain, B.; Tassan-Got, L.; Tirel, O.; Vient, E.; Volant, C.; Wieleczko, J.P

    2001-07-02

    The properties of fragments and light charged particles emitted in multifragmentation of single sources formed in central 36 A MeV Gd+U collisions are reviewed. Most of the products are isotropically distributed in the reaction c.m. Fragment kinetic energies reveal the onset of radial collective energy. A bulk effect is experimentally evidenced from the similarity of the charge distribution with that from the lighter 32 A MeV Xe+Sn system. Spinodal decomposition of finite nuclear matter exhibits the same property in simulated central collisions for the two systems, and appears therefore as a possible mechanism at the origin of multifragmentation in this incident energy domain.

  14. 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

  15. 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.

  16. 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.

  17. 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

  18. 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

  19. Nuclear inelastic scattering study of a dinuclear iron(II) complex showing a direct spin transition

    Energy Technology Data Exchange (ETDEWEB)

    Wolny, J. A., E-mail: wolny@physik.uni-kl.de [University of Kaiserslautern, Department of Physics (Germany); Garcia, Y. [Université Catholique de Louvain, Institute of Condensed Matter and Nanosciences, Molecules, Solids and Reactivity (IMCN/MOST) (Belgium); Faus, I.; Rackwitz, S. [University of Kaiserslautern, Department of Physics (Germany); Schlage, K.; Wille, H.-C. [DESY (Germany); Schünemann, V. [University of Kaiserslautern, Department of Physics (Germany)

    2016-12-15

    The results of the nuclear inelastic scattering (NIS)/nuclear resonance vibrational spectroscopy (NRVS) for the powder spectra of dimeric [Fe {sub 2}L{sub 5}(NCS) {sub 4}] (L = N-salicylidene-4-amino-1,2,4-triazole) complex are presented. This system is spin crossover (SCO) material tagged with a fluorophore that can sense or “feel” the SCO signal ripping through the molecular network and thereby providing an opportunity to register the SCO transition. The spectra have been measured for the low-spin and high-spin phases of the complex. The high-spin isomer reveals one broad band above 200 cm {sup −1}, while the low-spin one displays two intense bands in the range from 390 to 430 cm {sup −1}, accompanied by a number of weaker bands below this area and one at ca. 490 cm {sup −1}. A normal coordinate analysis based on density functional calculations yields the assignment of the spin marker bands to particular molecular modes. In addition the vibrational contribution to the spin transition has been estimated.

  20. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M., E-mail: sarker_md@yahoo.co [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2010-03-15

    The aim of this study is to analyze the neutronic parameters of TRIGA Mark-II research reactor using the chain of NJOY-WIMS-CITATION computer codes based on evaluated nuclear data libraries CENDL-2.2 and JEFF-3.1.1. The nuclear data processing code NJOY99.0 has been employed to generate the 69 group WIMS library for the isotopes of TRIGA core. The cell code WIMSD-5B was used to generate the cross sections in CITATION format and then 3-dimensional diffusion code CITTATION was used to calculate the neutronic parameters of the TRIGA Mark-II research reactor. All the analyses were performed using the 7-group macroscopic cross section library. The CITATION test-runs using different cross section sets based on different models applied in WIMS calculations have shown a strong influence of those models on the final integral parameters. Some of the cells were specially treated with PRIZE options available in WIMSD-5B to take into account the fine structure of the flux gradient in the fuel-reflector interface region. It was observed that two basic parameters, the effective multiplication factor, k{sub eff} and the thermal neutron flux, were in good agreement among the calculated results with each other as well as the measured values. The maximum power densities at the hot spot were 1.0446E02 W/cc and 1.0426E02 W/cc for the libraries CENDL-2.2 and JEFF-3.1.1 respectively. The calculated total peaking factors 5.793 and 5.745 were compared to the original SAR value of 5.6325 as well as MCNP result. Consequently, this analysis will be helpful to enhance the neutronic calculations and also be used for the further thermal-hydraulics study of the TRIGA core.

  1. 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.

  2. Blast Noise Prediction. Volume II. BNOISE 3.2 Computer Program Description and Program Listing.

    Science.gov (United States)

    1981-03-01

    1 )l L 11C~uLf I iTI 1 Td 1 ’ :1 PIt ILfd Lk 1 IIl 1 ~~ it tLui IIICht’ 11 ild . 2 II!Cd Lih L ! iIiltc i\\i) M A( 11,il , l Iiil I!31 -1 1(, And -O...VI. Percentage Correction Factors Ine tajh)Ce I ,ted hBr -\\B(jIN arc under the conditions of standard percent/temperature inver- ,,on .i t:trs , hcse

  3. OR TEP-II: a FORTRAN Thermal-Ellipsoid Plot Program for crystal structure illustrations

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, C.K.

    1976-03-01

    A computer program is described for drawing crystal structure illustrations using a mechanical plotter. Ball-and-stick type illustrations of a quality suitable for publication are produced with either spheres or thermal-motion probability ellipsoids on the atomic sites. The program can produce stereoscopic pairs of illustrations which aid in the visualization of complex packing arrangements of atoms and thermal motion patterns. Interatomic distances, bond angles, and principal axes of thermal motion are also calculated to aid the structural study. The most recent version of the program, OR TEP-II, has a hidden-line-elimination feature to omit those portions of atoms or bonds behind other atoms or bonds.

  4. Proceedings of the first analysis meeting on JUPITER-II Program

    Energy Technology Data Exchange (ETDEWEB)

    Shiradata, Keisho; Yamamoto, Masaaki [comps.

    1984-12-31

    The JUPITER-II Program is the Joint Physics Large Heterogeneous Core Critical Experiments Program between the U.S. Department of Energy (US DOE) and PNC, Japan. The experiments began in May 1982 and ended in April 1984, as a part of the ZPPR-13 program. The ZPPR-13 is a series of critical assemblies designed to study the fundamental neutronic behavior of large, radially-heterogeneous LMFBR cores. This report describes the results of analysis of ZPPR-13A and preliminary analysis of ZPPR-13B, and some topics of recent activities in fast reactor physics.

  5. 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.

  6. 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.

  7. 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.

  8. 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)

  9. 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.

  10. Report of the Secretary of Defense Task Force on DoD Nuclear Weapons Management. Phase II: Review of the DoD Nuclear Mission

    National Research Council Canada - National Science Library

    Schlesinger, James R; Carns, Michael P; Crouch, II, J. D; Gansler, Jacques S; Giambastiani, Jr., Edmund P; Hamre, John J; Miller, Franklin C; Williams, Christopher A; Blackwell, Jr, James A

    2008-01-01

    Incidents related to the Air Force's mishandling of nuclear weapons and components led to the creation of the Task Force in June 2008 to provide advice on nuclear matters for the Secretary of Defense...

  11. 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.

  12. 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.

  13. 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)

  14. Mn(II) complexes of different nuclearity: synthesis, characterization and catecholase-like activity.

    Science.gov (United States)

    Chakraborty, Prateeti; Majumder, Ishani; Banu, Kazi Sabnam; Ghosh, Bipinbihari; Kara, Hulya; Zangrando, Ennio; Das, Debasis

    2016-01-14

    Two "end-off" compartmental ligands, 2-formyl-4-chloro-6-N-ethylmorpholine-iminomethyl-phenol (HL1) and 2-formyl-4-methyl-6-N-ethylpyrrolidine-iminomethyl-phenol (HL2) have been designed and three complexes of Mn(ii), one mono-, one di- and a polynuclear, namely Mn(L1)(SCN)2(H2O)] (), [Mn2(L1)(OAc)2](BPh4)] (), and [Mn2(L2)(OAc)2(dca)]n () have been synthesized and structurally characterized. Variable temperature magnetic studies of and have been performed and data analyses reveal that Mn centers are antiferromagnetic coupled with J = -9.15 cm(-1) and J = -46.89, respectively. Catecholase activity of all the complexes has been investigated using 3,5-di-tert-butyl catechol (3,5-DTBC). All are highly active and the activity order on the basis of the kcat value is > > . In order to unveil whether the metal centered redox participation or the radical pathway is responsible for the catecholase-like activity of the complexes, detailed EPR and cyclic voltammetric (CV) studies have been performed. In addition to the six-line EPR spectrum characteristic to Mn(ii), an additional peak at g ∼ 2 is observed when the EPR study is done with the mixture of 3,5-DTBC and the catalyst, suggesting the formation of an organic radical, most likely ligand centered. The CV experiment with the mixture of 3,5-DTBC and the catalyst reveals ligand centered reduction rather than reduction of Mn(ii) to Mn(i). It is thus inferred that complexes show catecholase-like activity due to radical generation.

  15. Natural-abundance 13C nuclear-magnetic-resonance study of toxin II from Anemonia sulcata.

    Science.gov (United States)

    Norton, R S; Zwick, J; Béress, L

    1980-12-01

    Natural-abundance 13C NMR spectra (at 15.04 MHz) of the polypeptide toxin II from the sea anemone Anemonia sulcata have been analysed and compared with corresponding spectra reported recently for a closely related polypeptide anthopleurin A. The spectra contain many resolved one-carbon and two-carbon resonances from carbonyl, aromatic and methyl carbons, many of which have been assigned to individual carbons in the molecule on the basis of their chemical shifts, including their pH dependence, and by comparison with the 13C NMR spectrum of anthopleurin A. Analysis of the effects of pH on the spectrum yields estimates for the pKa values of a number of functional groups in the molecule, as follows: side-chain carboxylates of the two aspartic acid residues 2 and 3.1; COOH-terminal carboxylic acid, 3.5; imidazolium moieties of the two histidine residues, 6.7 and 7.6 NH2-terminal ammonium, 8. The similarity between the pKa values of these functional groups in toxin II and those of corresponding groups in anthopleurin A, together with the close agreement between chemical shifts of conserved carbons, indicates that many local interactions are nearly identical in the two molecules, and thus supports the thesis that their overall conformations in solution are similar. However, the local interactions involving one of the aspartic acid residues are altered in toxin II. Together with other data, this leads to a proposal for the site in these two molecules which is responsible for their cardiac stimulatory activity.

  16. GTP-dependent binding and nuclear transport of RNA polymerase II by Npa3 protein

    DEFF Research Database (Denmark)

    Staresincic, Lidija; Walker, Jane; Dirac-Svejstrup, A Barbara

    2011-01-01

    -dependent Npa3 depletion resulted in genome-wide transcription decreases, correlating with a loss of RNAPII from genes as measured by chromatin immunoprecipitation. Surprisingly, however, transcription in vitro was unaffected by Npa3, suggesting that it affects a process that is not required for transcription......We identified XAB1 in a proteomic screen for factors that interact with human RNA polymerase II (RNAPII). Because XAB1 has a conserved Saccharomyces cerevisiae homologue called Npa3, yeast genetics and biochemical analysis were used to dissect the significance of the interaction. Degron...

  17. Multifragmentation of a very heavy nuclear system (II): bulk properties and spinodal decomposition

    Energy Technology Data Exchange (ETDEWEB)

    Frankland, J.D.; Rivet, M.F.; Borderie, B. [Paris-11 Univ., Inst. de Physique Nucleaire, 91 - Orsay (France)] [and others

    2000-07-01

    The properties of fragments and light charged particles emitted in multifragmentation of single sources formed in central 36 A.MeV Gd+U collisions are reviewed. Most of the products are isotropically distributed in the reaction c.m. Fragment kinetic energies reveal the onset of radial collective energy. A bulk effect is experimentally evidenced from the similarity of the charge distribution with that from the lighter 32 A.MeV Xe+Sn system. Spinodal decomposition of finite nuclear matter exhibits the same property in simulated central collisions for the two systems, and appears therefore as a possible mechanism at the origin of multifragmentation in this incident energy domain. (authors)

  18. 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.

  19. 40 CFR 147.2650 - State-administered program-Class I, II, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ... CONTROL PROGRAMS Puerto Rico § 147.2650 State-administered program—Class I, II, III, IV, and V wells. The... 40 Protection of Environment 22 2010-07-01 2010-07-01 false State-administered program-Class I, II, III, IV, and V wells. 147.2650 Section 147.2650 Protection of Environment ENVIRONMENTAL PROTECTION...

  20. 40 CFR 147.2000 - State-administered program-Class I, II, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ... CONTROL PROGRAMS Rhode Island § 147.2000 State-administered program—Class I, II, III, IV, and V wells. The... 40 Protection of Environment 22 2010-07-01 2010-07-01 false State-administered program-Class I, II, III, IV, and V wells. 147.2000 Section 147.2000 Protection of Environment ENVIRONMENTAL PROTECTION...

  1. Pengembangan Asesmen Kinerja Untuk Penilaian Mahasiswa Pada Praktikum Fisika Dasar II Program Studi Pendidikan Fisika Universitas Muhammadiyah Makassar

    OpenAIRE

    Pertiwi, Erna Fitriani

    2016-01-01

    Telah dilakukan penelitian pengembangan yang bertujuan (1) mengembangkan asesmen kinerja untuk penilaian mahasiswa pada praktikum Fisika Dasar II Program Studi Pendidikan Fisika Universitas Muhammadiyah Makassar, (2) mendeskripsikan tentang profil asesmen kinerja untuk penilaian mahasiswa pada praktikum Fisika Dasar II Program Studi Pendidikan Fisika Universitas Muhammadiyah Makassar. Asesmen kinerja dikembangkan menggunakan model pengembangan four-D (4-D) yang terdiri dari tahap pendefinisia...

  2. 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.

  3. 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

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. Radiation effects in concrete for nuclear power plants, Part II: Perspective from micromechanical modeling

    Energy Technology Data Exchange (ETDEWEB)

    Le Pape, Y., E-mail: lepapeym@ornl.gov; Field, K.G.; Remec, I.

    2015-02-15

    Highlights: • A micromechanical model for irradiated concrete is proposed. • Confrontation with literature data is successful. • Neutron radiation-induced volumetric expansion is a predominant degradation mode. • The nature of the aggregate alters the severity of damage to irradiated concrete. - Abstract: The need to understand and characterize the effects of neutron irradiation on concrete has become urgent because of the possible extension of service life of many nuclear power generating stations. Current knowledge is primarily based on a collection of data obtained in test reactors. These data are inherently difficult to interpret because materials and testing conditions are inconsistent. A micromechanical approach based on the Hashin composite sphere model is presented to derive a first-order separation of the effects of radiation on cement paste and aggregate, and, also, on their interaction. Although the scarcity of available data limits the validation of the model, it appears that, without negating a possible gamma-ray induced effect, the neutron-induced damage and swelling of aggregate plays a predominant role on the overall concrete expansion and the damage of the cement paste. The radiation-induced volumetric expansion (RIVE) effects can also be aided by temperature elevation and shrinkage in the cement paste.

  12. Dynamics of asymmetric binary glass formers. II. Results from nuclear magnetic resonance spectroscopy.

    Science.gov (United States)

    Bock, D; Kahlau, R; Pötzschner, B; Körber, T; Wagner, E; Rössler, E A

    2014-03-07

    Various (2)H and (31)P nuclear magnetic resonance (NMR) spectroscopy techniques are applied to probe the component dynamics of the binary glass former tripropyl phosphate (TPP)/polystyrene-d3 (PS) over the full concentration range. The results are quantitatively compared to those of a dielectric spectroscopy (DS) study on the same system previously published [R. Kahlau, D. Bock, B. Schmidtke, and E. A. Rössler, J. Chem. Phys. 140, 044509 (2014)]. While the PS dynamics does not significantly change in the mixtures compared to that of neat PS, two fractions of TPP molecules are identified, one joining the glass transition of PS in the mixture (α1-process), the second reorienting isotropically (α2-process) even in the rigid matrix of PS, although at low concentration resembling a secondary process regarding its manifestation in the DS spectra. Pronounced dynamical heterogeneities are found for the TPP α2-process, showing up in extremely stretched, quasi-logarithmic stimulated echo decays. While the time window of NMR is insufficient for recording the full correlation functions, DS results, covering a larger dynamical range, provide a satisfactory interpolation of the NMR data. Two-dimensional (31)P NMR spectra prove exchange within the broadly distributed α2-process. As demonstrated by (2)H NMR, the PS matrix reflects the faster α2-process of TPP by performing a spatially highly hindered motion on the same timescale.

  13. The European Research on Severe Accidents in Generation-II and -III Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Jean-Pierre Van Dorsselaere

    2012-01-01

    Full Text Available Forty-three organisations from 22 countries network their capacities of research in SARNET (Severe Accident Research NETwork of excellence to resolve the most important remaining uncertainties and safety issues on severe accidents in existing and future water-cooled nuclear power plants (NPP. After a first project in the 6th Framework Programme (FP6 of the European Commission, the SARNET2 project, coordinated by IRSN, started in April 2009 for 4 years in the FP7 frame. After 2,5 years, some main outcomes of joint research (modelling and experiments by the network members on the highest priority issues are presented: in-vessel degraded core coolability, molten-corium-concrete-interaction, containment phenomena (water spray, hydrogen combustion…, source term issues (mainly iodine behaviour. The ASTEC integral computer code, jointly developed by IRSN and GRS to predict the NPP SA behaviour, capitalizes in terms of models the knowledge produced in the network: a few validation results are presented. For dissemination of knowledge, an educational 1-week course was organized for young researchers or students in January 2011, and a two-day course is planned mid-2012 for senior staff. Mobility of young researchers or students between the European partners is being promoted. The ERMSAR conference is becoming the major worldwide conference on SA research.

  14. Design of sample carrier for neutron irradiation facility at TRIGA MARK II nuclear reactor

    Science.gov (United States)

    Abdullah, Y.; Hamid, N. A.; Mansor, M. A.; Ahmad, M. H. A. R. M.; Yusof, M. R.; Yazid, H.; Mohamed, A. A.

