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Sample records for volume ii nuclear

  1. Analysis of some nuclear waste management options. Volume II. Appendices

    International Nuclear Information System (INIS)

    Berman, L.E.; Ensminger, D.A.; Giuffre, M.S.; Koplik, C.M.; Oston, S.G.; Pollak, G.D.; Ross, B.I.

    1978-01-01

    This report describes risk analyses performed on that portion of a nuclear fuel cycle which begins following solidification of high-level waste. Risks associated with handling, interim storage and transportation of the waste are assessed, as well as the long term implications of disposal in deep mined cavities. The risk is expressed in terms of expected dose to the general population and peak dose to individuals in the population. This volume consists of appendices which provide technical details of the work performed

  2. Analysis of some nuclear waste management options. Volume II. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Berman, L.E.; Ensminger, D.A.; Giuffre, M.S.; Koplik, C.M.; Oston, S.G.; Pollak, G.D.; Ross, B.I.

    1978-10-10

    This report describes risk analyses performed on that portion of a nuclear fuel cycle which begins following solidification of high-level waste. Risks associated with handling, interim storage and transportation of the waste are assessed, as well as the long term implications of disposal in deep mined cavities. The risk is expressed in terms of expected dose to the general population and peak dose to individuals in the population. This volume consists of appendices which provide technical details of the work performed.

  3. Nuclear legislation analytical study. Regulatory and institutional framework for nuclear activities in OECD member countries. Volume II

    International Nuclear Information System (INIS)

    1984-01-01

    This study is part of a series of analytical studies of the major aspects of nuclear legislation in OECD Member countries and is published in two volumes. This volume II of the study is a revision and an expansion of a 1969 study concerning the organisation and general regime governing nuclear activities. The national studies were prepared, to the extent possible, following a standard plan for all countries to facilitate information retrieval and comparison. This volume also contains tables of international conventions of relevance to the nuclear field. (NEA) [fr

  4. 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.

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

    1977-01-01

    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

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

    International Nuclear Information System (INIS)

    1980-06-01

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

  8. Mean nuclear volume

    DEFF Research Database (Denmark)

    Mogensen, O.; Sørensen, Flemming Brandt; Bichel, P.

    1999-01-01

    We evaluated the following nine parameters with respect to their prognostic value in females with endometrial cancer: four stereologic parameters [mean nuclear volume (MNV), nuclear volume fraction, nuclear index and mitotic index], the immunohistochemical expression of cancer antigen (CA125...

  9. Recommended criteria for the evaluation of on-site nuclear power plant emergency plans, volume II: criteria

    International Nuclear Information System (INIS)

    1997-01-01

    A critical review of existing Canadian and international nuclear power plant (NPP) emergency plans, evaluation criteria, and approaches has been conducted to provide AECB staff with information which can be used to assess the adequacy of NPP on-site emergency response plans. The results of this work are published in two volumes. Volume I, Basis Document, provides the reasons why certain requirements are in place. It also gives comprehensive references to various standards.Volume II, Criteria, contains the criteria which relate to on-site actions and their integration with control room activities and the roles of off-site responsible organizations. The recommended criteria provide information on what is required, and not on how to accomplish the requirements. The licensees are given the latitude to decide on the methods and processes needed to meet the requirements. The documents do not address NPP off-site plans and response capability, or the control room emergency operating procedures and response capability. This report contains only Volume II: Criteria. 55 refs., 2 tabs., 1 fig

  10. In situ leaching of a nuclear rubblized copper ore body. Volume II

    International Nuclear Information System (INIS)

    1975-06-01

    This volume contains detailed descriptions of technical and economical evaluations undertaken for the feasibility study. A summary of these results can be found in Vol. 1 along with the conclusions derived from the feasibility study and the recommendations tendered for future work. The sections of this study are presented in process order, and each section is complete in itself. The form of the presentation, hopefully, is logical and in a manner suitable for design purposes. As a further aid, each section has its own table of contents. The sections presented include method of attack, reference case, description of concept, nuclear rubblization, blasting plan, underground plumbing, fluid circulation, leaching technology, wellhead plant and pipeline, process plant, material and heat balance, hydrology, radioactivity, seismic, economics, sensitivity analysis, guide for environmental studies, exploration, and recommended experimental program. (U.S.)

  11. Underwater Nuclear Fuel Disassembly and Rod Storage Process and Equipment Description. Volume II

    International Nuclear Information System (INIS)

    Viebrock, J.M.

    1981-09-01

    The process, equipment, and the demonstration of the Underwater Nuclear Fuel Disassembly and Rod Storage System are presented. The process was shown to be a viable means of increasing spent fuel pool storage density by taking apart fuel assemblies and storing the fuel rods in a denser fashion than in the original storage racks. The assembly's nonfuel-bearing waste is compacted and containerized. The report documents design criteria and analysis, fabrication, demonstration program results, and proposed enhancements to the system

  12. Status of volcanic hazard studies for the Nevada Nuclear Waste Storage Investigations. Volume II

    International Nuclear Information System (INIS)

    Crowe, B.M.; Wohletz, K.H.; Vaniman, D.T.; Gladney, E.; Bower, N.