    2013-06-01

    The objective of this work is to design a sample carrier for neutron irradiation experiment at beam ports of research nuclear reactor, the Reaktor TRIGA PUSPATI (RTP). The sample carrier was designed so that irradiation experiment can be performed safely by researchers. This development will resolve the transferring of sample issues faced by the researchers at the facility when performing neutron irradiation studies. The function of sample carrier is to ensure the sample for the irradiation process can be transferred into and out from the beam port of the reactor safely and effectively. The design model used was House of Quality Method (HOQ) which is usually used for developing specifications for product and develop numerical target to work towards and determining how well we can meet up to the needs. The chosen sample carrier (product) consists of cylindrical casing shape with hydraulic cylinders transportation method. The sample placing can be done manually, locomotion was by wheel while shielding used was made of boron materials. The sample carrier design can shield thermal neutron during irradiation of sample so that only low fluencies fast neutron irradiates the sample.

  15. 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.

  16. 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.

  17. 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.

  18. Magnetochemistry of Model Complexes for the Water Oxidation Center of Photosystem II and High Nuclearity Manganese Complexes.

    Science.gov (United States)

    Tsai, Hui-Lien

    1995-01-01

    Several polynuclear oxo-bridged manganese compounds have been synthesized, and their structural, magnetic, and spectroscopic properties have been characterized. The tetranuclear complexes have been investigated as models of the manganese cluster in the water oxidation center of photosystem II. As the nuclearity increases, manganese complexes are no longer good model complexes. However, they exhibit interesting magnetic properties. Some have high spin ground states as a result of the spin frustration mechanism, or they show some quite unusual properties, such as relaxation behavior shown in superparamagnetic materials. The work described in this thesis focuses on characterizing the electronic structure of polynuclear manganese complexes that have from three to twelve manganese atoms. Of the complexes synthesized, (Mn_3 O(O_2C_2Cl _3)(HO_2CMe) _2(H_2O)) crystallizes in triclinic space group P1 and possesses asymmetric Mn_3 units and is a valence trapped Mn^{II}Mn^ {III}_2 complex. Variable temperature magnetic susceptibility studies have been performed for four trinuclear Mn complexes. The ground state is calculated to have S = 3/2 or S = 1/2 for rm Mn^ {II}Mn^{III}_2 complexes. The Mn^{III} _3 complexes have S = 0 ground state. By changing the ratio of the exchange interaction constant in a Mn_3O complex, it is possible to stabilize ground states with different total spin S _{T} for a rm Mn^{II}Mn^{III} _2 complex. The Mn_4 cubane complexes have been characterized to have an S = 9/2 ground state. Changing the mu_3-bridging ligand or the terminal ligand does not change the ground state of the cubane complexes. The cubane complexes show appreciable zero-field splitting thus have a large anisotropy energy. Because of this relaxation process be seen in theses molecules and shows an out-of-phase component in the AC susceptibility. Mn _8 and Mn_9 clusters show S = 11 and S = 3 ground state respectively. Neutral an reduced Mn_{12} complexes were also synthesized. All of

  19. 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)

  20. 40 CFR 147.650 - State-administrative program-Class I, II, III, IV, and V wells.

    Science.gov (United States)

    2010-07-01

    ... CONTROL PROGRAMS Idaho § 147.650 State-administrative program—Class I, II, III, IV, and V wells. The UIC program for Class I, II, III, IV, and V wells in the State of Idaho, other than those on Indian lands, is... 40 Protection of Environment 22 2010-07-01 2010-07-01 false State-administrative program-Class I...

  1. 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.

  2. 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.

  3. Transducer models in the ultrasound simulation program FIELD II and their accuracy

    DEFF Research Database (Denmark)

    Jensen, Jørgen Arendt; Bæk, David

    2010-01-01

    The FIELD II simulation program can be used for simulating any kind of linear ultrasound fields. The program is capable of describing multi-element transducers used with any kind of excitation, apodization, and focusing. The program has been widely used in both academia and by commercial ultrasound...... companies for investigation novel transducer geometries and advanced linear imaging schemes. The program models transducer geometries using a division of the transducer elements into either rectangles, triangles, or bounding lines. The precision of the simulation and the simulation time is intimately linked...... through the choice of the fundamental elements. The rectangular elements use a far-field approximation, whereas the two other methods use the full analytic solution, leading to a higher precision at the price of a slower simulation time. The talk will describe the different compromises and solutions...

  4. SCINFI II A program to calculate the standardization curve in liquid scintillation counting

    Energy Technology Data Exchange (ETDEWEB)

    Grau Carles, A.; Grau Malonda, A.

    1985-07-01

    A code, SCINFI II, written in BASIC, has been developed to compute the efficiency-quench standardization curve for any beta radionuclide. The free parameter method has been applied. The program requires the standardization curve for 3{sup H} and the polynomial or tabulated relating counting efficiency as figure of merit for both 3{sup H} and the problem radionuclide. The program is applied to the computation, of the counting efficiency for different values of quench when the problem is 14{sup C}. The results of four different computation methods are compared. (Author) 17 refs.

  5. A comprehensive system of cosinor treatment programs written for the Apple II microcomputer.

    Science.gov (United States)

    Vokac, M

    1984-01-01

    A comprehensive set of cosinor treatment programs has been written for an Apple II microcomputer. The system includes Single Cosinor, Mean (population) Cosinor and Serial Sections analyses as well as extensive graphics and file management. The package is integrated and used through a hierarchically ordered system of menus and choices. 48k memory and two disk drives are required, and both EPSON and SILENTYPE printers are supported.

  6. Ocean Thermal Energy Conversion (OTEC) test facilities study program. Final report. Volume II. Part A

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-17

    Results are presented of an 8-month study to develop alternative non-site-specific OTEC facilities/platform requirements for an integrated OTEC Test Program which may include land and floating test facilities. The document, Volume II - Appendixes is bound in three parts (A, B, and C) which together comprise a compendium of the most significant detailed data developed during the study. Part A contains definitions, baseline revisions, test plans, and energy utilization sections.

  7. 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.

  8. 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.

  9. DJ-1 Modulates Nuclear Erythroid 2-Related Factor-2-Mediated Protection in Human Primary Alveolar Type II Cells in Smokers.

    Science.gov (United States)

    Bahmed, Karim; Messier, Elise M; Zhou, Wenbo; Tuder, Rubin M; Freed, Curt R; Chu, Hong Wei; Kelsen, Steven G; Bowler, Russell P; Mason, Robert J; Kosmider, Beata

    2016-09-01

    Cigarette smoke (CS) is a main source of oxidative stress and a key risk factor for emphysema, which consists of alveolar wall destruction. Alveolar type (AT) II cells are in the gas exchange regions of the lung. We isolated primary ATII cells from deidentified organ donors whose lungs were not suitable for transplantation. We analyzed the cell injury obtained from nonsmokers, moderate smokers, and heavy smokers. DJ-1 protects cells from oxidative stress and induces nuclear erythroid 2-related factor-2 (Nrf2) expression, which activates the antioxidant defense system. In ATII cells isolated from moderate smokers, we found DJ-1 expression by RT-PCR, and Nrf2 and heme oxygenase (HO)-1 translocation by Western blotting and immunocytofluorescence. In ATII cells isolated from heavy smokers, we detected Nrf2 and HO-1 cytoplasmic localization. Moreover, we found high oxidative stress, as detected by 4-hydroxynonenal (4-HNE) (immunoblotting), inflammation by IL-8 and IL-6 levels by ELISA, and apoptosis by terminal deoxynucleotidyl transferase dUTP nick end labeling (TUNEL) assay in ATII cells obtained from heavy smokers. Furthermore, we detected early DJ-1 and late Nrf2 expression after ATII cell treatment with CS extract. We also overexpressed DJ-1 by adenovirus construct and found that this restored Nrf2 and HO-1 expression and induced nuclear translocation in heavy smokers. Moreover, DJ-1 overexpression also decreased ATII cell apoptosis caused by CS extract in vitro. Our results indicate that DJ-1 activates the Nrf2-mediated antioxidant defense system. Furthermore, DJ-1 overexpression can restore the impaired Nrf2 pathway, leading to ATII cell protection in heavy smokers. This suggests a potential therapeutic strategy for targeting DJ-1 in CS-related lung diseases.

  10. Energy Extension Service Pilot Program: evaluation report after two years. Volume II. State reports

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-04-01

    This report, Vol. II, presents a discussion of the operations of the ten EES pilot state programs during the period from October 1, 1977 through September 30, 1979. Each of the ten pilot states - Alabama, Connecticut, Michigan, New Mexico, Pennsylvania, Tennessee, Texas, Washington, Wisconsin, and Wyoming - received a grant of approximately $1.1 million to develop and implement an 18-month program beginning on October 1, 1977. In September 1978, each State received an additional $370,000 for service-delivery programs for the extension of the pilot program, April 1979 through September 1979. A case-study description of the operations of the pilot program in each State is provided here, with special attention given to the two programs selected in each State for more-detailed study and survey research. Although the thrust of this volume is descriptive, some survey data and analyses are presented for the emphasis programs. Two telephone surveys of clients and a non-client sample were conducted, one at the end of the first year of the pilot program (October 1977 - September 1978) and one at the end of the second year (October 1978 - September 1979).

  11. Beznau II nuclear power plant: Expertise on NOK's request for the removal of the time limitation for the operation licence; KKW Beznau II: Gutachten zum Gesuch der NOK um Aufhebung der Befristung der Betriebsbewilligung

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-15

    The Federal Agency for the Safety of Nuclear Installations (HSK) is the Swiss authority responsible for nuclear safety and protection against radioactivity in nuclear power plants. It has to examine the request of the North-East Swiss Power Corporation (NOK) concerning the removal of the operational time limitation for the Beznau-II reactor (KKB-II). In the present report HSK reviews the enterprise management and the safety of KKB-II on the basis of the results of the Periodic Safety Review. The Beznau nuclear power plant exhibits a very high degree of technical and organisational safety. During the past 10 years the plant has been operated in a safe manner. At the same time the plant has been improved and this guarantees that the mechanisms of ageing degradation are systematically identified and that measures can be taken that are possibly necessary. Under such conditions, the safety of KKB-II can be guarantied at all times. As a result of the management of quality, environmental and working safety conditions, the correct application and the continuous improvement of all processes important to safety are ensured. With these measures KKB has shown that safety is given priority over and against all other working goals. The examination by HSK of the Periodic Safety Review has shown that, in the past, KKB has applied modernisation measures independent of the licensing situation of the two reactor blocks. These modernisation measures largely contribute to the fact that the HSK examination did not reveal any significant safety deficiencies. Other improvement measures allow risk reduction or can bee seen as an adaptation to experience gained and to the state of the technological art. In conclusion, HSK states that no safety-relevant facts have been found which could prevent the removal of the time limitation on the operational licence for KKB-II. From the point of view of HSK, KKB-II fulfils the conditions for the safe continuation of operation

  12. Contribution of the C-terminal regions of promyelocytic leukemia protein (PML) isoforms II and V to PML nuclear body formation.

    Science.gov (United States)

    Geng, Yunyun; Monajembashi, Shamci; Shao, Anwen; Cui, Di; He, Weiyong; Chen, Zhongzhou; Hemmerich, Peter; Tang, Jun

    2012-08-31

    Promyelocytic leukemia protein (PML) nuclear bodies are dynamic and heterogeneous nuclear protein complexes implicated in various important functions, most notably tumor suppression. PML is the structural component of PML nuclear bodies and has several nuclear splice isoforms that share a common N-terminal region but differ in their C termini. Previous studies have suggested that the coiled-coil motif within the N-terminal region is sufficient for PML nuclear body formation by mediating homo/multi-dimerization of PML molecules. However, it has not been investigated whether any of the C-terminal variants of PML may contribute to PML body assembly. Here we report that the unique C-terminal domains of PML-II and PML-V can target to PML-NBs independent of their N-terminal region. Strikingly, both domains can form nuclear bodies in the absence of endogenous PML. The C-terminal domain of PML-II interacts transiently with unknown binding sites at PML nuclear bodies, whereas the C-terminal domain of PML-V exhibits hyperstable binding to PML bodies via homo-dimerization. This strong interaction is mediated by a putative α-helix in the C terminus of PML-V. Moreover, nuclear bodies assembled from the C-terminal domain of PML-V also recruit additional PML body components, including Daxx and Sp100. These observations establish the C-terminal domain of PML-V as an additional important contributor to the assembly mechanism(s) of PML bodies.

  13. 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.

  14. 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.

  15. Nuclear Waste Management under Approaching Disaster: A Comparison of Decommissioning Strategies for the German Repository Asse II.

    Science.gov (United States)

    Ilg, Patrick; Gabbert, Silke; Weikard, Hans-Peter

    2017-07-01

    This article compares different strategies for handling low- and medium-level nuclear waste buried in a retired potassium mine in Germany (Asse II) that faces significant risk of uncontrollable brine intrusion and, hence, long-term groundwater contamination. We survey the policy process that has resulted in the identification of three possible so-called decommissioning options: complete backfilling, relocation of the waste to deeper levels in the mine, and retrieval. The selection of a decommissioning strategy must compare expected investment costs with expected social damage costs (economic, environmental, and health damage costs) caused by flooding and subsequent groundwater contamination. We apply a cost minimization approach that accounts for the uncertainty regarding the stability of the rock formation and the risk of an uncontrollable brine intrusion. Since economic and health impacts stretch out into the far future, we examine the impact of different discounting methods and rates. Due to parameter uncertainty, we conduct a sensitivity analysis concerning key assumptions. We find that retrieval, the currently preferred option by policymakers, has the lowest expected social damage costs for low discount rates. However, this advantage is overcompensated by higher expected investment costs. Considering all costs, backfilling is the best option for all discounting scenarios considered. © 2016 Society for Risk Analysis.

  16. Failure analysis of leakage on titanium tubes within heat exchangers in a nuclear power plant. Part II: Mechanical degradation

    Energy Technology Data Exchange (ETDEWEB)

    Gong, Y.; Yang, Z.G. [Department of Materials Science, Fudan University, Shanghai (China); Yuan, J.Z. [Third Qinshan Nuclear Power Co. Ltd., Haiyan, Zhejiang Province (China)

    2012-01-15

    Serious failure incidents like clogging, quick thinning, and leakage frequently occurred on lots of titanium tubes of heat exchangers in a nuclear power plant in China. In the Part I of the whole failure analysis study with totally two parts, factors mainly involving three kinds of electrochemical corrosions were investigated, including galvanic corrosion, crevice corrosion, and hydrogen-assisted corrosion. In the current Part II, through microscopically analyzing the ruptures on the leaked tubes by scanning electron microscopy (SEM) and energy dispersive spectrometry (EDS), another four causes dominantly lying in the aspect of mechanical degradation were determined - clogging, erosion, mechanical damaging, and fretting. Among them, the erosion effect was the primary one, thus the stresses it exerted on the tube wall were also supplementarily evaluated by finite element method (FEM). Based on the analysis results, the different degradation extents and morphologies by erosion on the tubes when they were clogged by different substances such as seashell, rubber debris, and sediments were compared, and relevant mechanisms were discussed. Finally, countermeasures were put forward as well. (Copyright copyright 2012 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  17. Germany-US Nuclear Theory Exchange Program for QCD Studies of Hadrons & Nuclei 'GAUSTEQ'

    Energy Technology Data Exchange (ETDEWEB)

    Dudek, Jozef [Old Dominion Univ., Norfolk, VA (United States); Melnitchouk, Wally [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States)

    2016-03-07

    GAUSTEQ was a Germany-U.S. exchange program in nuclear theory whose purpose was to focus research efforts on QCD studies of hadrons and nuclei, centered around the current and future research programs of Jefferson Lab and the Gesellschaft fur Schwerionenforschung (GSI) in Germany. GAUSTEQ provided travel support for theoretical physicists at US institutions conducting collaborative research with physicists in Germany. GSI (with its Darmstadt and Helmholtz Institute Mainz braches) served as the German “hub” for visits of U.S. physicists, while Jefferson Lab served as the corresponding “hub” for visits of German physicists visiting U.S. institutions through the reciprocal GUSTEHP (German-US Theory Exchange in Hadron Physics) program. GAUSTEQ was funded by the Office of Nuclear Physics of the U.S. Department of Energy, under Contract No.DE-SC0006758 and officially managed through Old Dominion University in Norfolk, Virginia. The program ran between 2011 and 2015.

  18. XOQDOQ: computer program for the meteorological evaluation of routine effluent releases at nuclear power stations. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Sagendorf, J.F.; Goll, J.T.; Sandusky, W.F.

    1982-09-01

    Provided is a user's guide for the US Nuclear Regulatory Commission's (NRC) computer program X0QDOQ which implements Regulatory Guide 1.111. This NUREG supercedes NUREG-0324 which was published as a draft in September 1977. This program is used by the NRC meteorology staff in their independent meteorological evaluation of routine or anticipated intermittent releases at nuclear power stations. It operates in a batch input mode and has various options a user may select. Relative atmospheric dispersion and deposition factors are computed for 22 specific distances out to 50 miles from the site for each directional sector. From these results, values for 10 distance segments are computed. The user may also select other locations for which atmospheric dispersion deposition factors are computed. Program features, including required input data and output results, are described. A program listing and test case data input and resulting output are provided.

  19. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-25

    Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), 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. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.

  20. Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1979-September 30, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1980-03-07

    The results of work performed from July 1, 1979 through September 30, 1979 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) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), 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 the activities associated with the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment. The status of the data management system is presented. In addition, the progress in the screening test program is described.

  1. Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, April 1, 1979-June 30, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-25

    The results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), 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 the activities associated with the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment. The status of the data management system is presented. In addition, the progress in the screening test program is described.

  2. Development of a 3-D Nuclear Event Visualization Program Using Unity

    Science.gov (United States)

    Kuhn, Victoria

    2017-09-01

    Simulations have become increasingly important for science and there is an increasing emphasis on the visualization of simulations within a Virtual Reality (VR) environment. Our group is exploring this capability as a visualization tool not just for those curious about science, but also for educational purposes for K-12 students. Using data collected in 3-D by a Time Projection Chamber (TPC), we are able to visualize nuclear and cosmic events. The Unity game engine was used to recreate the TPC to visualize these events and construct a VR application. The methods used to create these simulations will be presented along with an example of a simulation. I will also present on the development and testing of this program, which I carried out this past summer at MSU as part of an REU program. We used data from the S πRIT TPC, but the software can be applied to other 3-D detectors. This work is supported by the U.S. Department of Energy under Grant Nos. DE-SC0014530, DE-NA0002923 and US NSF under Grant No. PHY-1565546.

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Rogers,E.; deBoer,G.; Crawford, C.; De Castro, K.; Landers, J.

    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." Gen. Eugene Habiger, a former "Assistant Secretary for Safeguards and Security" at the U.S. Department of Energy’s (DOE) nuclear-weapons complex and a former commander of U.S. strategic nuclear forces, has observed that "good security is 20% equipment and 80% people." Although eliminating the "human factor" is not possible, accounting for and mitigating the risk of the insider threat is an essential element in establishing an effective nuclear security culture. This paper will consider the organizational role in mitigating the risk associated with the malicious insider through monitoring and enhancing human reliability and motivation as well as enhancing the nuclear security culture.

  5. North Korea and Iran’s Nuclear Programs as Instability Factors in the New System of International Relations

    Science.gov (United States)

    2007-11-01

    that North Korea’s mission to increase its own offensive capabilities is overshadowed by the commercial objective to attract more potential buyers for...diplomatic compulsion ) failure. Apparently, this research will affect the future National Intelligence Council’s nuclear program evaluation of Iran, in

  6. Development and Operation of the nuclear technology program for improving the public acceptance by providing the right information

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Juwoon; Kang, Mincheol; Min, Sangky; Yi, Jongmin; Yi, Yunyoung

    2013-11-15

    This detailed assignment conducted to improve the communication efficiency through the operation of differentiated programs to accomplish 'Establishment of knowledge diffusion system for improvement of Nuclear understanding', which is the purpose of the general assignment. We developed the programs on each social opinion leader groups by providing the right information on nuclear(radiation) technology, and had a forum for providing the right information on each social groups. Also, Consisted the consultant group, which participates humanities and social sciences, civic group, science teachers, the press, national assembly workers. Technology PR was performed 4 times, which is 1 time more than the original plan of 4 times. In the theme of affection of radiation, we broadened the vision of various fields which enabled to approach in general for the PR program. We Induced a positive reaction from the participants in political areas which coexistent of uncertain expectation and difficult vision of nuclear and radiation, by sharing the development possibility in relation with potential values of radiation industry and other industries and delivering accurate information, not a fragmentary knowledge, but in general. We hope that this results will contribute to establishing the effective nuclear knowledge diffusion program system.

  7. Nuclear-Powered Artificial Heart Prototype System Development Program: Phase III. Quarterly progress report, October 1, 1976--December 31, 1976

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

    Technical progress and accomplishments on the active program tasks 49 through 62 on the development of a nuclear-powered artificial heart are reported. The tasks include waste heat rejection, systems studies, IVBM modification design, IVBM fabrication, IVBM performance testing, IVBM system life testing, field support, reliability and quality assurance, Mark I thermal insulation design, and Mark I thermal converter design. (TFD)

  8. Nuclear Medicine Program progress report for quarter ending September 30, 1991

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Srivastava, P.C.; Hasan, A.; Lambert, C.R.; Lambert, S.J.; Rice, D.E.

    1992-02-01

    Rat tissue distribution properties of ``IQNP,`` a new radioiodinated cholinergic-muscarinic receptor antagonist, are described. IQNP is the acronym for 1-azabicyclo[2.2.2]oct-3-yl {alpha}-hydroxy-{alpha}-phenyl-{alpha}(1-iodo-1-propen-3-yl) acetate, which is an analogue of the QNB muscarinic antagonist in which the p-iodophenyl moiety has been replaced with the 1-iodo-1-propen-3-yl moiety. The radioiodinated IQNP analogue is easier to prepare in much higher yields than QNB and is thus a candidate for the evaluation of muscarinic receptors by external imaging techniques. Studies in rats demonstrated that IQNP shows high uptake in those cerebral regions rich in muscarinic receptors QNB-treatment of rats either 1 h before (pre) or 2 h after (post) administration of radioiodinated IQNP resulted in significant displacement or blocking of cerebral specific IQNP uptake (% dose/gm) in the cortex and striatum. These studies demonstrate that IQNP has specificity for the cholinergic-muscarinic receptor and is a good candidate for further studies. Also during this period, several agents developed in the ORNL Nuclear Medicine Program were supplied to Medical Cooperative Programs for collaborative studies including the iodine-125-labeled BMIPP and DMIPP fatty acid analogues and the IPM antibody labeling agent. Tin-117m and gold-199 were produced in the ORNL High Flux Isotope Reactor (HFIR) and supplied to the OHER-supported program in the Medical Department at Brookhaven National Laboratory to aid in their research until the re-start of the High Flux Brookhaven Reactor.

  9. Nuclear Medicine Program progress report for quarter ending September 30, 1991

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Srivastava, P.C.; Hasan, A.; Lambert, C.R.; Lambert, S.J.; Rice, D.E.

    1992-02-01

    Rat tissue distribution properties of IQNP,'' a new radioiodinated cholinergic-muscarinic receptor antagonist, are described. IQNP is the acronym for 1-azabicyclo(2.2.2)oct-3-yl {alpha}-hydroxy-{alpha}-phenyl-{alpha}(1-iodo-1-propen-3-yl) acetate, which is an analogue of the QNB muscarinic antagonist in which the p-iodophenyl moiety has been replaced with the 1-iodo-1-propen-3-yl moiety. The radioiodinated IQNP analogue is easier to prepare in much higher yields than QNB and is thus a candidate for the evaluation of muscarinic receptors by external imaging techniques. Studies in rats demonstrated that IQNP shows high uptake in those cerebral regions rich in muscarinic receptors QNB-treatment of rats either 1 h before (pre) or 2 h after (post) administration of radioiodinated IQNP resulted in significant displacement or blocking of cerebral specific IQNP uptake (% dose/gm) in the cortex and striatum. These studies demonstrate that IQNP has specificity for the cholinergic-muscarinic receptor and is a good candidate for further studies. Also during this period, several agents developed in the ORNL Nuclear Medicine Program were supplied to Medical Cooperative Programs for collaborative studies including the iodine-125-labeled BMIPP and DMIPP fatty acid analogues and the IPM antibody labeling agent. Tin-117m and gold-199 were produced in the ORNL High Flux Isotope Reactor (HFIR) and supplied to the OHER-supported program in the Medical Department at Brookhaven National Laboratory to aid in their research until the re-start of the High Flux Brookhaven Reactor.

  10. 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

  11. Nuclear Systems Enhanced Performance Program, Maintenance Cycle Extension in Advanced Light Water Reactor Design

    Energy Technology Data Exchange (ETDEWEB)

    Professor Neill Todreas

    2001-10-01

    A renewed interest in new nuclear power generation in the US has spurred interest in developing advanced reactors with features which will address the public's concerns regarding nuclear generation. However, it is economic performance which will dictate whether any new orders for these plants will materialize. Economic performance is, to a great extent, improved by maximizing the time that the plant is on-line generating electricity relative to the time spent off-line conducting maintenance and refueling. Indeed, the strategy for the advanced light water reactor plant IRIS (International Reactor, Innovative and Secure) is to utilize an eight year operating cycle. This report describes a formalized strategy to address, during the design phase, the maintenance-related barriers to an extended operating cycle. The top-level objective of this investigation was to develop a methodology for injecting component and system maintainability issues into the reactor plant design process to overcome these barriers. A primary goal was to demonstrate the applicability and utility of the methodology in the context of the IRIS design. The first step in meeting the top-level objective was to determine the types of operating cycle length barriers that the IRIS design team is likely to face. Evaluation of previously identified regulatory and investment protection surveillance program barriers preventing a candidate operating PWR from achieving an extended (48 month) cycle was conducted in the context of the IRIS design. From this analysis, 54 known IRIS operating cycle length barriers were identified. The resolution methodology was applied to each of these barriers to generate design solution alternatives for consideration in the IRIS design. The methodology developed has been demonstrated to narrow the design space to feasible design solutions which enable a desired operating cycle length, yet is general enough to have broad applicability. Feedback from the IRIS design team

  12. DNA Radiation Environments Program Spring 1991 2-meter box experiments and analyses. [DEfense Nuclear Agency (DNA)

    Energy Technology Data Exchange (ETDEWEB)

    Santoro, R.T. (Oak Ridge National Lab., TN (United States)); Whitaker, S.Y. (Clark Atlanta Univ., GA (United States))

    1993-03-01

    This report summarizes the Spring 1991 2-m Box experiments that were performed at the Army Pulse Radiation Facility (APRF) at Aberdeen Proving Ground. These studies were sponsored by the Defense Nuclear Agency (DNA) under the Radiation Environments Program to obtain measured data for benchmarking the Adjoint Monte Carlo Code System, MASH, Version 1.0. The MASH code system was developed for the Department of Defense and NATO for calculating neutron and gamma-ray radiation fields and shielding protection factors for armored vehicles and military structures against nuclear weapon radiation. In the 2-m Box experiments, neutron and gamma-ray dose rates and reduction factors were measured in the free-field and as a function of position on an anthropomorphic phantom that was placed outside and inside a borated polyethylene lined steel-walled 2-m box. The data were acquired at a distance of 400-m from the APRF reactor. The purpose of these experiments was to measure the neutron and gamma-ray dose rates as a function of detector location on the phantom for cases when the phantom was in the free-field and inside of the box. Neutron measurements were made using a BD-100R bubble detector and gamma-ray measurements were made using thermoluminescent detectors (TLD). Calculated and measured data were compared in terms of the C/M ratio. The calculated and measured neutron and gamma-ray dose rates and reduction factors agreed on the average within the [plus minus]20% limits mandated by DNA and demonstrate the capability of the MASH code system in reproducing measured data in nominally shielded assemblies.

  13. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    Abdou, M.

    1984-10-01

    The Nuclear Fusion Issues chapter contains a comprehensive list of engineering issues for fusion reactor nuclear components. The list explicitly defines the uncertainties associated with the engineering option of a fusion reactor and addresses the potential consequences resulting from each issue. The next chapter identifies the fusion nuclear technology testing needs up to the engineering demonstration stage. (MOW)

  14. 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 D: Part A, Naval Spent Nuclear Fuel Management

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    Volume 1 to the Department of Energy`s Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Management Programs Environmental Impact Statement evaluates a range of alternatives for managing naval spent nuclear fuel expected to be removed from US Navy nuclear-powered vessels and prototype reactors through the year 2035. The Environmental Impact Statement (EIS) considers a range of alternatives for examining and storing naval spent nuclear fuel, including alternatives that terminate examination and involve storage close to the refueling or defueling site. The EIS covers the potential environmental impacts of each alternative, as well as cost impacts and impacts to the Naval Nuclear Propulsion Program mission. This Appendix covers aspects of the alternatives that involve managing naval spent nuclear fuel at four naval shipyards and the Naval Nuclear Propulsion Program Kesselring Site in West Milton, New York. This Appendix also covers the impacts of alternatives that involve examining naval spent nuclear fuel at the Expended Core Facility in Idaho and the potential impacts of constructing and operating an inspection facility at any of the Department of Energy (DOE) facilities considered in the EIS. This Appendix also considers the impacts of the alternative involving limited spent nuclear fuel examinations at Puget Sound Naval Shipyard. This Appendix does not address the impacts associated with storing naval spent nuclear fuel after it has been inspected and transferred to DOE facilities. These impacts are addressed in separate appendices for each DOE site.

  15. 77 FR 23228 - Notice of Submission for OMB Review; Small Business Innovation Research (SBIR) Program-Phase II...

    Science.gov (United States)

    2012-04-18

    ... Public Law 106-554, the ``Small Business Reauthorization Act of 2000, H.R. 5667'' enacted on December 21... Notice of Submission for OMB Review; Small Business Innovation Research (SBIR) Program--Phase II--Grant Application Package SUMMARY: This application package invites small business concerns to submit a Phase II...

  16. The relative influence of secondary versus primary prevention using the national cholesterol education program adult treatment panel II guidelines

    NARCIS (Netherlands)

    Goldman, L; Coxson, P; Hunink, MGM; Goldman, PA; Tosteson, ANA; Mittleman, M; Williams, L; Weinstein, MC

    OBJECTIVES This study was undertaken to project the population-wide effect of full implementation of the Adult Treatment Panel (ATP) II guidelines of the National Cholesterol Education Program (NCEP). BACKGROUND The ATP II has proposed guidelines for cholesterol reduction, but the long-term

  17. Graduate Research Assistant Program for Professional Development at Oak Ridge National Laboratory (ORNL) Global Nuclear Security Technology Division (GNSTD)

    Energy Technology Data Exchange (ETDEWEB)

    Eipeldauer, Mary D [ORNL; Shelander Jr, Bruce R [ORNL

    2012-01-01

    The southeast is a highly suitable environment for establishing a series of nuclear safety, security and safeguards 'professional development' courses. Oak Ridge National Laboratory (ORNL) provides expertise in the research component of these subjects while the Y-12 Nuclear Security Complex handles safeguards/security and safety applications. Several universities (i.e., University of Tennessee, Knoxville (UTK), North Carolina State University, University of Michigan, and Georgia Technology Institute) in the region, which offer nuclear engineering and public policy administration programs, and the Howard Baker Center for Public Policy make this an ideal environment for learning. More recently, the Institute for Nuclear Security (INS) was established between ORNL, Y-12, UTK and Oak Ridge Associate Universities (ORAU), with a focus on five principal areas. These areas include policy, law, and diplomacy; education and training; science and technology; operational and intelligence capability building; and real-world missions and applications. This is a new approach that includes professional development within the graduate research assistant program addressing global needs in nuclear security, safety and safeguards.

  18. Nuclear program of Iran. Towards de-escalation of a nuclear crisis. Advisory letter; Nucleair programma van Iran. Naar de-escalatie van een nucleaire crisis. Briefadvies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-04-15

    The Dutch government, partly at the request of the House of Representatives (Second Chamber), the AIV asked to give an opinion about the position of Iran in the region and the role of the nuclear program of Iran in the geopolitical relations, in view of the most recent developments [Dutch] De Nederlandse regering heeft, mede op verzoek van de Tweede Kamer der Staten-Generaal, de AIV gevraagd advies uit te brengen over de positie van Iran in de regio en de rol van het nucleaire programma van Iran in de geopolitieke verhoudingen hierin, mede gelet op de meest recente ontwikkelingen.

  19. Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, January 1, 1979-March 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-07-19

    This report presents the results of work performed from January 1, 1979 through March 31, 1979 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. Work covered in this report includes the activities associated with the creep-rupture testing of the test materials for the purpose of verifying the stresses selected for the screening creep test program, and the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment.

  20. Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, September 23, 1976--December 31, 1976

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    This report presents the results of work performed from September 23, 1976 through December 31, 1976 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. 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 affect 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.

  1. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, October 1, 1978--December 31, 1978

    Energy Technology Data Exchange (ETDEWEB)

    1979-03-09

    Results of work performed from October 1, 1978 through December 31, 1978 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program is presented. Objectives are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys, and selection of materials for future test facilities and more extensive qualification programs. The activities associated with the characterization of the materials for the screening test program, and the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment are included. The status of the data management system is presented.

  2. Temperature variation on the Mediterranean Sea by the exploitation of the Vandellos II Nuclear Power Plant; Variacion de temperatura en el mar mediterraneo por la explotacion de la C.N. de Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Villarreal Romero, M.; Ribes Hernandez, G.; Esparza Martin, J. L.

    2010-07-01

    The aim of this study is to verify the compliance with the Resolution of 7th February MAH/285/2007 Departament de Medi Ambient I Habitatge de la Generalitat de Catalunya establishing discharges limits to the Mediterranean Sea and, in particular, the section that references the thermal rise. The study area include about 1.5 km coastline, which is located in the vicinity of the Vandellos II Nuclear Power Plant.

  3. Applications of Nuclear Physics

    OpenAIRE

    Hayes, Anna C.

    2017-01-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that und...

  4. Ocean Thermal Energy Conversion (OTEC) test facilities study program. Final report. Volume II. Part C

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-01-17

    Results are presented of an 8-month study to develop alternative non-site-specific OTEC facilities/platform requirements for an integrated OTEC Test Program which may include land and floating test facilities. Volume II--Appendixes is bound in three parts (A, B, and C) which together comprise a compendium of the most significant detailed data developed during the study. Part C describes test facility support, data acquisition and control system design, cost data, energy self-sufficiency, and test facility applications.

  5. Launch Vehicle Ascent Trajectory Simulation Using the Program to Optimize Simulated Trajectories II (POST2)

    Science.gov (United States)

    Lugo, Rafael A.; Shidner, Jeremy D.; Powell, Richard W.; Marsh, Steven M.; Hoffman, James A.; Litton, Daniel K.; Schmitt, Terri L.

    2017-01-01

    The Program to Optimize Simulated Trajectories II (POST2) has been continuously developed for over 40 years and has been used in many flight and research projects. Recently, there has been an effort to improve the POST2 architecture by promoting modularity, flexibility, and ability to support multiple simultaneous projects. The purpose of this paper is to provide insight into the development of trajectory simulation in POST2 by describing methods and examples of various improved models for a launch vehicle liftoff and ascent.

  6. Rigid Polyurethane Foam (RPF) Technology for Countermines (Sea) Program Phase II

    Energy Technology Data Exchange (ETDEWEB)

    WOODFIN,RONALD L.; FAUCETT,DAVID L.; HANCE,BRADLEY G.; LATHAM,AMY E.; SCHMIDT,C.O.

    1999-10-01

    This Phase II report documents the results of one subtask initiated under the joint Department of Energy (DOE)/Department of Defense (DoD) Memorandum of Understanding (MOU) for Countermine Warfare. The development of Rigid Polyurethane Foams for neutralization of mines and barriers in amphibious assault was the objective of the tasking. This phase of the program concentrated on formation of RPF in water, explosive mine simulations, and development of foam and fabric pontoons. Field experimentation was done primarily at the Energetic Materials Research and Testing Center (EMRTC) of the New Mexico Institute of Mining and Technology, Socorro, NM between February 1996 and September 1998.