    1986-01-01

    Volcanic hazard investigations during FY 1984 focused on five topics: the emplacement mechanism of shallow basalt intrusions, geochemical trends through time for volcanic fields of the Death Valley-Pancake Range volcanic zone, the possibility of bimodal basalt-rhyolite volcanism, the age and process of enrichment for incompatible elements in young basalts of the Nevada Test Site (NTS) region, and the possibility of hydrovolcanic activity. The stress regime of Yucca Mountain may favor formation of shallow basalt intrusions. However, combined field and drill-hole studies suggest shallow basalt intrusions are rare in the geologic record of the southern Great Basin. The geochemical patterns of basaltic volcanism through time in the NTS region provide no evidence for evolution toward a large-volume volcanic field or increases in future rates of volcanism. Existing data are consistent with a declining volcanic system comparable to the late stages of the southern Death Valley volcanic field. The hazards of bimodal volcanism in this area are judged to be low. The source of a 6-Myr pumice discovered in alluvial deposits of Crater Flat has not been found. Geochemical studies show that the enrichment of trace elements in the younger rift basalts must be related to an enrichment of their mantle source rocks. This geochemical enrichment event, which may have been metasomatic alteration, predates the basalts of the silicic episode and is, therefore, not a young event. Studies of crater dimensions of hydrovolcanic landforms indicate that the worst case scenario (exhumation of a repository at Yucca Mountain by hydrovolcanic explosions) is unlikely. Theoretical models of melt-water vapor explosions, particularly the thermal detonation model, suggest hydrovolcanic explosion are possible at Yucca Mountain. 80 refs., 21 figs., 5 tabs

  13. Nuclear physics II

    International Nuclear Information System (INIS)

    Elze, T.

    1988-01-01

    This script consisting of two parts contains the matter of the courses Nuclear Pyhsics I and II, as they were presented in the winter term 1987/88 and summer term 1988 for students of physics at Frankfurt University. In the present part II the matter of the summer term is summarized. (orig.) [de

  14. Advanced training course on state systems of accounting for and control of nuclear materials. Volume II. Visual aids

    International Nuclear Information System (INIS)

    Sorenson, R.J.; Schneider, R.A.

    1979-01-01

    Purpose of the course was to train in the accounting and control of nuclear materials in a bulk processing facility, for international safeguards. The Exxon low enriched uranium fabrication plant is used as an example. This volume contains visual aids used for the presentation

  15. Nuclear materials safeguards. Volume II. 1975--March 1976 (a bibliography with abstracts). Report for 1975--Mar 1976

    International Nuclear Information System (INIS)

    Grooms, D.W.

    1976-03-01

    Citations cover the methods of safeguarding nuclear materials through effective management, accountability, nondestructive assays, instrumentation, and automated continuous inventory systems. Problem areas and recommendations for improving the management of nuclear materials are included. (Contains 88 abstracts) See also NTIS/PS-76/0200, Nuclear Materials Safeguards. Vol. 1. 1964-1974 (A title bibliography)

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

    International Nuclear Information System (INIS)

    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

  17. Dynamic Isotope Power System (DIPS) Applications Study. Volume II. Nuclear Integrated Multimission Spacecraft (NIMS) design definition. Final report

    International Nuclear Information System (INIS)

    1979-11-01

    The design requirements for the Nuclear Integrated Multimission Spacecraft. (NIMS) are discussed in detail. The requirements are a function of mission specifications, payload, control system requirements, electric system specifications, and cost limitations

  18. Assessment and management of ageing of major nuclear power plant components important to safety: In-containment instrumentation and control cables. Volume II

    International Nuclear Information System (INIS)

    2000-12-01

    and technical support organizations dealing with specific plant components addressed in the reports. The component addressed in the present report is the in-containment instrumentation and control (I and C) cables. The report presents, in two volumes, results of a Co-ordinated Research Project (CRP) on the Management of Ageing of In-containment Instrumentation and Control cables. Part I, Volume 1 presents information on current methods for assessing and managing ageing degradation of Instrumentation and Control cables in real NPP environments prepared by the CRP team. An important complement of this information is user perspectives on the application of these methods which are presented in Part II, Volume 1. Volume 2 contains annexes supporting the guidance of Volume 1 with more detailed information and examples provided by individual CRP participants. For a quick overview, readers should see Section 8 of Part I, Volume 1, which describes a systematic ageing management programme for Instrumentation and Control cables utilizing methods presented in the report; Section 9 of Part I, Volume 1, which presents CRP conclusions and recommendations; and Part II providing the application guidance from the user's perspective

  19. Nuclear Electric Propulsion mission engineering study covering the period April 1971 to January 1973. Volume II. Final report

    International Nuclear Information System (INIS)