  7. Iran's growing nuclear weapons program: A catalyst for regional instability in the Middle East. Study project

    Energy Technology Data Exchange (ETDEWEB)

    Deyermond, J.J.

    1993-03-10

    Following the end of the Cold War, the United States as well as other nations around the world now find themselves in a state of political, economic, and military transition. While the US and other nations such as the Islamic Republic of Iran are undergoing significant increases in 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 East.

  8. The program at JPL to investigate the nuclear interaction of RTG's with scientific instruments on deep space probes

    Science.gov (United States)

    Truscello, V.

    1972-01-01

    A major concern in the integration of a radioisotope thermoelectric generator (RTG) with a spacecraft designed to explore the outer planets is the effect of the emitted radiation on the normal operation of scientific instruments. The necessary techniques and tools developed to allow accurate calculation of the neutron and gamma spectrum emanating from the RTG. The specific sources of radiation were identified and quantified. Monte Carlo techniques are then employed to perform the nuclear transport calculations. The results of these studies are presented. An extensive experimental program was initiated to measure the response of a number of scientific components to the nuclear radiation.

  9. 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

  10. Immunocytochemical study of estrogen receptor activation factor (E-RAF and the proteins that interact with nuclear estrogen receptor II (nER II in epithelial endometrial cells, in the presence and in the absence of estradiol

    Directory of Open Access Journals (Sweden)

    OM Echeverría

    2009-06-01

    Full Text Available The localization and abundance of the estrogen receptor activation factor (E-RAF and a small nuclear ribonucleoprotein (snRNP complex containing three proteins, p32, p55 and p60, which interact with the nuclear estrogen receptor II (nER II, have been studied in rat endometrial epithelial cells by means of immunofluorescence and high resolution quantitative immunocytochemistry. In the cytoplasm E-RAF is associated with the rough endoplasmic reticulum. In the nucleus it is mainly localized at the interchromatin space, and surrounding the clumps of compact or semi-condensed chromatin. Quantitative analyses show that the abundance of E-RAF in the nucleus increases after ovariectomy and decreases 3 minutes after estradiol administration. These results are in agreement with the currently available biochemical data. Double immunolocalizations demonstrate that p32, p55, p60 co-localize with other splicing-related protein. High resolution immunolocalization shows that p32, p55, p60 are associated with perichromatin fibrils (co-transcriptional splicing and with clusters of interchromatin granules (storage of splicing-related molecules. The nuclear abundance of the snRNP complex decreases with ovariectomy, increases within 3 minutes after estradiol administration and remains higher than that in ovariectomized animals for 27 minutes. These results strongly support the previous data on the role of nER-II in the regulation of mRNA transcription and its export from the nucleus to the cytoplasm.

  11. 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.

  12. Nuclear war and nuclear peace

    Energy Technology Data Exchange (ETDEWEB)

    Segal, G.; Moreton, E.; Freedman, L.; Baylis, J.

    1983-01-01

    This book is an in-depth examination of East-West tactical and strategic nuclear weapons policy. The contributors explore such issues as the history and implications of tactical weapons in Europe, the general conflicts that have characterized US and Soviet interaction, the development of British nuclear weapons policy, and arms control including SALT I and II and the START talks.

  13. 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.

  14. Chiral Nuclear Dynamics II

    CERN Document Server

    Rho, Mannque

    2008-01-01

    This is the sequel to the first volume to treat in one effective field theory framework the physics of strongly interacting matter under extreme conditions. This is vital for understanding the high temperature phenomena taking place in relativistic heavy ion collisions and in the early Universe, as well as the high-density matter predicted to be present in compact stars. The underlying thesis is that what governs hadronic properties in a heat bath and/or a dense medium is hidden local symmetry which emerges from chiral dynamics of light quark systems and from the duality between QCD in 4D and

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

    Energy Technology Data Exchange (ETDEWEB)

    1978-07-27

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

  16. FUSE Cycle 3 Program CO22: Chromospheric Activity in Population II Giants

    Science.gov (United States)

    Harper, Graham M.

    2004-01-01

    One of the mysteries of Population II giants is that they still show chromospheric emission despite their great age. The global dynamo which was active during their main-sequence lifetimes is expected to become extremely weak through magnetic rotational braking. The nature of the observed emission is not understood; although acoustic shock waves might provide the heating, acoustic waves are not predicted to drive the observed mass loss - which in turn requires the dissipation of magneto-hydrodynamic waves. This program was designed to search for the faint stellar H Ly(beta) emission wings and the fluorescent Fe II and H2 emission from one of the brightest, metal poor, Population II stars. These FUSE diagnostics, when combined with existing UV and optical spectra, help determine the major radiative cooling channels for the chromosphere. This observation was to complement that previously planned for the mildly metal deficient giant alpha Boo (K2 III). However, a Boo has yet to be observed with FUSE.

  17. Spent nuclear fuels project: FY 1995 multi-year program plan, WBS {number_sign}1.4

    Energy Technology Data Exchange (ETDEWEB)

    Denning, J.L.

    1994-09-01

    The mission of the Spent Nuclear Fuel (SNF) program is to safely, reliably, and efficiently manage, condition, transport, and store Department of Energy (DOE)-owned SNF, so that it meets acceptance criteria for disposal in a permanent repository. The Hanford Site Spent Nuclear Fuel strategic plan for accomplishing the project mission is: Establish near-term safe storage in the 105-K Basins; Complete national Environmental Policy Act (NEPA) process to obtain a decision on how and where spent nuclear fuel will be managed on the site; Define and establish alternative interim storage on site or transport off site to support implementation of the NEPA decision; and Define and establish a waste package qualified for final disposition. This report contains descriptions of the following: Work Breakdown Structure; WBS Dictionary; Responsibility Assignment Matrix; Program Logic Diagrams; Program Master Baseline Schedule; Program Performance Baseline Schedule; Milestone List; Milestone Description Sheets; Cost Baseline Summary by Year; Basis of Estimate; Waste Type Data; Planned Staffing; and Fiscal Year Work Plan.

  18. 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

  19. Tripartite Motif-Containing Protein 22 Interacts with Class II Transactivator and Orchestrates Its Recruitment in Nuclear Bodies Containing TRIM19/PML and Cyclin T1.

    Science.gov (United States)

    Forlani, Greta; Tosi, Giovanna; Turrini, Filippo; Poli, Guido; Vicenzi, Elisa; Accolla, Roberto S

    2017-01-01

    Among interferon (IFN) inducible antiviral factors both tripartite motif-containing protein 22 (TRIM22) and class II transactivator (CIITA) share the capacity of repressing human immunodeficiency virus type 1 (HIV-1) proviral transcription. TRIM22 is constitutively expressed in a subset of U937 cell clones poorly permissive to HIV-1 replication, whereas CIITA has been shown to inhibit virus multiplication in both T lymphocytic and myeloid cells, including poorly HIV-1 permissive U937 cells, by suppressing Tat-mediated transactivation of HIV-1 transcription. Therefore, we tested whether TRIM22 and CIITA could form a nuclear complex potentially endowed with HIV-1 repressive functions. Indeed, we observed that TRIM22, independent of its E3 ubiquitin ligase domain, interacts with CIITA and promotes its recruitment into nuclear bodies. Importantly, TRIM19/promyelocytic leukemia (PML) protein, another repressor of HIV-1 transcription also acting before proviral integration, colocalize in these nuclear bodies upon TRIM22 expression induced by IFN-γ. Finally, tTRIM22 nuclear bodies also contained CyclinT1, a crucial elongation factor of HIV-1 primary transcripts. These findings show that TRIM22 nuclear bodies are a site of recruitment of factors crucial for the regulation of HIV-1 transcription and highlight the potential existence of a concerted action between TRIM22, CIITA, and TRIM19/PML to maintain a state of proviral latency, at least in myeloid cells.

  20. Current status of the neutron application program at TRR-II

    Science.gov (United States)

    Huang, Yuhao

    2002-01-01

    This paper describes the current status of the neutron application program at the Taiwan Research Reactor-II (TRR-II) project. It has been more than two years since the project was officially approved in October 1998. In addition to the completion of the basic designs of the core, the core block, and the experimental facilities, some achievements related to the application promotion are also accomplished. In the past two years, the project team invited more than 50 foreign experts to TRR-II to discuss various design issues related to the reactor and experimental facilities. As a multi-purpose research reactor, its scope includes facilities such as fuel/material irradiation, isotope production, neutron activation analysis, neutron transmutation doping, cold neutron source and guides, and neutron spectrometers. A special task force was organized in the early stage to promote these applications, especially focused on the area of neutron scattering, which had not been well organized before. Up to now, the team has completed the preliminary market planning for general irradiation facilities, and the following are the major achievements for promotion of neutron scattering applications: Establish collaboration agreements with NIST (formal), ILL, and FRM-II for personnel training. Subcontract with domestic professors to promote neutron scattering related research in Taiwan. Co-Sponsor large-scale workshops and conferences (average two times per year). Invite foreign experts specialized in neutron scattering for mini-workshops or topical meetings (average 5-8 times per year). Discussion on establishing an independent “Neutron Application Research Center” to encourage the involvement of domestic professors and students.

  1. Technology Reinvestment Program/Advanced ``Zero Emission'' Control Valve (Phase II)

    Energy Technology Data Exchange (ETDEWEB)

    J. Napoleon

    1998-12-01

    The objectives of this effort are to determine, develop and demonstrate the feasibility of significantly reducing the cost and expanding the applications for a family of Advanced Zero Emissions Control Valves that meets the fugitive emissions requirements of the 1990 Amendments to the Clean Air Act. This program is a direct technology spin-off from the valve technology that is critical to the US Navy's Nuclear Powered Fleet. These zero emissions valves will allow the Hydrocarbon and Chemical Processing Industries, etc., to maintain their competitiveness and still meet environmental and safety requirements. Phase 2 is directed at refining the basic technologies developed during Phase 1 so that they can be more readily selected and utilized by the target market. In addition to various necessary certifications, the project will develop a full featured digital controller with ``smart valve'' growth capability, expanding valve sizes/applications and identifying valve materials to permit applications in severe operational environments.

  2. Massachusetts Beryllium Screening Program for Former Workers of Wyman-Gordon, Norton Abrasives, and MIT/Nuclear Metals

    Energy Technology Data Exchange (ETDEWEB)

    Pepper, L. D.

    2008-05-21

    The overall objective of this project was to provide medical screening to former workers of Wyman-Gordon Company, Norton Abrasives, and MIT/Nuclear Metals (NMI) in order to prevent and minimize the health impact of diseases caused by site related workplace exposures to beryllium. The program was developed in response to a request by the U.S. Department of Energy (DOE) that had been authorized by Congress in Section 3162 of the 1993 Defense Authorization Act, urging the DOE to carry out a program for the identification and ongoing evaluation of current and former DOE employees who are subjected to significant health risks during such employment." This program, funded by the DOE, was an amendment to the medical surveillance program for former DOE workers at the Nevada Test Site (NTS). This program's scope included workers who had worked for organizations that provided beryllium products or materials to the DOE as part of their nuclear weapons program. These organizations have been identified as Beryllium Vendors.

  3. Preparations for the start-up of a research program in nuclear safeguards at Chalmers - Stage 2

    Energy Technology Data Exchange (ETDEWEB)

    Kitamura, Yasunori; Pazsit, Imre

    2004-12-01

    This report gives an account of the work performed at the Dept. of Reactor Physics at Chalmers Univ. of Technology in the second stage of the preparations for the start-up of a research program in nuclear safeguards and nuclear material management. The program is aimed at utilizing the experimental facilities as well as the experience in reactor physics, criticality safety, signal processing and unfolding, and experimental nuclear techniques, in tackling problems in non-destructive assay (NDA) of nuclear materials. During the present project, the following three main subjects were dealt with: first tests and pilot measurements were performed with one of the two newly acquired {sup 252}Cf detectors that were obtained from JNC Japan; the second exercise of the ESARDA benchmark. which consisted of the evaluation of the pulse train generated by Los Alamos Laboratory for multiplicity counting was performed and reported to the organisers of the benchmark; the modified Monte-Carlo code MCNP-PoliMi was installed, tested and work started for generating (although outside the ESARDA benchmark), pulse train data as obtained from various neutron sources with or without the presence of fissile material, as detected with an Active Well Coincidence Counter.

  4. Nuclear Weapons: NNSA and DOD Need to More Effectively Manage the Stockpile Life Extension Program

    Science.gov (United States)

    2009-03-01

    Pantex Plant in Texas. The Y-12 plant manufactures critical nuclear components, such as parts made from enriched uranium, for the nuclear explosives...system for the W76 warhead. The Savannah River Site plant fills gas bottles it receives from Kansas City with tritium and deuterium , which are used to

  5. The Representation of Iran’s Nuclear Program in British Newspaper Editorials: A Critical Discourse Analytic Perspective

    Directory of Open Access Journals (Sweden)

    Mahmood Reza Atai

    2013-09-01

    Full Text Available In this study, Van Dijk’s (1998 model of CDA was utilized in order to examine the representation of Iran’s nuclear program in editorials published by British news casting companies. The analysis of the editorials was carried out at two levels of headlines and full text stories with regard to the linguistic features of lexical choices, nominalization, passivization, overcompleteness, and voice. The results support biased representation in media discourse, in this case Iran’s nuclear program. Likewise, the findings approve Bloor and Bloor (2007 ideological circles of Self (i.e., the West and Other (i.e., Iran or US and THEM in the media. The findings may be utilized to increase Critical Language Awareness (CLA among EFL teachers / students and can promise implications for ESP materials development and EAP courses for the students of journalism.

  6. 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.

  7. Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, July 1--September 30, 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-11-24

    Results of work performed from July 1, 1978 through September 30, 1978 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. Candidate alloys were evaluated for Very High Temperature Reactor Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the affect of simulated reactor primary coolant (Helium containing small amounts of various other gases), the high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. The activities associated with the characterization of the materials for the screening test program are reported, i.e., test specimen preparation, information from the materials characterization tests performed by General Electric, and the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment. The status of the data management system is presented.

  8. Department of Energy Nuclear Material Protection, Control, and Accounting Program at the Mangyshlak Atomic Energy Complex, Aktau, Republic of Kazakhstan

    Energy Technology Data Exchange (ETDEWEB)

    Case, R.; Berry, R.B.; Eras, A. [and others

    1998-08-01

    As part of the Cooperative Threat Reduction Nuclear Material Protection, Control, and Accounting (MPC and A) Program, the US Department of Energy and Mangyshlak Atomic Energy Complex (MAEC), Aktau, Republic of Kazakstan have cooperated to enhance existing MAEC MPC and A features at the BN-350 liquid-metal fast-breeder reactor. This paper describes the methodology of the enhancement activities and provides representative examples of the MPC and A augmentation implemented at the MAEC.

  9. 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).

  10. Battle Staff Training System II: Computer-Based Instruction Supporting the Force XXI Training Program

    National Research Council Canada - National Science Library

    Wampler, Richard

    1998-01-01

    This report documents the methodology and lessons learned in the development of the Innovative Tools and Techniques for Brigade and Below Staff Training II - Battle Staff Training System II (ITTBBST-BSTS II...

  11. 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.

  12. JUPITER-II Program: ANL analysis of ZPPR-13A and ZPPR-13B

    Energy Technology Data Exchange (ETDEWEB)

    Collins, P.J.; Brumbach, S.B. (comps.)

    1984-08-09

    The ZPPR-13 experiments provide basic physics data for radial-heterogeneous LMFBR cores of approximately 700 MWe size. Assemblies ZPPR-13A, ZPPR-13B and ZPPR-13C comprised the JUPITER-II cooperative program between US-DOE and PNC of Japan. The measurements were made between August 1982 and April 1984. This report describes in detail the results of the ANL analyses of phases 13A and 13B/1 and includes preliminary results for the later assemblies of phase 13B. The data were compiled primarily for discussions at the Third Jupiter Analysis Meeting to be held at ANL-West between September 11th and 14th, 1984.

  13. JUPITER-II Program: ANL analysis of ZPPR-13A and ZPPR-13B

    Energy Technology Data Exchange (ETDEWEB)

    Collins, P.J.; Brumbach, S.B. [comps.

    1984-08-01

    The ZPPR-13 experiments provide basic physics data for radial heterogeneous LMFBR cores of approximately 700MWe size. Assemblies ZPPR-13A, ZPPR-13B and ZPPR-13A comprised the JUPITER-II cooperative program between the U.S. Department of Energy (US DOE) and PNC of Japan. The measurements were made between August 1982 and April 1984. The core designs and the measurements were planned jointly by the two parties with substantial input from U.S. industrial interests to ensure coverage of the design requirements. This report describes in detail the results of the Argonne National Laboratory (ANL) analyses of phases 13A and 13B/1 and includes preliminary results for the later assemblies of phase 13B..

  14. Subseabed disposal program annual report, January-December 1980. Volume II. Appendices (principal investigator progress reports). Part 1

    Energy Technology Data Exchange (ETDEWEB)

    Hinga, K.R. (ed.)

    1981-07-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume I, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-Q; Part 2 contains Appendices R-MM. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base.

  15. Research on radionuclide migration under subsurface geochemical conditions. JAERI/AECL Phase II Collaborative Program Year 1 (joint research)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-01

    A radionuclide migration experiment program for fractured rocks was performed under the JAERI/AECL Phase-II Collaborative Program on research and development in radioactive waste management. The program started in the fiscal year 1993, as a five-year program consists of Quarried block radionuclide migration program, Speciation of long-lived radionuclides in groundwater, Isotopic hydrogeology and Groundwater flow model development. During the first year of the program (Program Year 1: March 18, 1994 - September 30, 1994), a plan was developed to take out granite blocks containing part of natural water-bearing fracture from the wall of the experimental gallery at the depth of 240 m, and literature reviews were done in the area of the speciation of long-lived radionuclides in groundwater, isotopic hydrogeology and the groundwater flow model development to proceed further work for the Program Year 2. (author)

  16. Integrated Data Collection Analysis (IDCA) Program - RDX Type II Class 5 Standard, Data Set 1

    Energy Technology Data Exchange (ETDEWEB)

    Sandstrom, Mary M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brown, Geoffrey W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Preston, Daniel N. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pollard, Colin J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Warner, Kirstin F. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Sorenson, Daniel N. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Remmers, Daniel L. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Moran, Jesse S. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Shelley, Timothy J. [Air Force Research Lab. (AFRL), Tyndall AFB, FL (United States); Reyes, Jose A. [Applied Research Associates, Inc., Tyndall AFB, FL (United States); Hsu, Peter C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Whipple, Richard E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, John G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2011-04-11

    This document describes the results of the first reference sample material—RDX Type II Class 5—examined in the proficiency study for small-scale safety and thermal (SSST) testing of explosive materials for the Integrated Data Collection Analysis (IDCA) Program. The IDCA program is conducting proficiency testing on homemade explosives (HMEs). The reference sample materials are being studied to establish the accuracy of traditional explosives safety testing for each performing laboratory. These results will be used for comparison to results from testing HMEs. This effort, funded by the Department of Homeland Security (DHS), ultimately will put the issues of safe handling of these materials in perspective with standard military explosives. The results of the study will add SSST testing results for a broad suite of different HMEs to the literature, potentially suggest new guidelines and methods for HME testing, and possibly establish what are the needed accuracies in SSST testing to develop safe handling practices. Described here are the results for impact, friction, electrostatic discharge, and scanning calorimetry analysis of a reference sample of RDX Type II Class 5. The results from each participating testing laboratory are compared using identical test material and preparation methods wherever possible. Note, however, the test procedures differ among the laboratories. These results are then compared to historical data from various sources. The performers involved are Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Air Force Research Laboratory/ RXQL (AFRL), Indian Head Division, Naval Surface Warfare Center, (IHD-NSWC), and Sandia National Laboratories (SNL). These tests are conducted as a proficiency study in order to establish some consistency in test protocols, procedures, and experiments and to understand how to compare results when test protocols are not identical.

  17. Comments on the future activities of the RERTR program - part II

    Energy Technology Data Exchange (ETDEWEB)

    Krull, W. [GKSS Research Centre Geesthacht GmbH (Germany)

    1997-08-01

    At the last RERTR meeting an historical overview was given and the status and consequences of enrichment reduction were discussed. At that time and somewhat more today many doubts are raised that enrichment reduction, as a tool for reducing the proliferation risk, is being done in the most efficient and convincing manner. The informations presented in this report were taken from IAEA, US-DOE, US-GAO publications and from proceedings of the RERTR meetings. The data presented should be compared only on a relative basis. It was not the intention for many reasons to present quantitative exact values as some figures used for developing the conclusions are being confidential. Others are available in the above mentioned publications and proceedings. But nevertheless conclusions drawn and recommendations developed are believed to be worth to be taken into account by research reactor operators, their funding organizations and administrators when they are faced with decisions about the future of their facilities. All of the international effort on reducing the enrichment on research and test reactors has their only justification from the INFCE (International Nuclear Fuel Cycle Evaluation) conclusions to reduce the proliferation risk worldwide to a large extent. Worldwide is important. IAEA and others have to convince operators and organizations upon the necessity in doing so. One of the best way convincing people is giving convincing examples. At present none of the nations having a military nuclear weapons program is giving such a convincing example. Even in cases where the qualified fuel and all other necessary tools for converting specific research reactors are existing only small or no progress can be seen. Only non-weapon states are being pressed today.

  18. Technology Roadmap Instrumentation, Control, and Human-Machine Interface to Support DOE Advanced Nuclear Energy Programs

    Energy Technology Data Exchange (ETDEWEB)

    Donald D Dudenhoeffer; Burce P Hallbert

    2007-03-01

    Instrumentation, Controls, and Human-Machine Interface (ICHMI) technologies are essential to ensuring delivery and effective operation of optimized advanced Generation IV (Gen IV) nuclear energy systems. In 1996, the Watts Bar I nuclear power plant in Tennessee was the last U.S. nuclear power plant to go on line. It was, in fact, built based on pre-1990 technology. Since this last U.S. nuclear power plant was designed, there have been major advances in the field of ICHMI systems. Computer technology employed in other industries has advanced dramatically, and computing systems are now replaced every few years as they become functionally obsolete. Functional obsolescence occurs when newer, more functional technology replaces or supersedes an existing technology, even though an existing technology may well be in working order.Although ICHMI architectures are comprised of much of the same technology, they have not been updated nearly as often in the nuclear power industry. For example, some newer Personal Digital Assistants (PDAs) or handheld computers may, in fact, have more functionality than the 1996 computer control system at the Watts Bar I plant. This illustrates the need to transition and upgrade current nuclear power plant ICHMI technologies.

  19. Development of Operation of Nuclear Technology Education Program for Mutual Technical Cooperation

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-12-15

    The objective of this project is to provide training opportunities to key personnel from developing countries in the field of nuclear technologies through which it would be possible to expand our nation's role as a technology donor and as a leading country in the international nuclear society. In addition, it is expected that this training course would be useful for building a foundation to enter the international markets of nuclear technology and related products. Through this project, it was possible to obtain the current status of the nuclear industries in the countries with which potential cooperation would be expected in the future. Inviting key manager groups from countries which are interested in technology transfer from other countries could provide them with an opportunity to experience our nation's nuclear industries and technologies. Specifically, this project could open with a seminar in Kazakhstan which has abundant natural resources including uranium. Through this visit, it was possible to enhance the cooperation between the two countries in nuclear technology, and it opened a way to cooperate in the support of the Kazakhstan medical radioisotope center and human resources development.

  20. A plan to qualify a Russian space nuclear reactor for launch by the United States

    Science.gov (United States)

    Polansky, G. F.; Schmidt, G. L.; Reynolds, E. L.; Schaefer, E. D.; Ogloblin, B.; Bocharov, A.

    1993-06-01

    A Nuclear Electric Propulsion Space Test Program (NEPSTP) is reviewed, and a Topaz II space nuclear power system is described. It is pointed out that the inherent difficulties of qualifying space reactors combined with the additional complications of employing Russian space hardware put challenges to the NEPSTP flight qualification program. The Topaz II hardware is designed to qualify the reactor to the U.S. MIL-STD-1540B requirements.

  1. Nociones de la programacion de lenguas extranjeras; Ensayo metodologico (II) (Notions on Programed Instruction in Foreign Languages; Methodological Essay II)

    Science.gov (United States)

    Feldman, David

    1975-01-01

    This paper discusses the prerequisites to programed language instruction, the role of the native language and the level of skill, and then explains materials and machines needed for such a program. Particular attention is given to phonetics. (Text is in Spanish.) (CK)

  2. 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.

  3. Nuclear Medicine Program progress report for quarter ending June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; Hsieh, B.T.; McPherson, D.W.; Mirzadeh, S.; Lambert, C.R.

    1993-07-01

    The ``IQNP`` agent is an antagonist for the cholinergic-muscarinic receptor. Since the IQNP molecule has two asymmetric centers and either cis or trans isomerism of the vinyl iodide, there are eight possible isomeric combinations. In this report, the systematic synthesis, purification and animal testing of several isomers of radioiodinated ``IQNP`` are reported. A dramatic and unexpected relation between the absolute configuration at the two asymmetric centers and the stereochemistry of the vinyl iodide on receptor specificity was observed. The E-(R)(R) isomer shows specific and significant localization (per cent dose/gram at 6 hours) in receptor-rich cerebral structures (i.e. Cortex = 1.38 + 0.31; Striatum = 1.22 + 0.20) and low uptake in tissues rich in the M{sub 2} subtype (Heart = 0.10; Cerebellum = 0.04). In contrast, the E-(R)(S) isomer shows very low receptor-specific uptake (Cortex = 0.04; Striatum = 0.02), demonstrating the importance of absolute configuration at the acetate center. An unexpected and important observation is that the stereochemistry of the vinyl iodine appears to affect receptor subtype specificity, since the Z-(R,S)(R) isomer shows much higher uptake in the heart (0.56 + 0.12) and cerebellum (0.17 + 0.04). Studies are now in progress to confirm these exciting results in vitro. Progress has also continued during this period with several collaborative programs. The first large-scale clinical tungsten-188/rhenium-188 generator prototype (500 mCi) was fabricated and supplied to the Center for Molecular Medicine and Immunology (CMMI), in Newark, New Jersey, for Phase I clinical trials of rhenium-188-labeled anti CEA antibodies for patient treatment. Collaborative studies are also continuing in conjunction with the Nuclear Medicine Department at the University of Massachusetts where a generator is in use to compare the biological properties of {open_quotes}direct{close_quotes} and {open_quotes}indirect{close_quotes} labeled antibodies.

  4. Nuclear-Renewable Hybrid Energy Systems: 2016 Technology Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Bragg-Sitton, Shannon M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Boardman, Richard [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Suk Kim, Jong [Idaho National Lab. (INL), Idaho Falls, ID (United States); McKellar, Michael [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sabharwall, Piyush [Idaho National Lab. (INL), Idaho Falls, ID (United States); Chen, Jun [Idaho National Lab. (INL), Idaho Falls, ID (United States); Cetiner, M. Sacit [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Harrison, T. Jay [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Qualls, A. Lou [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-03-01

    The United States is in the midst of an energy revolution, spurred by advancement of technology to produce unprecedented supplies of oil and natural gas. Simultaneously, there is an increasing concern for climate change attributed to greenhouse gas (GHG) emissions that, in large part, result from burning fossil fuels. An international consensus has concluded that the U.S. and other developed nations have an imperative to reduce GHG emissions to address these climate change concerns. The global desire to reduce GHG emissions has led to the development and deployment of clean energy resources and technologies, particularly renewable energy technologies, at a rapid rate. At the same time, each of the major energy sectors—the electric grid, industrial manufacturing, transportation, and the residential/commercial consumers— is increasingly becoming linked through information and communications technologies, advanced modeling and simulation, and controls. Coordination of clean energy generation technologies through integrated hybrid energy systems, as defined below, has the potential to further revolutionize energy services at the system level by coordinating the exchange of energy currency among the energy sectors in a manner that optimizes financial efficiency (including capital investments), maximizes thermodynamic efficiency (through best use of exergy, which is the potential to use the available energy in producing energy services), reduces environmental impacts when clean energy inputs are maximized, and provides resources for grid management. Rapid buildout of renewable technologies has been largely driven by local, state, and federal policies, such as renewable portfolio standards and production tax credits that incentivize investment in these generation sources. A foundational assumption within this program plan is that renewable technologies will continue to be major contributors to the future U.S. energy infrastructure. While increased use of clean

  5. A Conserved Nuclear Cyclophilin Is Required for Both RNA Polymerase II Elongation and Co-transcriptional Splicing in Caenorhabditis elegans.

    Directory of Open Access Journals (Sweden)

    Jeong H Ahn

    2016-08-01

    Full Text Available The elongation phase of transcription by RNA Polymerase II (Pol II involves numerous events that are tightly coordinated, including RNA processing, histone modification, and chromatin remodeling. RNA splicing factors are associated with elongating Pol II, and the interdependent coupling of splicing and elongation has been documented in several systems. Here we identify a conserved, multi-domain cyclophilin family member, SIG-7, as an essential factor for both normal transcription elongation and co-transcriptional splicing. In embryos depleted for SIG-7, RNA levels for over a thousand zygotically expressed genes are substantially reduced, Pol II becomes significantly reduced at the 3' end of genes, marks of transcription elongation are reduced, and unspliced mRNAs accumulate. Our findings suggest that SIG-7 plays a central role in both Pol II elongation and co-transcriptional splicing and may provide an important link for their coordination and regulation.

  6. A Conserved Nuclear Cyclophilin Is Required for Both RNA Polymerase II Elongation and Co-transcriptional Splicing in Caenorhabditis elegans.

    Science.gov (United States)

    Ahn, Jeong H; Rechsteiner, Andreas; Strome, Susan; Kelly, William G

    2016-08-01

    The elongation phase of transcription by RNA Polymerase II (Pol II) involves numerous events that are tightly coordinated, including RNA processing, histone modification, and chromatin remodeling. RNA splicing factors are associated with elongating Pol II, and the interdependent coupling of splicing and elongation has been documented in several systems. Here we identify a conserved, multi-domain cyclophilin family member, SIG-7, as an essential factor for both normal transcription elongation and co-transcriptional splicing. In embryos depleted for SIG-7, RNA levels for over a thousand zygotically expressed genes are substantially reduced, Pol II becomes significantly reduced at the 3' end of genes, marks of transcription elongation are reduced, and unspliced mRNAs accumulate. Our findings suggest that SIG-7 plays a central role in both Pol II elongation and co-transcriptional splicing and may provide an important link for their coordination and regulation.

  7. 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.

  8. Pilot program to identify valve failures which impact the safety and operation of light water nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Tsacoyeanes, J. C.; Raju, P. P.

    1980-04-01

    The pilot program described has been initiated under the Department of Energy Light Water Reactor Safety Research and Development Program and has the following specific objectives: to identify the principal types and causes of failures in valves, valve operators and their controls and associated hardware, which lead to, or could lead to plant trip; and to suggest possible remedies for the prevention of these failures and recommend future research and development programs which could lead to minimizing these valve failures or mitigating their effect on plant operation. The data surveyed cover incidents reported over the six-year period, beginning 1973 through the end of 1978. Three sources of information on valve failures have been consulted: failure data centers, participating organizations in the nuclear power industry, and technical documents.

  9. PACIAE 2.0: An updated parton and hadron cascade model (program) for the relativistic nuclear collisions

    Science.gov (United States)

    Sa, Ben-Hao; Zhou, Dai-Mei; Yan, Yu-Liang; Li, Xiao-Mei; Feng, Sheng-Qin; Dong, Bao-Guo; Cai, Xu

    2012-02-01

    We have updated the parton and hadron cascade model PACIAE for the relativistic nuclear collisions, from based on JETSET 6.4 and PYTHIA 5.7 to based on PYTHIA 6.4, and renamed as PACIAE 2.0. The main physics concerning the stages of the parton initiation, parton rescattering, hadronization, and hadron rescattering were discussed. The structures of the programs were briefly explained. In addition, some calculated examples were compared with the experimental data. It turns out that this model (program) works well. Program summaryProgram title: PACIAE version 2.0 Catalogue identifier: AEKI_v1_0 Program summary URL:http://cpc.cs.qub.ac.uk/summaries/AEKI_v1_0.html Program obtainable from: CPC Program Library, Queen's University, Belfast, N. Ireland Licensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.html No. of lines in distributed program, including test data, etc.: 297 523 No. of bytes in distributed program, including test data, etc.: 2 051 274 Distribution format: tar.gz Programming language: FORTRAN 77 Computer: DELL Studio XPS and others with a FORTRAN 77 or GFORTRAN compiler Operating system: Unix/Linux RAM: 1 G words Word size: 64 bits Classification: 11.2 Nature of problem: The Monte Carlo simulation of hadron transport (cascade) model is successful in studying the observables at final state in the relativistic nuclear collisions. However the high p suppression, the jet quenching (energy loss), and the eccentricity scaling of v etc., observed in high energy nuclear collisions, indicates the important effect of the initial partonic state on the final hadronic state. Therefore better parton and hadron transport (cascade) models for the relativistic nuclear collisions are highly required. Solution method: The parton and hadron cascade model PACIAE is originally based on the JETSET 7.4 and PYTHIA 5.7. The PYTHIA model has been updated to PYTHIA 6.4 with the additions of new physics, the improvements in existing physics, and the

  10. Advanced gas cooled nuclear reactor materials evaluation and development program. Progress report, April 1--June 30, 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-31

    The objectives of the program are to evaluate candidate alloys for Very High Temperature Reactor Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the affect of simulated reactor primary coolant (Helium containing small amounts of various other gases), 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 the report includes the activities associated with the procurement of the materials for the screening test program, information from vendor certification for the materials receiver, and preliminary information from the materials characterization tests performed by General Electric. The construction status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment are discussed. The status of the data management system is also reviewed.

  11. 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.

  12. Advantages of a program of quality control in the nuclear medicine equipment; Ventajas de un programa de control de calidad en los equipos de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Trujillo Z, F.E.; Argumosa, E. [Departamento de Medicina Nuclear del Instituto Nacional de Cancerologia, Tlalpan, Mexico D.F. (Mexico); Herrera R, M.R. [Hospital Infantil de Mexico ' Federico Gomez' , Mexico D.F. (Mexico)

    2007-07-01

    In Nuclear Medicine more 90% of the entirety of the carried out procedures its are with diagnostic ends where it is acquired one or several images. This makes indispensable to have an appropriate operation of the dedicated equipment to produce images and also of those non former images, as the activity caliper, to assure an appropriate quality diagnoses not from the images and the correct dose administration to the patient. In this work the main calibrations that should be carried out and an example of the program of quality control of a gamma camera mark Siemens and model E.CAM are presented. Considerations that should take as for the radiological protection are exposed. Comments on the parameters that correct the required calibrations and the images taken place by an operation or inadequate calibrations are included. In conclusion, the necessity of a program that it contains as minimum the quality control of the gamma cameras and of the activity caliper, having as main advantages a good image quality diagnoses and to minimize the dose imparted the patient are exposed. (Author)

  13. Lessons in Nuclear Safety, Panel on Integration of People and Programs

    Energy Technology Data Exchange (ETDEWEB)

    Pinkston, David [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-02-24

    Four slides present a historical perspective on the evolution of nuclear safety, a description of systemic misalignment (available resources do not match expectations, demographic cliff developing, promulgation of increased expectations and new requirements proceeds unabated), and needs facing nuclear safety (financial stability, operational stability, and succession planning). The following conclusions are stated under the heading "Nuclear Safety - 'The System'": the current universe of requirements is too large for the resource pool available; the current universe of requirements has too many different sources of interpretation; there are so many indicators that it’s hard to know what is leading (or important); and the net result can come to defy integrated comprehension at the worker level.

  14. Applications of nuclear physics

    Science.gov (United States)

    Hayes, A. C.