    1973-03-01

    The results of a mission engineering analysis of nuclear-thermionic electric propulsion spacecraft for unmanned interplanetary and geocentric missions are summarized. Critical technologies assessed are associated with the development of Nuclear Electric Propulsion (NEP), and the impact of its availability on future space programs. Specific areas of investigation include outer planet and comet rendezvous mission analysis, NEP Stage design for geocentric and interplanetary missions NEP system development cost and unit costs, and technology requirements for NEP Stage development. A multi-mission NEP Stage can be developed to perform both multiple geocentric and interplanetary missions. Development program costs for a 1983 launch would be of the order of $275 M, including hardware and reactor development, flight system hardware, and mission support. Recurring unit costs for flight NEP systems would be of the order of $25 M for a 120kWe NEP Stage. Identified pacing NEP technology requirements are the development of 20,000 full power hour ion thrusters and thermionic reactor, and the development of related power conditioning. The resulting NEP Stage design provides both inherent reliability and high payload mass capability. High payload mass capability can be translated into both low payload cost and high payload reliability. NEP Stage and payload integration is compatible with the Space Shuttle

  20. Exxon Nuclear Company WREM-based generic PWR ECCS evaluation model. Appendix C to Volume II. Yankee Rowe example problem

    International Nuclear Information System (INIS)

    1975-01-01

    Core 12, of the Yankee Rowe (YR), plant is to be licensed with the Exxon Nuclear Co. PWR Evaluation Model. This appendix presents methodology and results of an example calculation for the YR plant using the ENC Evaluation Model. This example problem is for the double-ended guillotine cold leg break with a discharge coefficient of 0.6 assuming loss of one emergency diesel. The NSSS supplier has determined this case to give the highest peak cladding temperature (PCT) for Core 11. The YR example problem was performed to determine the maximum acceptable local peak heating rate (Kw/ft). The blowdown was performed with beginning-of-cycle (BOC) ENC fuel at full power with the hot assembly power corresponding to the design peak rod heating rate of 12.9 Kw/ft. The HOT CHANNEL, TOODEE2, and RELAP4-FLOOD runs were made at several reduced hot assembly radial peaks, holding axial peaking constant, until an acceptable PCT was achieved. This procedure results in a PCT of 1834 0 F at a reduced peak linear heating rate of 10.5 Kw/ft for the ENC fuel at BOC. (auth)

  1. Human factors analysis and design methods for nuclear waste retrieval systems. Volume II. A compendium of human factors design data

    International Nuclear Information System (INIS)

    Casey, S.M.

    1980-04-01

    This document is a compilation of human factors engineering design recommendations and data, selected and organized to assist in the design of a nuclear waste retrieval system. Design guidelines from a variety of sources have been evaluated, edited, and expanded for inclusion in this document, and, where appropriate, portions of text from selected sources have been included in their entirety. A number of human factors engineering guidelines for equipment designers have been written over the past three decades, each tailored to the needs of the specific system being designed. In the case of this particular document, a review of the preliminary human operator functions involved in each phase of the retrieval process was performed, resulting in the identification of areas of design emphasis upon which this document should be based. Documents containing information and design data on each of these areas were acquired, and data and design guidelines related to the previously identified areas of emphasis were extracted and reorganized. For each system function, actions were first assigned to operator and/or machine, and the operator functions were then described. Separate lists of operator functions were developed for each of the areas of retrieval activities - survey and mapping, remining, floor flange emplacement, plug and canister overcoring, plug and canister removal and transport, and CWSRS activity. These functions and the associated man-machine interface were grouped into categories based on task similarity, and the principal topics of human factors design emphasis were extracted. These topic areas are reflected in the contents of the 12 sections of this document

  2. Deep repository for spent nuclear fuel. SR-97-Post-closure safety. Main Report. Volume I and II

    International Nuclear Information System (INIS)

    Hedin, A.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10 -6 per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in buffer, geosphere

  3. Deep repository for spent nuclear fuel. SR-97-Post-closure safety. Main Report. Volume I and II

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, A [ed.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10{sup -6} per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in buffer

  4. Deep repository for spent nuclear fuel. SR-97-Post-closure safety. Main Report. Volume I and II

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, A. [ed.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10{sup -6} per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in

  5. 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

  6. DART II documentation. Volume III. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    1979-10-01

    The DART II is a remote, interactive, microprocessor-based data acquistion system suitable for use with air monitors. This volume of DART II documentation contains the following appendixes: adjustment and calibration procedures; mother board signature list; schematic diagrams; device specification sheets; ROM program listing; 6800 microprocessor instruction list, octal listing; and cable lists. (RWR)

  7. Site Environmental Report for 1998 Volume II

    International Nuclear Information System (INIS)

    Ruggieri, Michael

    1999-01-01

    Volume II of the Site Environment Report for 1998 is provided by Ernest Orlando Lawrence Berkeley National Laboratory as a supplemental appendix to the report printed in volume I. Volume II contains the environmental monitoring and sampling data used to generate summary results in the main report for routine and non routine activities at the Laboratory (except for groundwater sampling data, which may be found in the reports referred to in chapter 6). Data presented in the tables are given in International System of Units (SI) units of measure

  8. Comparison between dispersed nuclear power plants and a nuclear energy center at a hypothetical site on Kentucky Lake, Tennessee. Volume II. Transmission of power

    International Nuclear Information System (INIS)

    Reister, D.B.; Zelby, L.W.