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  15. Applications of nuclear physics.

    Science.gov (United States)

    Hayes, A C

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  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. Experiments at the Frontiers of Nuclear Physics: the Experimental Program of the Super-Frs Collaboration

    Science.gov (United States)

    Scheidenberger, C.; Äystö, J.; Behr, K.-H.; Benlliure, J.; Bracco, A.; Egelhof, P.; Fomichev, A.; Galès, S.; Geissel, H.; Grahn, T.; Grigorenko, L.; Harakeh, M. N.; Hayano, R.; Heinz, S.; Itahashi, K.; Jokinen, A.; Kalantar-Nayestanaki, N.; Kanungo, R.; Lenske, H.; Muenzenberg, G.; Mukha, I.; Nociforo, C.; Ong, H. J.; Pfützner, M.; Prochazka, A.; Pietri, S.; Plaß, W. R.; Purushothaman, S.; Saito, T.; Simon, H.; Tanihata, I.; Terashima, S.; Toki, H.; Trache, L.; Weick, H.; Winfield, J. S.; Winkler, M.; Zamfir, V.

    2015-06-01

    The superconducting fragment separator (Super-FRS) will be one of the main scientific instruments of the future FAIR facility. This versatile high-resolution spectrometer allows for a variety of exciting experiments in atomic, nuclear and hadron physics. Future directions are presented in this contribution.

  18. NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-07-01

    This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

  19. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    A. K. Herbst; J. A. McCray; R. J. Kirkham; J. Pao; S. H. Hinckley

    1999-09-30

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

  20. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Hinckley, Steve Harold

    1999-10-01

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

  1. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program, FY-98 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, A.K.; Rogers, A.Z.; McCray, J.A.; Simmons, R.F.; Palethorpe, S.J.

    1999-03-01

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

  2. Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-98 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Herbst, Alan Keith; Mc Cray, John Alan; Rogers, Adam Zachary; Simmons, R. F.; Palethorpe, S. J.

    1999-03-01

    The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

  3. 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

  4. Fabrication and testing of a 4-node micro-pocket fission detector array for the Kansas State University TRIGA Mk. II research nuclear reactor

    Science.gov (United States)

    Reichenberger, Michael A.; Nichols, Daniel M.; Stevenson, Sarah R.; Swope, Tanner M.; Hilger, Caden W.; Unruh, Troy C.; McGregor, Douglas S.; Roberts, Jeremy A.

    2017-08-01

    Advancements in nuclear reactor core modeling and computational capability have encouraged further development of in-core neutron sensors. Micro-Pocket Fission Detectors (MPFDs) have been fabricated and tested previously, but successful testing of these prior detectors was limited to single-node operation with specialized designs. Described in this work is a modular, four-node MPFD array fabricated and tested at Kansas State University (KSU). The four sensor nodes were equally spaced to span the length of the fuel-region of the KSU TRIGA Mk. II research nuclear reactor core. The encapsulated array was filled with argon gas, serving as an ionization medium in the small cavities of the MPFDs. The unified design improved device ruggedness and simplified construction over previous designs. A 0.315-in. (8-mm) penetration in the upper grid plate of the KSU TRIGA Mk. II research nuclear reactor was used to deploy the array between fuel elements in the core. The MPFD array was coupled to an electronic support system which has been developed to support pulse-mode operation. Neutron-induced pulses were observed on all four sensor channels. Stable device operation was confirmed by testing under steady-state reactor conditions. Each of the four sensors in the array responded to changes in reactor power between 10 kWth and full power (750 kWth). Reactor power transients were observed in real-time including positive transients with periods of 5, 15, and 30 s. Finally, manual reactor power oscillations were observed in real-time.

  5. Communication and surrounding of Asco and Vandellos II nuclear power plants; La comunicacion y el entorno de las centrales de Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The Asco and Vandellos-II power plants have always been integrated into the regions where they are located, and they take an active part in the development of surrounding towns through quality employment provided by our facilities, social and cultural support and aid to development promoted by regional councils. Communication to media is a corporate priority defined in our strategic plant, to ensure openness, rigour and punctuality. We also attend to the visitors who want to learn more about our facilities in the visitor center, and we have agreements with agrarian institutions in the area so that students can de practical training in the farms we own for agricultural production. (Author)

  6. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Quarterly progress report, April 1, 1977--June 30, 1977

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    The objectives of this program are to evaluate candidate alloys of Very High Temperature Reactor (VHTR) Process Heat and Direct Cycle helium Turbine (DCHT) applications, in terms of the effects 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 the report includes completion of alloy selection for the screening tests. The alloys selected for potential VHTR Nuclear Process Heat (NPH) applications and for potential DCHT applications are listed. The present status on the simulated reactor helium loop design and construction and the design and construction progress on the testing and analysis facilities and equipment are discussed.

  7. Nuclear Terrorism: Calibrating Funding for Defensive Programs in Response to the Threat

    Science.gov (United States)

    2009-12-01

    However, the likelihood of such an attack raises three fundamental questions that must be answered to fairly and rationally characterize the scope of the...that DOE sites, such as Los Alamos National Laboratory, Y-12, Oak Ridge National Laboratory, and Hanford , have all received waivers exempting them...and frequently less secure potential source of nuclear bomb building material. In mid-2008, the global supply of HEU was estimated at 1,670 +/- 300

  8. Establishing an effective dose equivalent monitoring program for a commercial nuclear power station

    Science.gov (United States)

    Thompson, Barbara Jane

    The purpose of this thesis is to determine whether monitoring personnel with multiple dosimeter badges to determine effective dose equivalent (EDE) is both acceptable to the Nuclear Regulatory Commission (NRC) and practical for the nuclear power industry. Until now, most nuclear power plants have used a single dosimeter or occasionally multiple dosimeters to monitor the "deep dose equivalent (DDE)" as defined by the International Commission on Radiological Units (ICRU). The measurement of EDE, to replace DDE, is now deemed by international and regulatory agencies to better approximate a worker's dose related to long-term risks of occupational radiation exposure. The definition of DDE, and the formulation of EDE for use as a new indicator of occupational exposure, are presented in this thesis. Radiation exposure measurements using multiple dosimeters on each worker for certain tasks were collected for this thesis on workers at a Dominion/Virginia Company nuclear power plant. These multiple dosimeter measurements have been examined to determine how such a new personnel monitoring system compares to the former one at the Dominion plant, in which only one dosimeter reading was used predominately to calculated deep dose equivalent. This is based on the assumption that most workers were exposed to uniform radiation fields and that the single dosimeter reading was representative of the highest average exposure for the worker's task. These multiple dosimetry measurements show that it is both feasible and advantageous to provide such dosimetry in situations where exposures may be non-uniform and significant enough to approach yearly exposure limits in a single day, such as in the tasks required during refueling outages.

  9. For the Record - A History of the Nuclear Test Personnel Review Program, 1978-1986.

    Science.gov (United States)

    1986-08-01

    Philip and 16 on the USS Bairoko sustained lesions that were classified as beta burns, all of which healed without complications (13: 3-4). Summary of...October Tower NMY* HUMBOLDT 29 October Tower 0.0078 SANTA FE 30 October Balloon 1.3 BLANCA 30 October Tunnel 22 *No measurable yield 4.17.1 Background...weapons far more powerful than conventional explosives. Nuclear energy is another and a more appropriate label for this energy. BETA BURNS Skin lesions

  10. 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.

  11. Biologically relevant mono- and di-nuclear manganese II/III/IV complexes of mononegative pentadentate ligands

    DEFF Research Database (Denmark)

    Baffert, Carole; Collomb, Marie-Nöelle; Deronzier, Alain

    2003-01-01

    ,2-diamine) have been prepared. The crystal structure of the Mn(II)-aqua complex of 1, shows it to be dimeric via (mu-kappaO)-bridging through one carboxylate oxygen atom of each of the two ligands. The non-coordinated carboxylate oxygen atoms are H-bonded to the water ligands on the adjacent Mn ion...... were characterised by UV-visible spectroscopy, ESI mass spectrometry and cyclic voltammetry. In addition, III-IV and II-III species were electrochemically generated. Thus the new mononegative pentadentate ligand systems display significant flexibility in the range of Mn oxidation states and species...

  12. Light Water Reactor Sustainability Program: Evaluation of Localized Cable Test 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); Fifield, Leonard S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hartman, Trenton S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-05-30

    This Pacific Northwest National Laboratory (PNNL) milestone report describes progress to date on the investigation of nondestructive test (NDE) methods focusing particularly on local measurements 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 NPPs consider applying for second, or subsequent, license renewal (SLR) to extend their operating period from 60 years to 80 years, it important to understand how the materials installed in plant systems and components will age during that time and develop aging management programs (AMPs) 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 is directed toward the more demanding challenge of assuring the cable function under accident or DBE. Most utilities already have a program associated with their first life extension from 40 to 60 years. Regrettably, there is neither a clear guideline nor a single NDE that can assure cable function and integrity for all cables. Thankfully, however, practical implementation of a broad range of tests allows utilities to develop a practical program that assures cable function to a high degree. 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 is a destructive test so the test programs must apply an array of other NDE tests to assure or infer the overall set of cable’s system integrity. These cable NDE programs vary in rigor and methodology. As the industry gains experience with the efficacy of these programs, it is expected that implementation practice will converge to a more common approach. This report addresses the range of local NDE cable tests that are

  13. A combination of lacunary polyoxometalates and high-nuclear transition-metal clusters under hydrothermal conditions. Part II: From double cluster, dimer, and tetramer to three-dimensional frameworks.

    Science.gov (United States)

    Zhao, Jun-Wei; Jia, Hong-Peng; Zhang, Jie; Zheng, Shou-Tian; Yang, Guo-Yu

    2007-01-01

    The hydrothermal reactions of trivacant Keggin A-alpha-XW(9)O(34) polyoxoanions (X=P(V)/Si(IV)) with transition-metal ions (Ni(II)/Cu(II)/Fe(II)) in the presence of amines result in eight novel high-nuclear transition-metal-substituted polyoxotungstates [{Ni(7)(mu(3)-OH)(3)O(2)(dap)(3)(H(2)O)(6)}(B-alpha-PW(9)O(34))][{Ni(6)(mu(3)-OH)(3)(dap)(3)(H(2)O)(6)}(B-alpha-PW(9)O(34))][Ni(dap)(2)(H(2)O)(2)]4.5 H(2)O (1), [Cu(dap)(H(2)O)(3)](2)[{Cu(8)(dap)(4)(H(2)O)(2)}(B-alpha-SiW(9)O(34))(2)]6 H(2)O (2), (enH(2))(3)H(15)[{Fe(II) (1.5)Fe(III) (12)(mu(3)-OH)(12)(mu(4)-PO(4))(4)}(B-alpha-PW(9)O(34))(4)]ca.130 H(2)O (3), [{Cu(6)(mu(3)-OH)(3)(en)(3) (H(2)O)(3)}(B-alpha-PW(9)O(34))]7 H(2)O (4), [{Ni(6)(mu(3)-OH)(3)(en)(3)(H(2)O)(6)}(B-alpha-PW(9)O(34))]7 H(2)O (5), [{Ni(6)(mu(3)-OH)(3)(en)(2)(H(2)O)(8)}(B-alpha-PW(9)O(34))]7 H(2)O (6), [{Ni(6)(mu(3)-OH)(3)(dap)(2)(H(2)O)(8)}(B-alpha-PW(9)O(34))] 7 H(2)O (7), and [{Ni(6)(mu(3)-OH)(3)(en)(3)(H(2)O)(6)}(B-alpha-SiW(9)O(34))][Ni(0.5)(en)] 3.5 H(2)O (8) (en=ethylenediamine, dap=1,2-diaminopropane). These compounds have been structurally characterized by elemental analyses, IR spectra, diffuse reflectance spectra, thermogravimatric analysis, and X-ray crystallography. The double-cluster complex of phosphotungstate 1 simultaneously contains hepta- and hexa-Ni(II)-substituted trivacant Keggin units [{Ni(7)(mu(3)-OH)(3)O(2)(dap)(3)(H(2)O)(6)}(B-alpha-PW(9)O(34))](2-) and [{Ni(6)(mu(3)-OH)(3)(dap)(3)(H(2)O)(6)}(B-alpha-PW(9)O(34))]. The dimeric silicotungstate 2 is built up from two trivacant Keggin [B-alpha-SiW(9)O(34)](10-) fragments linked by an octa-Cu(II) cluster. The main skeleton of 3 is a tetrameric cluster constructed from four tri-Fe(III)-substituted [Fe(III) (3)(mu(3)-OH)(3)(B-alpha-PW(9) O(34))](3-) Keggin units linked by a central Fe(II) (4)O(4) cubane core and four mu(4)-PO(4) bridges. Complex 4 is an unprecedented three-dimensional extended architecture with hexagonal channels built by hexa-Cu(II) clusters and trivacant

  14. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1980-September 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-12-12

    Objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), 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 the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described: screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, 950 and 1050/sup 0/C. Initiation of controlled purity helium creep-rupture testing in the intensive screening test program is discussed. In addition, the results of 1000-hour exposures at 750 and 850/sup 0/C on several experimental alloys are discussed.

  15. Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, April 1, 1980-June 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-11-14

    Objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), 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 the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described; this includes: screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850 and 950/sup 0/C. The initiation of air creep-rupture testing in the intensive screening test program is discussed. In addition, the status of the data management system is described.

  16. Comparison between a 13-session and one-time program on Korea elementary, middle and high school students' understanding of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Han, Eun Ok; Choi, Yoon Seok [Dept. of Education and Research, Korea Academy of Nuclear Safety, Seoul (Korea, Republic of); Lim, Young Khi [Dept. of Radiological Science, Gachon University, Incheon (Korea, Republic of)

    2017-03-15

    To help future generations make accurate value judgments about nuclear power generation and radiation, this study will provide an effective education plan suitable for South Korea by applying and analyzing programs for the understanding of nuclear power within the diversely operated programs in the current Korean education system. This study analyzed the difference in educational effects by operating a 13-session regular curriculum for one semester and a one-session short-term curriculum from March to July 2016. As a result of operating a 13-session model school and a one-time educational program to analyze behavior changes against the traditional learning model, it was found that all elementary, middle and high school students showed higher acceptability of nuclear power in South Korea. The variation was greater for the model school than the short-term program. To prevent future generations from making biased policy decisions stemming from fear regarding nuclear power, it is necessary to bolster their value judgments in policy decisions by acquiring sufficient information about nuclear power generation and radiation through educational programs.

  17. The Dresden Felsenkeller shallow-underground accelerator laboratory for nuclear astrophysics - Status and first physics program

    Energy Technology Data Exchange (ETDEWEB)

    Ilgner, Ch. [Nuclear Astrophysics group, Helmholtz-Zentrum Dresden-Rossendorf, Institute of Radiation Physics, Dresden (Germany)

    2015-07-01

    Favored by the low background in underground laboratories, low-background accelerator-based experiments are an important tool to study nuclear reactions involving stable charged particles. This technique has been used for many years with great success at the 0.4 MV LUNA accelerator in the Gran Sasso laboratory in Italy, protected from cosmic rays by 1400 m of rock. However, the nuclear reactions of helium and carbon burning and the neutron source reactions for the astrophysical s-process require higher beam energies than those available at LUNA. Also the study of solar fusion reactions necessitates new data at higher energies. As a result, in the present NuPECC long range plan for nuclear physics in Europe, the installation of one or more higher-energy underground accelerators is strongly recommended. An intercomparison exercise using the same High-Purity Ge detector at several sites has shown that, with a combination of 45 m rock overburden, as can be found in the Felsenkeller underground site in Dresden, and an active veto against the remaining muon flux, in a typical nuclear astrophysics setup a background level can be achieved that is similar to the deep underground scenario as in the Gran- Sasso underground laboratory, for instance. Recently, a muon background study and geodetic measurements were carried out by the REGARD group. It was estimated that the rock overburden at the place of the future ion accelerator is equivalent to 130 m of water. The maximum muon flux measured was 2.5 m{sup -2} sr{sup -1} s{sup -1}, in the direction of the tunnel entrance. Based on this finding, a used 5 MV pelletron tandem accelerator with 250 μA up-charge current and external sputter ion source has been obtained and transported to Dresden. Work on an additional radio-frequency ion source on the high voltage terminal is in progress and far advanced. The installation of the accelerator in the Felsenkeller is expected for the near future. The status of the project and the

  18. Corrosion of oxide nuclear fuels in high-temperature water (LWBR Development Program

    Energy Technology Data Exchange (ETDEWEB)

    Markowitz, J M; Clayton, J C

    1970-02-01

    The corrosion behavior of a group of nuclear fuel oxides including urania, thoria, urania-zirconia, urania-calcia-zirconia, and urania-thoria has been studied in 360/sup 0/C, pH 10 flowing water, both degassed and oxygenated (5 and 100 ppM). Weight gains of the specimens, which were of plate or cylindrical pellet shape, were determined periodically during the corrosion exposures, some of which were as long as 500 days; in addition, ceramographic examinations, x-ray diffraction measurements, and chemical analyses were carried out on selected specimens. The results are summarized and discussed. (NSA 24: 25764)

  19. Construction of a bibliographic information database and development of retrieval system for research reports in nuclear science and technology (II)

    Energy Technology Data Exchange (ETDEWEB)

    Han, Duk Haeng; Kim, Tae Whan; Choi, Kwang; Yoo, An Na; Keum, Jong Yong; Kim, In Kwon [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-05-01

    The major goal of this project is to construct a bibliographic information database in nuclear engineering and to develop a prototype retrieval system. To give an easy access to microfiche research report, this project has accomplished the construction of microfiche research reports database and the development of retrieval system. The results of the project are as follows; 1. Microfiche research reports database was constructed by downloading from DOE Energy, NTIS, INIS. 2. The retrieval system was developed in host and web version using access point such as title, abstracts, keyword, report number. 6 tabs., 8 figs., 11 refs. (Author) .new.

  20. Department of Defense Chemical, Biological, Radiological, and Nuclear Defense Program. FY2003-2005 Performance Plan

    Science.gov (United States)

    2004-05-01

    cell and working cell banks. - Conduct assay development and validation. Initiated technology transfer and process definition for a candidate... cell banks for serotypes C, E, and F (Block II). Recombinant Botulinum Vaccine − Continue process validation efforts for serotypes A and B (Block I...Integrated CB Detection Complete investigation of modified nanoelectrodes for the detection of CB agents. Initiate novel approaches for improved CB

  1. Program of radiological monitoring environmental a nuclear facility in latency; Sistema de Analisis Espectrometrico de los equipos de las estaciones de la Red de Vigilancia Radiologica de Cataluna

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  2. Groundwater monitoring program plan and conceptual site model for the Al-Tuwaitha Nuclear Research Center in Iraq.

    Energy Technology Data Exchange (ETDEWEB)

    Copland, John Robin; Cochran, John Russell

    2013-07-01

    The Radiation Protection Center of the Iraqi Ministry of Environment is developing a groundwater monitoring program (GMP) for the Al-Tuwaitha Nuclear Research Center located near Baghdad, Iraq. The Al-Tuwaitha Nuclear Research Center was established in about 1960 and is currently being cleaned-up and decommissioned by Iraqs Ministry of Science and Technology. This Groundwater Monitoring Program Plan (GMPP) and Conceptual Site Model (CSM) support the Radiation Protection Center by providing: A CSM describing the hydrogeologic regime and contaminant issues, recommendations for future groundwater characterization activities, and descriptions of the organizational elements of a groundwater monitoring program. The Conceptual Site Model identifies a number of potential sources of groundwater contamination at Al-Tuwaitha. The model also identifies two water-bearing zones (a shallow groundwater zone and a regional aquifer). The depth to the shallow groundwater zone varies from approximately 7 to 10 meters (m) across the facility. The shallow groundwater zone is composed of a layer of silty sand and fine sand that does not extend laterally across the entire facility. An approximately 4-m thick layer of clay underlies the shallow groundwater zone. The depth to the regional aquifer varies from approximately 14 to 17 m across the facility. The regional aquifer is composed of interfingering layers of silty sand, fine-grained sand, and medium-grained sand. Based on the limited analyses described in this report, there is no severe contamination of the groundwater at Al-Tuwaitha with radioactive constituents. However, significant data gaps exist and this plan recommends the installation of additional groundwater monitoring wells and conducting additional types of radiological and chemical analyses.

  3. Program for the thermal design and simulation of the operation of a steam condenser for thermal and nuclear power stations and its application to the condenser at the Cofrentes nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Garcia Bartual, R.; Pallares Huici, E.

    A program is being developed for an IBM-PC or AT computer based on a calculation system which synthesises the heat transfer process which takes place in the steam condensors at conventional thermal power stations. The program incorporates a useful tool capable of representing characteristic operating curves for a given condensor. Describes its application to the steam condenser at the Cofrentes nuclear power station. 4 refs., 5 tabs., 8 figs.

  4. Health effects model for nuclear power plant accident consequence analysis. Part I. Introduction, integration, and summary. Part II. Scientific basis for health effects models

    Energy Technology Data Exchange (ETDEWEB)

    Evans, J.S.; Moeller, D.W.; Cooper, D.W.

    1985-07-01

    Analysis of the radiological health effects of nuclear power plant accidents requires models for predicting early health effects, cancers and benign thyroid nodules, and genetic effects. Since the publication of the Reactor Safety Study, additional information on radiological health effects has become available. This report summarizes the efforts of a program designed to provide revised health effects models for nuclear power plant accident consequence modeling. The new models for early effects address four causes of mortality and nine categories of morbidity. The models for early effects are based upon two parameter Weibull functions. They permit evaluation of the influence of dose protraction and address the issue of variation in radiosensitivity among the population. The piecewise-linear dose-response models used in the Reactor Safety Study to predict cancers and thyroid nodules have been replaced by linear and linear-quadratic models. The new models reflect the most recently reported results of the follow-up of the survivors of the bombings of Hiroshima and Nagasaki and permit analysis of both morbidity and mortality. The new models for genetic effects allow prediction of genetic risks in each of the first five generations after an accident and include information on the relative severity of various classes of genetic effects. The uncertainty in modeloling radiological health risks is addressed by providing central, upper, and lower estimates of risks. An approach is outlined for summarizing the health consequences of nuclear power plant accidents. 298 refs., 9 figs., 49 tabs.

  5. Nuclear inelastic scattering of 1D polymeric Fe(II) complexes of 1,2,4-aminotriazole in their high-spin and low-spin state

    Energy Technology Data Exchange (ETDEWEB)

    Wolny, Juliusz A., E-mail: wolny@physik.uni-kl.de; Rackwitz, Sergej [University of Kaiserslautern, Department of Physics (Germany); Achterhold, Klaus [Technische Universitaet Muenchen, Department of Physics (Germany); Muffler, Kai; Schuenemann, Volker [University of Kaiserslautern, Department of Physics (Germany)

    2012-03-15

    The vibrational properties of Fe(II) 1D spin crossover polymers have been characterized by nuclear inelastic scattering (NIS). The complexes under study were the tosylate and perchlorate salts of ([Fe(4-amino-1,2,4-triazole){sub 3}] <{sup +2}){sub n} complexes. The complexes have LS (S = 0) marker bands in the range of 300-500 cm{sup - 1}, while the marker bands corresponding to the HS (S = 2) state are detected between 200 cm{sup - 1} and 300 cm{sup - 1}, in line with the decreasing Fe-N bond strengths during the transition from LS to HS. Accompanying DFT calculations using the functional B3LYP and the basis set CEP-31G confirm these assignments.

  6. Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1956, Part 1 - 5

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, W. H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Cramer, S. J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Miller, A. J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    1957-03-12

    This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of the research on circulating-fuel reactors and other ANP research at the Laboratory under its Contract W-7405-eng-26. The report is divided into five major parts: 1. Aircraft Reactor Engineering, 2. Chemistry, 3. Metallurgy, 4. Heat Transfer and Physical Properties, Radiation Damage, and Fuel Recovery and Reprocessing, and 5. Reactor Shielding. The ANP Project is comprised of about 550 technical and scientific personnel engaged in many phases of research directed toward the achievement of nuclear propulsion of aircraft. A considerable portion of this research is performed in support of the work of other organizations participating in the national ANP effort. However, the bulk of the ANP research at ORNL is directed toward the development of a circulating-fuel type of reactor. The design, construction, and operation of the Aircraft Reactor Test (ART), with the cooperation of the Pratt & Whitney Aircraft Division, are the current objectives of the project. The ART is to be a power plant system that will include a 60-Mw circulating fuel reflector-moderator reactor and adequate means for heat disposal. Operation of the system will be for the purpose of determining feasibility and for studying the problems associated with the design, construction, and operation of a high-power circulating-fuel refIector-moderated aircraft reactor system.

  7. T helper 17 lineage differentiation is programmed by orphan nuclear receptors ROR alpha and ROR gamma.

    Science.gov (United States)

    Yang, Xuexian O; Pappu, Bhanu P; Nurieva, Roza; Akimzhanov, Askar; Kang, Hong Soon; Chung, Yeonseok; Ma, Li; Shah, Bhavin; Panopoulos, Athanasia D; Schluns, Kimberly S; Watowich, Stephanie S; Tian, Qiang; Jetten, Anton M; Dong, Chen

    2008-01-01

    T cell functional differentiation is mediated by lineage-specific transcription factors. T helper 17 (Th17) has been recently identified as a distinct Th lineage mediating tissue inflammation. Retinoic acid receptor-related orphan receptor gamma (ROR gamma) was shown to regulate Th17 differentiation; ROR gamma deficiency, however, did not completely abolish Th17 cytokine expression. Here, we report Th17 cells highly expressed another related nuclear receptor, ROR alpha, induced by transforming growth factor-beta and interleukin-6 (IL-6), which is dependent on signal transducer and activator of transcription 3. Overexpression of ROR alpha promoted Th17 differentiation, possibly through the conserved noncoding sequence 2 in Il17-Il17f locus. ROR alpha deficiency resulted in reduced IL-17 expression in vitro and in vivo. Furthermore, ROR alpha and ROR gamma coexpression synergistically led to greater Th17 differentiation. Double deficiencies in ROR alpha and ROR gamma globally impaired Th17 generation and completely protected mice against experimental autoimmune encephalomyelitis. Therefore, Th17 differentiation is directed by two lineage-specific nuclear receptors, ROR alpha and ROR gamma.

  8. 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...

  9. Exploration for fossil and nuclear fuels from orbital altitudes. [results of ERTS program for oil exploration

    Science.gov (United States)

    Short, N. M.

    1974-01-01

    Results from the ERTS program pertinent to exploration for oil, gas, and uranium are discussed. A review of achievements in relevant geological studies from ERTS, and a survey of accomplishments oriented towards exploration for energy sources are presented along with an evaluation of the prospects and limitations of the space platform approach to fuel exploration, and an examination of continuing programs designed to prove out the use of ERTS and other space system in exploring for fuel resources.

  10. Regulatory activities related with the modification of the frequency of the programmed stoppings of the Argentine nuclear centrals; Actividades regulatorias relacionadas con la modficacion de la frecuencia de las paradas programadas de las centrales nucleares argentinas

    Energy Technology Data Exchange (ETDEWEB)

    Marino, E.; Calvo, J.; Waldman, R.; Navarro, R

    2006-07-01

    The mandatory character documentation of the Argentinean nuclear power stations in Embalse and Atucha I, required the realization of a programmed stoppings every twelve months to execute that settled down in the maintenance and surveillance programs for each installation. Nucleoelectrica Argentina S.A., in it character of Responsible Entity of the operation of these power stations, requested to the Argentinean Nuclear Regulatory Authority, in 2003 and 2005 respectively, the authorization to change the period of the repetitive tests and of the preventive maintenance of the systems related with the safety, to extend them from twelve to eighteen months. The mentioned applications were founded in economic aspects and in inclining to a decrease in the doses of the workers that perform in the activities that are carried out in the programmed stops. The adopted position by the Nuclear Regulatory Authority to decide on these applications was based on the result of diverse evaluations that included the use of the Probabilistic Analysis of Safety specific of each power station, the operative experience resultant of the execution of the preventive maintenance program, and of the results of the repetitive tests and of the inspections in service. The regulatory decisions were different in each case. Indeed, the Embalse nuclear power station was authorized by the Regulatory Authority to modify from twelve to eighteen months the period among the realization of the repetitive tests and of the preventive maintenance, conditioned to the execution of some specific regulatory requirements. On the other hand, the Atucha I nuclear power station was not authorized to modify this period. In this presentation that is detailed the acted by the Nuclear Regulatory Authority in both cases, the used analysis tools, and the foundation of the adopted decisions. (Author)

  11. The social construction of risk and the controversial Brazilian Nuclear Program: among scientific, political and public; Construcao social do risco e o controverso Programa Nuclear Brasileiro: entre o cientifico, o politico e o publico

    Energy Technology Data Exchange (ETDEWEB)

    Camelo, Ana Paula

    2015-07-01

    This research aims to investigate the Brazilian Nuclear Program (PNB) stating as reference the Fukushima nuclear accident. Its main purpose is to analyze how the Japanese accident impacted the PNB. Therefore, the program will be analyzed within 10-years (2004-2014) in order to answer this question. The discussion launched in this thesis is based on the framework of the Social Studies of Science and Technology, which enables the understanding of socio-technical controversies beyond the social or technological determinism. Through the discussion of the concepts of framing, socio-technical imaginary, risk and governance of science and technology, the research shows how the controversy in focus has resulted in the opportunity to consider not only economic, technological, environmental issues about nuclear energy, but also its political dimensions and challenges. Among these challenges, and from very different perspectives, arise questions about the role nuclear energy plays in the Brazilian context, the future of the program and the decision making process on these issues. Despite the central purpose of this study is essentially on risks, PNB and on the Brazilian context, it should be pointed that it is impossible to consider it in isolation of what is happening internationally (considering interests, tensions, relations between actors, etc.) The research thereby identifies key implications of Fukushima in the international context, but focuses on the disputes regarding possible review of the PNB. It also highlights how the socio-technical controversies, such as the nuclear energy, demand or impose a discussion on the governance of science and technology, risk and on the engagement of different sectors and actors in decision-making on issues, that are at the same time about energy, technology and nationality relevance. All this reflection is made from multi-sited analysis, which allowed following the controversy surrounding nuclear energy, reheated by the Fukushima

  12. Experience and advantages in implementation of educational program in network form at Department «Closed nuclear fuel cycle Technologies» of National Research Nuclear University «MEPhI»

    Science.gov (United States)

    Beygel‧, A. G.; Kutsenko, K. V.; Lavrukhin, A. A.; Magomedbekov, E. P.; Pershukov, V. A.; Sofronov, V. L.; Tyupina, E. A.; Zhiganov, A. N.

    2017-01-01

    The experience of implementation of the basic educational program of magistracy on direction «Nuclear Physics and Technologies» in a network form is presented. Examples of joint implementation of the educational process with employers organizations, other universities and intranet mobility of students are given.

  13. Measurements of miniature ionization chamber currents in the JSI TRIGA Mark II reactor demonstrate the importance of the delayed contribution to the photon field in nuclear reactors

    Science.gov (United States)

    Radulović, Vladimir; Fourmentel, Damien; Barbot, Loïc; Villard, Jean-François; Kaiba, Tanja; Gašper, Žerovnik; Snoj, Luka

    2015-12-01

    The characterization of experimental locations of a research nuclear reactor implies the determination of neutron and photon flux levels within, with the best achievable accuracy. In nuclear reactors, photon fluxes are commonly calculated by Monte Carlo simulations but rarely measured on-line. In this context, experiments were conducted with a miniature gas ionization chamber (MIC) based on miniature fission chamber mechanical parts, recently developed by the CEA (French Atomic Energy and Alternative Energies Commission) irradiated in the core of the Jožef Stefan Institute TRIGA Mark II reactor in Ljubljana, Slovenia. The aim of the study was to compare the measured MIC currents with calculated currents based on simulations with the MCNP6 code. A discrepancy of around 50% was observed between the measured and the calculated currents; in the latter taking into consideration only the prompt photon field. Further experimental measurements of MIC currents following reactor SCRAMs (reactor shutdown with rapid insertions of control rods) provide evidence that over 30% of the total measured signal is due to the delayed photon field, originating from fission and activation products, which are untreated in the calculations. In the comparison between the measured and calculated values, these findings imply an overall discrepancy of less than 20% of the total signal which is still unexplained.

  14. Evolution of seismic monitoring systems of nuclear power plants. Improvements and practical applications; Evolucion de los sistemas de vigilancia sismica de las II.NN. Mejoras introducidas y aplicaciones practicas

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez Cabanero, J. G.; Jimenez Juan, A.

    2010-07-01

    The II. NN. Spanish have a seismic monitoring system (SVS) covering two objectives relevant to nuclear security: determining earthquake leave operation, and specific data that serve to limit or reduce the uncertainties associated with the seismic source, the site and design. Since its construction, the major SVS II. NN. have been equipped with the best time of seismic instrumentation to record earthquakes strong, but with limited resolution for recording in the free field and appropriately moderate earthquakes.

  15. The Savannah River Site`s Groundwater Monitoring Program, First Quarter 1996, Volumes I and II

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, C.D. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1996-10-22

    This report summarizes the Savanna River Site (SRS) Groundwater Monitoring Program conducted by EPD/EMS during the first quarter 1996. It includes the analytical data, field data, data review, quality control, and other documentation for this program. It also provides a record of the program`s activities and serves as an official record of the analytical results.

  16. 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.

  17. Computer program TRACK_TEST for calculating parameters and plotting profiles for etch pits in nuclear track materials

    Science.gov (United States)

    Nikezic, D.; Yu, K. N.

    2006-01-01

    A computer program called TRACK_TEST for calculating parameters (lengths of the major and minor axes) and plotting profiles in nuclear track materials resulted from light-ion irradiation and subsequent chemical etching is described. The programming steps are outlined, including calculations of alpha-particle ranges, determination of the distance along the particle trajectory penetrated by the chemical etchant, calculations of track coordinates, determination of the lengths of the major and minor axes and determination of the contour of the track opening. Descriptions of the program are given, including the built-in V functions for the two commonly employed nuclear track materials commercially known as LR 115 (cellulose nitrate) and CR-39 (poly allyl diglycol carbonate) irradiated by alpha particles. Program summaryTitle of the program:TRACK_TEST Catalogue identifier:ADWT Program obtainable from:CPC Program Library, Queen's University of Belfast, N. Ireland Program summary URL:http://cpc.cs.qub.ac.uk/summaries/ADWT Computer:Pentium PC Operating systems:Windows 95+ Programming language:Fortran 90 Memory required to execute with typical data:256 MB No. of lines in distributed program, including test data, etc.: 2739 No. of bytes in distributed program, including test data, etc.:204 526 Distribution format:tar.gz External subprograms used:The entire code must be linked with the MSFLIB library Nature of problem: Fast heavy charged particles (like alpha particles and other light ions etc.) create latent tracks in some dielectric materials. After chemical etching in aqueous NaOH or KOH solutions, these tracks become visible under an optical microscope. The growth of a track is based on the simultaneous actions of the etchant on undamaged regions (with the bulk etch rate V) and along the particle track (with the track etch rate V). Growth of the track is described satisfactorily by these two parameters ( V and V). Several models have been presented in the past describing

  18. Civil Defense, U. S. A.: A Programmed Orientation to Civil Defense. Unit 2. Nuclear Weapons Effects and Shelter.

    Science.gov (United States)

    Defense Civil Preparedness Agency (DOD), Battle Creek, MI.