    1976-05-01

    A comparison is made among power transmission systems required to serve a single set of load center demands from four modes of siting the generating facilities: a single generation site with an ultimate generation capacity of 48,000 MW; four generation sites each with a generation capacity of 12,000 MW; 10 generation sites each with a generation capacity of 4,800 MW; and a system that resulted when the existing utility plan for future generation was logically expanded. The time period for the study is from the year 1985 to the year 2020, when the full 48,000 MW of new capacity from the single large nuclear energy center is on-line. The load centers served are Huntsville, Alabama; Evansville, Indiana; Paducah, Kentucky; and Chattanooga, Nashville, and Memphis, Tennessee. Generation sites are real locations but are hypothetical in terms of miles of transmission lines, the product of the amount of power transmitted and the distance transmitted (GW-miles), and cost

  9. ALICE: Physics Performance Report, Volume II

    International Nuclear Information System (INIS)

    Alessandro, B; Antinori, F; Belikov, J A

    2006-01-01

    ALICE is a general-purpose heavy-ion experiment designed to study the physics of strongly interacting matter and the quark-gluon plasma in nucleus-nucleus collisions at the LHC. It currently involves more than 900 physicists and senior engineers, from both the nuclear and high-energy physics sectors, from over 90 institutions in about 30 countries. The ALICE detector is designed to cope with the highest particle multiplicities above those anticipated for Pb-Pb collisions (dN ch /dy up to 8000) and it will be operational at the start-up of the LHC. In addition to heavy systems, the ALICE Collaboration will study collisions of lower-mass ions, which are a means of varying the energy density, and protons (both pp and pA), which primarily provide reference data for the nucleus-nucleus collisions. In addition, the pp data will allow for a number of genuine pp physics studies. The detailed design of the different detector systems has been laid down in a number of Technical Design Reports issued between mid-1998 and the end of 2004. The experiment is currently under construction and will be ready for data taking with both proton and heavy-ion beams at the start-up of the LHC. Since the comprehensive information on detector and physics performance was last published in the ALICE Technical Proposal in 1996, the detector, as well as simulation, reconstruction and analysis software have undergone significant development. The Physics Performance Report (PPR) provides an updated and comprehensive summary of the performance of the various ALICE subsystems, including updates to the Technical Design Reports, as appropriate. The PPR is divided into two volumes. Volume I, published in 2004 (CERN/LHCC 2003-049, ALICE Collaboration 2004 J. Phys. G: Nucl. Part. Phys. 30 1517-1763), contains in four chapters a short theoretical overview and an extensive reference list concerning the physics topics of interest to ALICE, the experimental conditions at the LHC, a short summary and update

  10. RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume II. Program implementation

    International Nuclear Information System (INIS)

    1976-06-01

    A discussion is presented of the use of the RELAP4/MOD5 computer program in simulating the thermal-hydraulic behavior of light-water reactor systems when subjected to postulated transients such as a LOCA, pump failure, or nuclear excursion. The volume is divided into main sections which cover: (1) program description, (2) input data, (3) problem initialization, (4) user guidelines, (5) output discussion, (6) source program description, (7) implementation requirements, (8) data files, (9) description of PLOTR4M, (10) description of STH20, (11) summary flowchart, (12) sample problems, (13) problem definition, and (14) problem input

  11. TIBER II/ETR final design report: Volume 2, 3.0 Engineering

    International Nuclear Information System (INIS)

    Lee, J.D.

    1987-09-01

    This paper discusses the design of the TIBER II Tokamak. This particular volume discusses: mechanical systems; electrical systems; shield nuclear analysis and tritium issues; reactor building facilities; and tritium systems

  12. International Nuclear Model. Volume 3. Program description

    International Nuclear Information System (INIS)

    Andress, D.

    1985-01-01

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

  13. Hanford spent nuclear fuel project recommended path forward, volume III: Alternatives and path forward evaluation supporting documentation

    International Nuclear Information System (INIS)

    Fulton, J.C.

    1994-10-01

    Volume I of the Hanford Spent Nuclear Fuel Project - Recommended Path Forward constitutes an aggressive series of projects to construct and operate systems and facilities to safely retrieve, package, transport, process, and store K Basins fuel and sludge. Volume II provided a comparative evaluation of four Alternatives for the Path Forward and an evaluation for the Recommended Path Forward. Although Volume II contained extensive appendices, six supporting documents have been compiled in Volume III to provide additional background for Volume II

  14. Phonons: Theory and experiments II. Volume 2

    International Nuclear Information System (INIS)

    Bruesch, P.

    1986-01-01

    The present second volume titled as ''Phonons: Theory and Experiments II'', contains, a thorough study of experimental techniques and the interpretation of experimental results. This three-volume set tries to bridge the gap between theory and experiment, and is addressed to those working in both camps in the vast field of dynamical properties of solids. Topics presented in the second volume include; infrared-, Raman and Brillouin spectroscopy, interaction of X-rays with phonons, and inelastic neutron scattering. In addition an account is given of some other techniques, including ultrasonic methods, inelastic electron tunneling spectroscopy, point contact spectroscopy, and spectroscopy of surface phonons, thin films and adsorbates. Both experimental aspects and theoretical concepts necessary for the interpretation of experimental data are discussed. An attempt is made to present the descriptive as well as the analytical aspects of the topics. Simple models are often used to illustrate the basic concepts and more than 100 figures are included to illustrate both theoretical and experimental results. Many chapters contain a number of problems with hints and results giving additional information

  15. Nuclear power. Volume 1. Nuclear power plant design

    International Nuclear Information System (INIS)

    Pedersen, E.S.

    1978-01-01

    NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 1 contains the following chapters; (1) nuclear reactor theory; (2) nuclear reactor design; (3) types of nuclear power plants; (4) licensing requirements; (5) shielding and personnel exposure; (6) containment and structural design; (7) main steam and turbine cycles; (8) plant electrical system; (9) plant instrumentation and control systems; (10) radioactive waste disposal (waste management) and (11) conclusion

  16. Site Environmental Report for 2005 Volume I and Volume II

    Energy Technology Data Exchange (ETDEWEB)

    Ruggieri, Michael

    2006-07-07

    Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, ''Environment, Safety, and Health Reporting''. The ''Site Environmental Report for 2005'' summarizes Berkeley Lab's environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2005. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as ''Berkeley Lab'', ''the Laboratory'', ''Lawrence Berkeley National Laboratory'', and ''LBNL''.) The report is separated into two volumes. Volume I contains an overview of the Laboratory, the status of environmental programs, and summarized results from surveillance and monitoring activities. This year's Volume I text body is organized into an executive summary followed by six chapters. The report's structure has been reorganized this year, and it now includes a chapter devoted to environmental management system topics. Volume II contains individual data results from surveillance and monitoring activities. The ''Site Environmental Report'' is distributed by releasing it on the Web from the Berkeley Lab Environmental Services Group (ESG) home page, which is located at http://www.lbl.gov/ehs/esg/. Many of the documents cited in this report also are accessible from the ESG Web page. CD and printed copies of this Site Environmental Report are available upon request. The report follows the Laboratory's policy of using the International System of Units (SI), also known as the metric system of measurements. Whenever possible, results are also reported using the more conventional (non-SI) system of measurements, because the non-SI system is referenced by several current

  17. 2000 Physical Acoustics Summer School (PASS 00). Volume II: Transparencies

    National Research Council Canada - National Science Library

    Bass, Henry

    2001-01-01

    .... Volume II of these proceedings contains copies of the transparencies used by the lecturers and Volume III contains background materials that were sent to student and discussion leader participants...

  18. Nuclear power. Volume 2. Nuclear power project management

    International Nuclear Information System (INIS)

    Pedersen, E.S.

    1978-01-01

    NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 2 contains the following chapters: (1) review of nuclear power plants; (2) licensing procedures; (3) safety analysis; (4) project professional services; (5) quality assurance and project organization; (6) construction, scheduling, and operation; (7) nuclear fuel handling and fuel management; (8) plant cost management; and (9) conclusion

  19. Progress in nuclear energy. Volume 10

    International Nuclear Information System (INIS)

    Williams, M.M.R.; McCormick, N.J.

    1983-01-01

    This book consists of 15 articles written by specialists in the field of atomic energy. A significant portion of this volume is devoted to a special section reporting on the impact of the accident at Three Mile Island on the nuclear power industry. Changes in reactor instrumentation, operator training, and emergency preparedness are discussed in detail. A paper reporting on the effects of the accident on the public's attitude toward nuclear power is included in this section. Contents, abridged: The safety of CO 2 cooled reactor technology. Denaturing fissile materials. Impact of the Three Mile Island accident on the nuclear power industry; changes in the nuclear power industry after TMI; impact of TMI on combustion engineering technical activities. Impact of the accident at Three Mile Island on a NSSS vendor--a Westinghouse perspective; emergency planning and preparedness since Three Mile Island. The impact of TMI upon the public acceptance of nuclear power

  20. Environmental monitoring and ecological studies program. 1974 annual report for the Prairie Island Nuclear Generating Plant near Red Wing, Minnesota. Volume II

    International Nuclear Information System (INIS)

    1975-06-01

    Data are presented from studies on the effects of thermal effluents from the Prairie Island nuclear power plant on fish and invertebrate populations in the Mississippi River in the vicinity of the plant. Populations of aquatic and terrestrial plants and birds in the immediate vicinity of the plant were also characterized. (U.S.)

  1. Nuclear India. Vol. II. [India's nuclear policy

    Energy Technology Data Exchange (ETDEWEB)

    Jain, J P

    1974-01-01

    The book contains 186 documents on India's nuclear policy covering a period from November 1948 to May 1974. It thus forms a comprehensive documentary account of India's nuclear policy. They include: texts of India's agreements for cooperation on the peaceful uses of atomic energy with the USA and Canada, the summary conclusions of India's atomic energy program for the decade 1970-80, the resolutions and amendments moved by India, the communications sent and the statements made by Indian representatives in various international forums--the conference of the IAEA statute, the Annual General Conference of the IAEA and its committees and the Board of Governors, the UN General Assembly and its First Committee, the conference of the Committee on Disarmaments etc. It also contains texts or extracts from the papers presented, statements made, and addresses and talks delivered by H. J. Bhabha, V. A. Sarabhai, H. N. Sethna and other eminent scientists at the international conferences on the peaceful uses of atomic energy, IAEA discussions on PNE, etc. Policy statements by India's Prime Ministers Nehru, Shastri and (Mrs.) Gandhi, and Foreign Ministers Chagla and Swaran Singh, made from time to time in the Lok Sabha and the Rajya Sabha--the two houses of the Indian parliaments--are also included. The sources of these documents are listed at the end. (MCB)

  2. Fixed site neutralization model programmer's manual. Volume II

    International Nuclear Information System (INIS)

    Engi, D.; Chapman, L.D.; Judnick, W.; Blum, R.; Broegler, L.; Lenz, J.; Weinthraub, A.; Ballard, D.