    Basic information about nuclear weapons is presented so that their effects can be meaningfully related to the defensive countermeasures which will be most effective against them. Major topics include: (1) Explosive power of nuclear weapons, (2) Major effects of nuclear explosions, (3) Two basic types of nuclear explosions, (4) Contrast between air…

  19. Nuclear weapons modernizations

    Energy Technology Data Exchange (ETDEWEB)

    Kristensen, Hans M. [Federation of American Scientists, Washington, DC (United States)

    2014-05-09

    This article reviews the nuclear weapons modernization programs underway in the world's nine nuclear weapons states. It concludes that despite significant reductions in overall weapons inventories since the end of the Cold War, the pace of reductions is slowing - four of the nuclear weapons states are even increasing their arsenals, and all the nuclear weapons states are busy modernizing their remaining arsenals in what appears to be a dynamic and counterproductive nuclear competition. The author questions whether perpetual modernization combined with no specific plan for the elimination of nuclear weapons is consistent with the nuclear Non-Proliferation Treaty and concludes that new limits on nuclear modernizations are needed.

  20. Nuclear Physics

    CERN Document Server

    Savage, Martin J

    2016-01-01

    Lattice QCD is making good progress toward calculating the structure and properties of light nuclei and the forces between nucleons. These calculations will ultimately refine the nuclear forces, particularly in the three- and four-nucleon sector and the short-distance interactions of nucleons with electroweak currents, and allow for a reduction of uncertainties in nuclear many-body calculations of nuclei and their reactions. After highlighting their importance, particularly to the Nuclear Physics and High-Energy Physics experimental programs, I discuss the progress that has been made toward achieving these goals and the challenges that remain.

  1. DESIGN ANALYSIS OF A PREPACKAGED NUCLEAR POWER PLANT (1000 eKW). VOLUME II. REACTOR DESIGN ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    None

    1959-02-01

    Reactor and primary and secondary system design analyses of a prepackaged nuclear power plant are presented. The plant is of the pressurized water steam-electric generating type which is air transportable skid mounted and suitable for a remote site installation. The plant design incorporates the maximum degree of reliability and simplicity and the minimum degree of maintenance and cost. The plant is capable of producing a gross electrical output of 1000 kw(e) and 5 x 10/sup 6/ Btu/hr for space heating. The primary system generates a total of 6.5 Mw of heat in order to supply the required electrical and heating load. (W.D.M.)

  2. Prospective benefits analysis of the DOE Nuclear Energy portfolio: NE R&D program data assumptions, approach, & results

    Energy Technology Data Exchange (ETDEWEB)

    Bhatt, Vatsal [Brookhaven National Lab. (BNL), Upton, NY (United States); Friley, Paul [Brookhaven National Lab. (BNL), Upton, NY (United States); Lee, John [Brookhaven National Lab. (BNL), Upton, NY (United States); Reisman, Ann [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2006-10-31

    The Office of Nuclear Energy (NE) leads the U.S. Government’s efforts to develop new nuclear energy generation technologies to meet energy and climate goals, and to develop advanced proliferation-resistant nuclear fuel technologies that maximize energy from nuclear fuel; contributes to the R&D for a possible transition to a hydrogen economy; and maintains and enhances the national nuclear technology infrastructure. NE serves the present and future energy needs of the Nation by managing the safe operation and maintenance of the Department of Energy (DOE) critical nuclear in frastructure, providing nuclear technology goods and services, and conducting R&D.

  3. ORIS: the Oak Ridge Imaging System program listings. [Nuclear medicine imaging with rectilinear scanner and gamma camera

    Energy Technology Data Exchange (ETDEWEB)

    Bell, P. R.; Dougherty, J. M.

    1978-04-01

    The Oak Ridge Imaging System (ORIS) is a general purpose access, storage, processing and display system for nuclear medicine imaging with rectilinear scanner and gamma camera. This volume contains listings of the PDP-8/E version of ORIS Version 2. The system is designed to run under the Digital Equipment Corporation's OS/8 monitor in 16K or more words of core. System and image file mass storage is on RK8E disk; longer-time image file storage is provided on DECtape. Another version of this program exists for use with the RF08 disk, and a more limited version is for DECtape only. This latter version is intended for non-medical imaging.

  4. Opportunities for Russian Nuclear Weapons Institute developing computer-aided design programs for pharmaceutical drug discovery. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-23

    The goal of this study is to determine whether physicists at the Russian Nuclear Weapons Institute can profitably service the need for computer aided drug design (CADD) programs. The Russian physicists` primary competitive advantage is their ability to write particularly efficient code able to work with limited computing power; a history of working with very large, complex modeling systems; an extensive knowledge of physics and mathematics, and price competitiveness. Their primary competitive disadvantage is their lack of biology, and cultural and geographic issues. The first phase of the study focused on defining the competitive landscape, primarily through interviews with and literature searches on the key providers of CADD software. The second phase focused on users of CADD technology to determine deficiencies in the current product offerings, to understand what product they most desired, and to define the potential demand for such a product.

  5. Protective role of Nigella sativa against experimentally induced type-II diabetic nuclear damage in Wistar rats

    Directory of Open Access Journals (Sweden)

    T. J. Sheikh

    2013-07-01

    Full Text Available Aim: To identify the anti-mutagenic effect of Nigella sativa on the experimentally induced chronic diabetes (type – II in Wistar rats.Materials and Methods: The anti-mutagenic effect was evaluated in Nigella sativa treated diabetic rats against the streptozotocin - nicotinamide (STZ-NA (at a dose rate of 45-110 i.p mg/kg b.wt for 90 days induced type-II diabetes mellitus using bone marrow micronucleus tests. The antioxidant status was tested by estimating the serum levels of lipid peroxidation and superoxide dismutase.Results: Our results indicated that diabetic rats treated with Nigella sativa decreased the frequency of micronuclei in the erythrocytes of bone marrow (P < 0.05 and enhanced the antioxidant status (P < 0.05 in the treated diabetic rats as compared to controls.Conclusion: The observations indicated that the diabetic patients are more prone to cell mutations which are related to the level of cellular oxidative status and it could be reduced by Nigella sativa.

  6. 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.

  7. Risk-based inservice testing program modifications at Palo Verde nuclear generating station

    Energy Technology Data Exchange (ETDEWEB)

    Knauf, S.; Lindenlaub, B.; Linthicum, R.

    1996-12-01

    Arizona Public Service Company (APS) is investigating changes to the Palo Verde Inservice Testing (IST) Program that are intended to result in the reduction of the required test frequency for various valves in the American Society of Mechanical Engineers (ASME) Section XI IST program. The analytical techniques employed to select candidate valves and to demonstrate that these frequency reductions are acceptable are risk based. The results of the Palo Verde probabilistic risk assessment (PRA), updated in June 1994, and the risk significant determination performed as part of the implementation efforts for 10 CFR 50.65 (the maintenance rule) were used to select candidate valves for extended test intervals. Additional component level evaluations were conducted by an `expert panel.` The decision to pursue these changes was facilitated by the ASME Risk-Based Inservice Testing Research Task Force for which Palo Verde is participating as a pilot plant. The NRC`s increasing acceptance of cost beneficial licensing actions and risk-based submittals also provided incentive to seek these changes. Arizona Public Service is pursuing the risk-based IST program modification in order to reduce the unnecessary regulatory burden of the IST program through qualitative and quantitative analysis consistent with maintaining a high level of plant safety. The objectives of this project at Palo Verde are as follows: (1) Apply risk-based technologies to IST components to determine their risk significance (i.e., high or low). (2) Apply a combination of deterministic and risk-based methods to determine appropriate testing requirements for IST components including improvement of testing methods and frequency intervals for high-risk significant components. (3) Apply risk-based technologies to high-risk significant components identified by the {open_quotes}expert panel{close_quotes} and outside of the IST program to determine whether additional testing requirements are appropriate.

  8. Phenology for Resource Management and Decision Making: Phase I and II Program Evaluation and Final Report

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This report summarizes the work completed on Phase I and II of the Project from September 1, 2014 through February 14, 2017. Included are the Goals and Objectives...

  9. DOE program guide for universities and other research groups. Part I. DOE Research and Development Programs; Part II. DOE Procurement and Assistance Policies/Procedures

    Energy Technology Data Exchange (ETDEWEB)

    1980-03-01

    This guide addresses the DOE responsibility for fostering advanced research and development of all energy resources, both current and potential. It is intended to provide, in a single publication, all the fundamental information needed by an institution to develop a potential working relationship with DOE. Part I describes DOE research and development programs and facilities, and identifies areas of additional research needs and potential areas for new research opportunities. It also summarizes budget data and identifies the DOE program information contacts for each program. Part II provides researchers and research administrators with an introduction to the DOE administrative policies and procedures for submission and evaluation of proposals and the administration of resulting grants, cooperative agreements, and research contracts. (RWR)

  10. Aerodynamic Accounting Technique for Determining Effects of Nuclear Damage to Aircraft. Volume 2. Program User Guide

    Science.gov (United States)

    1978-02-28

    444 4󈧰� IVu ,"~~~~~c ::2:::::;;:: I I 94994444V#~U4U444U4UJ4d.4j: w 3.3" 9J’U U4 . o4 4’j4 IVJ ""’IJ44lW4.4JC’) U, -7 LU x w4 44 l . 9...f 5 .I WPw4 N ~. N 9A T y I, w 4r Iwi D oU 4P P5I IV cP~ N ~ r.e ~ .oE I IVU ,.u~ d. ’ III II UPIN W - I 7S y -i - - - - - IV IV ty tAAAA. IV A 0

  11. Nuclear Medicine Program progress report for quarter ending September 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.

    1992-12-01

    The radioiodination and in vivo evaluation of p-iodocaramiphen a muscarinic antagonist which binds with high affinity to the M{sub 1} receptor subtype in vitro are described. Biodistribution studies in female Fischer rats demonstrated that [{sup 125}I]-piodocaraminphen had significant cerebral localization, but the uptake did not demonstrate specific uptake in those cerebral regions rich in muscarinic receptors, and radioactivity washed out rapidly from the brain. In addition there was no significant blockage of activity when the rats were preinjected with quinuclidinyl benzilate. These results suggest that p-iodocaramiphen is not a good candidate for the in vivo study of M{sub 1} muscarinic receptor populations by SPECT. Because of the widespread interest and expected importance of the availability of large amounts of tungsten-188 required for the tungsten-188/rhenium-188 generator systems, we have investigated the large-scale production of tungsten-188 in the ORNL HFIR. We have also compared our production data with the theoretical production values and with experimental data available in the literature from other reactors. Tungsten-188 is produced in a fission nuclear reactor by double neutron capture of tungsten-186. The experimental yield of tungsten-188 is approximately 4 mCi/mg of tungsten-186 at the end of bombardment (EOB) in the HFIR operating at 85 MWt power for a one cycle irradiation ({approximately}21 days) at a thermal neutron flux of 2 {times} 10{sup 15} n.s{sup {minus}1}cm{sup {minus}2}.

  12. Nuclear Medicine Program progress report for quarter ending September 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S.; Hasan, A.; Lambert, C.R.

    1992-12-01

    The radioiodination and in vivo evaluation of p-iodocaramiphen a muscarinic antagonist which binds with high affinity to the M[sub 1] receptor subtype in vitro are described. Biodistribution studies in female Fischer rats demonstrated that [[sup 125]I]-piodocaraminphen had significant cerebral localization, but the uptake did not demonstrate specific uptake in those cerebral regions rich in muscarinic receptors, and radioactivity washed out rapidly from the brain. In addition there was no significant blockage of activity when the rats were preinjected with quinuclidinyl benzilate. These results suggest that p-iodocaramiphen is not a good candidate for the in vivo study of M[sub 1] muscarinic receptor populations by SPECT. Because of the widespread interest and expected importance of the availability of large amounts of tungsten-188 required for the tungsten-188/rhenium-188 generator systems, we have investigated the large-scale production of tungsten-188 in the ORNL HFIR. We have also compared our production data with the theoretical production values and with experimental data available in the literature from other reactors. Tungsten-188 is produced in a fission nuclear reactor by double neutron capture of tungsten-186. The experimental yield of tungsten-188 is approximately 4 mCi/mg of tungsten-186 at the end of bombardment (EOB) in the HFIR operating at 85 MWt power for a one cycle irradiation ([approximately]21 days) at a thermal neutron flux of 2 [times] 10[sup 15] n.s[sup [minus]1]cm[sup [minus]2].

  13. Western Nuclear Science Alliance

    Energy Technology Data Exchange (ETDEWEB)

    Steve Reese; George Miller; Stephen Frantz; Denis Beller; Denis Beller; Ed Morse; Melinda Krahenbuhl; Bob Flocchini; Jim Elliston

    2010-12-07

    The primary objective of the INIE program is to strengthen nuclear science and engineering programs at the member institutions and to address the long term goal of the University Reactor Infrastructure and Education Assistance Program.

  14. Huntington II Simulation Program - PH. Student Workbook, Teacher's Guide, and Resource Handbook.

    Science.gov (United States)

    Friedland, James

    Described is the computer simulation program "PH." The program consists of three different laboratory investigations dealing with the pH specificity of enzymes. The purpose of the program is to enable tenth- to twelfth-grade students to determine a possible explanation for pH specificity in an experimental, but mathematical, fashion.…

  15. National Center for Advanced Information Components Manufacturing. Program summary report, Volume II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    The National Center for Advanced Information Components Manufacturing focused on manufacturing research and development for flat panel displays, advanced lithography, microelectronics, and optoelectronics. This report provides an overview of the program, program history, summaries of the technical projects, and key program accomplishments.

  16. Primary and secondary relaxation process in plastically crystalline cyanocyclohexane studied by 2H nuclear magnetic resonance. II. Quantitative analysis

    Science.gov (United States)

    Micko, B.; Kruk, D.; Rössler, E. A.

    2013-02-01

    We analyze the results of our previously reported 2H nuclear magnetic resonance (NMR) experiments in the plastically crystalline (PC) phase of cyanocyclohexane (Part I of this work) to study the fast secondary relaxation (or β-process) in detail. Both, the occurrence of an additional minimum in the spin-lattice relaxation T1 and the pronounced effects arising in the solid-echo spectrum above the glass transition temperature Tg = 134 K, allow for a direct determination of the restricting geometry of the β-process in terms of the "wobbling-in-a-cone" model. Whereas at temperatures below Tg the reorientation is confined to rather small solid angles (below 10°), the spatial restriction decreases strongly with temperature above Tg, i.e., the distribution of cone angles shifts continuously towards higher values. The β-process in the PC phase of cyanocyclohexane proceeds via the same mechanism as found in structural glass formers. This is substantiated by demonstrating the very similar behavior (for T log τβ⟩ (taken from dielectric spectroscopy). We do, however, not observe a clear-cut relation between the relaxation strength of the β-process observed by NMR (calculated within the wobbling-in-a-cone model) and dielectric spectroscopy.

  17. Annual Report Nucelar Energy Research and Development Program Nuclear Energy Research Initiative

    Energy Technology Data Exchange (ETDEWEB)

    Hively, LM

    2003-02-13

    NERI Project No.2000-0109 began in August 2000 and has three tasks. The first project year addressed Task 1, namely development of nonlinear prognostication for critical equipment in nuclear power facilities. That work is described in the first year's annual report (ORNLTM-2001/195). The current (second) project year (FY02) addresses Task 2, while the third project year will address Tasks 2-3. This report describes the work for the second project year, spanning August 2001 through August 2002, including status of the tasks, issues and concerns, cost performance, and status summary of tasks. The objective of the second project year's work is a compelling demonstration of the nonlinear prognostication algorithm using much more data. The guidance from Dr. Madeline Feltus (DOE/NE-20) is that it would be preferable to show forewarning of failure for different kinds of nuclear-grade equipment, as opposed to many different failure modes from one piece of equipment. Long-term monitoring of operational utility equipment is possible in principle, but is not practically feasible for the following reason. Time and funding constraints for this project do not allow us to monitor the many machines (thousands) that will be necessary to obtain even a few failure sequences, due to low failure rates (<10{sup -3}/year) in the operational environment. Moreover, the ONLY way to guarantee a controlled failure sequence is to seed progressively larger faults in the equipment or to overload the equipment for accelerated tests. Both of these approaches are infeasible for operational utility machinery, but are straight-forward in a test environment. Our subcontractor has provided such test sequences. Thus, we have revised Tasks 2.1-2.4 to analyze archival test data from such tests. The second phase of our work involves validation of the nonlinear prognostication over the second and third years of the proposed work. Recognizing the inherent limitations outlined in the previous

  18. 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".

  19. Nye County Nuclear Waste Repository Project Office independent scientific investigations program annual report, May 1997--April 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This annual summary report, prepared by the Nye County Nuclear Waste Repository Project Office (NWRPO), summarizes the activities that were performed during the period from May 1, 1997 to April 30, 1998. These activities were conducted in support of the Independent Scientific Investigation Program (ISIP) of Nye County at the Yucca Mountain Site (YMS). The Nye County NWRPO is responsible for protecting the health and safety of the Nye County residents. NWRPO`s on-site representative is responsible for designing and implementing the Independent Scientific Investigation Program (ISIP). Major objectives of the ISIP include: Investigating key issues related to conceptual design and performance of the repository that can have major impact on human health, safety, and the environment; identifying areas not being addressed adequately by the Department of Energy (DOE). Nye County has identified several key scientific issues of concern that may affect repository design and performance which were not being adequately addressed by DOE. Nye County has been conducting its own independent study to evaluate the significance of these issues. This report summarizes the results of monitoring from two boreholes and the Exploratory Studies Facility (ESF) tunnel that have been instrumented by Nye County since March and April of 1995. The preliminary data and interpretations presented in this report do not constitute and should not be considered as the official position of Nye County. The ISIP presently includes borehole and tunnel instrumentation, monitoring, data analysis, and numerical modeling activities to address the concerns of Nye County.

  20. Nuclear Science Division: 1993 Annual report

    Energy Technology Data Exchange (ETDEWEB)

    Myers, W.D. [ed.

    1994-06-01

    This report describes the activities of the Nuclear Science Division for the 1993 calendar year. This was another significant year in the history of the Division with many interesting and important accomplishments. Activities for the following programs are covered here: (1) nuclear structure and reactions program; (2) the Institute for Nuclear and Particle Astrophysics; (3) relativistic nuclear collisions program; (4) nuclear theory program; (5) nuclear data evaluation program, isotope project; and (6) 88-inch cyclotron operations.