    1979-12-01

    This report relates to protection of nuclear materials at nuclear facilities. This volume presents the source listings for the Fixed Site Neutralization Model and its supporting modules, the Plex Preprocessor and the Data Preprocessor

  3. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume 1. Program summary

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. This introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings and recommendations. Each of Volumes II-VII reports on an individual assessment (Volume II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP.

  4. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume 1. Program summary

    International Nuclear Information System (INIS)

    1979-12-01

    This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. This introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings and recommendations. Each of Volumes II-VII reports on an individual assessment (Volume II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP

  5. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Volume II. A report to the President's Commission on the Accident at Three Mile Island

    International Nuclear Information System (INIS)

    Bretthauer, E.W.; Grossman, R.F.; Thome, D.J.; Smith, A.E.

    1981-03-01

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. The original report was printed in September 1979 and the update was released in December 1979. Table 6-Summary of Department of Health, Education, and Welfare (HEW) sampling and analytical procedures; Table 7-Computer printout of environmental data collected by HEW; Table 8-Summary of US Nuclear Regulatory Commission (NRC) sampling and analytical procedures

  6. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume I. Program summary

    International Nuclear Information System (INIS)

    1980-06-01

    This report summarizes the Nonproliferation Alternative Systems Assessment Program (NASAP): its background, its studies, and its results. The introductory chapter traces the growth of the issue of nuclear weapons proliferation and the organization and objectives of NASAP. Chapter 2 summarizes the program's assessments, findings, and recommendations. Each of Volumes II-VII reports on an individual assessment (Volumn II: Proliferation Resistance; Volume III: Resources and Fuel Cycle Facilities; Volume IV: Commercial Potential; Volume V: Economics and Systems Analysis; Volume VI: Safety and Environmental Considerations for Licensing; Volume VII: International Perspectives). Volume VIII (Advanced Concepts) presents a combined assessment of several less fully developed concepts, and Volume IX (Reactor and Fuel Cycle Descriptions) provides detailed descriptions of the reactor and fuel-cycle systems studied by NASAP

  7. Nuclear medicine and thyroid disease - part II

    International Nuclear Information System (INIS)

    Chatterton, B.E.

    2005-01-01

    Part 1 of this article discussed the anatomy, physiology and basic pathology of the thyroid gland. Techniques of thyroid scanning and a few clinical examples are shown part II Copyright (2005) The Australian and New Zealand Society Of Nuclear Medicine Inc

  8. Stereological analysis of nuclear volume in recurrent meningiomas

    DEFF Research Database (Denmark)

    Madsen, C; Schrøder, H D

    1994-01-01

    A stereological estimation of nuclear volume in recurrent and non-recurrent meningiomas was made. The aim was to investigate whether this method could discriminate between these two groups. We found that the mean nuclear volumes in recurrent meningiomas were all larger at debut than in any...... of the control tumors. The mean nuclear volume of the individual recurrent tumors appeared to change with time, showing a tendency to diminish. A relationship between large nuclear volume at presentation and number of or time interval between recurrences was not found. We conclude that measurement of mean...... nuclear volume in meningiomas might help identify a group at risk of recurrence....

  9. Index to Nuclear Safety: a technical progress review by chrology, permuted title, and author, Volume 11(1) through Volume 20(6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W B; Passiakos, M

    1980-06-01

    This index to Nuclear Safety, a bimonthly technical progress review, covers articles published in Nuclear Safety, Volume II, No. 1 (January-February 1970), through Volume 20, No. 6 (November-December 1979). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 600 technical articles published in Nuclear Safety in the last ten years are listed in this index.

  10. Nuclear spectroscopy with direct relations II. Proceedings

    International Nuclear Information System (INIS)

    Throw, F. E.

    1964-01-01

    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

  11. Fiscal year 1985 Department of Energy authorization (high-energy and nuclear physics). Volume II-B. Hearing before the Subcommittee on Energy Development and Applications of the Committee on Science and Technology, US House of Representatives, Ninety-Eighth Congress, Second Session, February 22, 1984

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    Volume II-B of the DOE authorization hearings for fiscal year 1985 covers testimony on high-energy and nuclear physics programs. The volume opens with a continuation of Appendix I, which contains questions directed at Dr. Alvin Trivelpiece and his responses on research at several laboratories and four construction projects. The latter include general plant projects, the Continuous Electron Beam Accelerator Facility, the Tandem/AGS Heavy Ion Transfer Line, and the University Accelerator Upgrade at the University of Washington and Yale. Two 1983 DOE/National Science Foundation reports make up Appendix II. The volume concludes with the text of the 1985 budget request for $746,105,000 and a breakdown of line item expenditures

  12. Blanket comparison and selection study. Volume II

    International Nuclear Information System (INIS)

    1983-10-01

    This volume contains extensive data for the following chapters: (1) solid breeder tritium recovery, (2) solid breeder blanket designs, (3) alternate blanket concept screening, and (4) safety analysis. The following appendices are also included: (1) blanket design guidelines, (2) power conversion systems, (3) helium-cooled, vanadium alloy structure blanket design, (4) high wall loading study, and (5) molten salt safety studies

  13. Bibliography of Utah radioactive occurrences. Volume II

    International Nuclear Information System (INIS)

    Doelling, H.H.

    1983-07-01

    The references in this bibliography were assembled by reviewing published bibliographies of Utah geology, unpublished reports of the US Geological Survey and the Department of Energy, and various university theses. Each of the listings is cross-referenced by location and subject matter. This report is published in two volumes

  14. AJER VOLUME II-JULY 2014

    African Journals Online (AJOL)

    user

    African Journal of Economic Review, Volume 1I, Issue 2, July 2014 ..... This paper also carries out the Chow-break point test (stability test) to test .... Unlike other East African countries, Rwanda has had a lot of political instabilities characterized.

  15. Stereological estimation of nuclear mean volume in invasive meningiomas

    DEFF Research Database (Denmark)

    Madsen, C; Schrøder, H D

    1996-01-01

    A stereological estimation of nuclear mean volume in bone and brain invasive meningiomas was made. For comparison the nuclear mean volume of benign meningiomas was estimated. The aim was to investigate whether this method could discriminate between these groups. We found that the nuclear mean...... volume in the bone and brain invasive meningiomas was larger than in the benign tumors. The difference was significant and moreover it was seen that there was no overlap between the two groups. In the bone invasive meningiomas the nuclear mean volume appeared to be larger inside than outside the bone....... No significant difference in nuclear mean volume was found between brain and bone invasive meningiomas. The results demonstrate that invasive meningiomas differ from benign meningiomas by an objective stereological estimation of nuclear mean volume (p

  16. European Nuclear Decommissioning Training Facility II

    International Nuclear Information System (INIS)

    Demeulemeester, Y.

    2005-01-01

    SCK-CEN co-ordinates a project called European Nuclear Decommissioning Training Facility II (EUNDETRAF II) in the Sixth Framework Programme on Community activities in the field of research, technological development and demonstration for the period 2002 to 2006. This was a continuation of the FP5 project EUNDETRAF. EUNDETRAF II is a consortium of main European decommissioners, such as SCK-CEN, EWN (Energie Werke Nord, Greifswald Germany), Belgatom (Belgium), SOGIN Societa Gestione Impiantio Nucleari, Italy), Universitaet Hannover (Germany), RWE NUKEM (United Kingdom), DECOM Slovakia Slovakia), CEA Centre d'Energie Atomique, France), UKAEA (United Kingdom's Atomic Energy Agency, United Kingdom) and NRG (Nuclear Research and consultancy Group, Netherlands). The primary objective of this project is to bring together this vast skill base and experience; to consolidate it for easy assimilation and to transfer to future generations by organising a comprehensive training programme.Each training course has a one-week theoretical and a one-week practical component. The theoretical part is for a broader audience and consists of lectures covering all the main aspects of a decommissioning. The practical part of the course includes site visits and desk top solutions of anticipated decommissioning problems. Due to operational constraints and safety considerations, the number of participants to this part of the course is strictly limited. The partners intend to organise altogether two two-week EUNDETRAF II training courses over a period of three years. Another goal is to disseminate the existing theory as well as the practical know-how to personnel of the third countries. Finally it is important to bring together the principal decommissioning organisations undertaking various decommissioning activities. The project creates a forum for regular contacts to exchange information and experiences for mutual benefit of these organisations as well as to enhance skill base in Europe to

  17. Fusion Engineering Device. Volume II. Design description

    International Nuclear Information System (INIS)

    1981-10-01

    This volume summarizes the design of the FED. It includes a description of the major systems and subsystems, the supporting plasma design analysis, a projected device cost and associated construction schedule, and a description of the facilities to house and support the device. This effort represents the culmination of the FY81 studies conducted at the Fusion Engineering Design Center (FEDC). Unique in these design activities has been the collaborative involvement of the Design Center personnel and numerous resource physicists from the fusion community who have made significant contributions in the physics design analysis as well as the physics support of the engineering design of the major FED systems and components

  18. 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.

  19. Airborne radioactive emission control technology. Volume II

    International Nuclear Information System (INIS)

    Skoski, L.; Berlin, R.; Corby, D.; Clancy, J.; Hoopes, G.

    1980-03-01

    This report reviews the current and future control technology for airborne emissions from a wide variety of industries/facilities, including uranium mining and milling, other nuclear fuel cycle facilities, other NRC-licensed and DOE facilities, fossil fuel facilities, selected metal and non-metal extraction industries, and others. Where specific radioactivity control technology is lacking, a description of any existing control technology is given. Future control technology is assessed in terms of improvements to equipment performance and process alterations. A catalogue of investigated research on advanced control technologies is presented

  20. Free radicals in biology. Volume II

    International Nuclear Information System (INIS)

    Pryor, W.A.

    1976-01-01

    This volume continues the treatment of topics in free radical biology and free radical pathology from Volume I. In the first chapter, pyridinyl radicals, radicals which are models for those derived from NAD, are discussed. Pyridinyl radicals can be synthesized and isolated and directly studied in a number of chemical systems. The next chapter treats the role of glutathione in the cell. It is becoming even more apparent that this vital thiol controls a large number of important cellular functions. The GSH/GSSG balance has recently been implicated as a control for cellular development; this balance also may be important in relaying the effects of oxidants from one site to another in the body. The next chapter outlines the reactions of singlet oxygen; some of these involve free radicals and some do not. This reactive intermediate appears to be important both in photochemical smog and in cellular chemistry where singlet oxygen is produced by nonphotochemical processes. The production of free radicals from dry tissues, a controversial area with conflicting claims is reviewed. The next chapter outlines the current status of the studies of photochemical smog. The next two chapters treat specific reactive materials which are present in smog. The first discusses the chemistry of nitrogen oxides and ozone. The second chapter treats the chemistry of the peroxyacyl nitrites. These compounds, although present in only small concentration, are among the most toxic components of smog. The last two chapters treat radiation damage to proteins and radiation protection and radical reactions produced by radiation in nucleic acids

  1. Draft Strategic Laboratory Missions Plan. Volume II

    International Nuclear Information System (INIS)

    1996-03-01

    This volume described in detail the Department's research and technology development activities and their funding at the Department's laboratories. It includes 166 Mission Activity Profiles, organized by major mission area, with each representing a discrete budget function called a Budget and Reporting (B ampersand R) Code. The activities profiled here encompass the total research and technology development funding of the laboratories from the Department. Each profile includes a description of the activity and shows how the funding for that activity is distributed among the DOE laboratories as well as universities and industry. The profiles also indicate the principal laboratories for each activity, as well as which other laboratories are involved. The information in this volume is at the core of the Strategic Laboratory Mission Plan. It enables a reader to follow funds from the Department's appropriation to a specific activity description and to specific R ampersand D performing institutions. This information will enable the Department, along with the Laboratory Operations Board and Congress, to review the distribution of R ampersand D performers chosen to execute the Department's missions

  2. Draft Strategic Laboratory Missions Plan. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    This volume described in detail the Department`s research and technology development activities and their funding at the Department`s laboratories. It includes 166 Mission Activity Profiles, organized by major mission area, with each representing a discrete budget function called a Budget and Reporting (B & R) Code. The activities profiled here encompass the total research and technology development funding of the laboratories from the Department. Each profile includes a description of the activity and shows how the funding for that activity is distributed among the DOE laboratories as well as universities and industry. The profiles also indicate the principal laboratories for each activity, as well as which other laboratories are involved. The information in this volume is at the core of the Strategic Laboratory Mission Plan. It enables a reader to follow funds from the Department`s appropriation to a specific activity description and to specific R & D performing institutions. This information will enable the Department, along with the Laboratory Operations Board and Congress, to review the distribution of R & D performers chosen to execute the Department`s missions.

  3. Introduction to "Global Tsunami Science: Past and Future, Volume II"

    Science.gov (United States)

    Rabinovich, Alexander B.; Fritz, Hermann M.; Tanioka, Yuichiro; Geist, Eric L.

    2017-08-01

    Twenty-two papers on the study of tsunamis are included in Volume II of the PAGEOPH topical issue "Global Tsunami Science: Past and Future". Volume I of this topical issue was published as PAGEOPH, vol. 173, No. 12, 2016 (Eds., E. L. Geist, H. M. Fritz, A. B. Rabinovich, and Y. Tanioka). Three papers in Volume II focus on details of the 2011 and 2016 tsunami-generating earthquakes offshore of Tohoku, Japan. The next six papers describe important case studies and observations of recent and historical events. Four papers related to tsunami hazard assessment are followed by three papers on tsunami hydrodynamics and numerical modelling. Three papers discuss problems of tsunami warning and real-time forecasting. The final set of three papers importantly investigates tsunamis generated by non-seismic sources: volcanic explosions, landslides, and meteorological disturbances. Collectively, this volume highlights contemporary trends in global tsunami research, both fundamental and applied toward hazard assessment and mitigation.

  4. Nuclear Power Options Viability Study. Volume 3. Nuclear discipline topics

    International Nuclear Information System (INIS)

    Trauger, D.B.; White, J.D.; Bowers, H.I.

    1986-09-01

    Innovative reactor concepts are described and evaluated in accordance with criteria established in the study. The reactors to be studied were chosen on the basis of three ground rules: (1) the potential for commercialization between 2000-2010, (2) economic competiveness with coal-fired plants, and (3) the degree of passive safety in the design. The concepts, classified by coolants, were light water reactors, liquid metal reactors, and high temperature reactors, and most were of modular design. All the concepts appear to be potentially viable in the time frame selected, but the information available is not adequate for a definitive evaluation of their economic competitiveness. This volume primarily reports in greater detail on several topics from the study. These are: Construction, Economics, Regulation, Safety and Economic Risk, Nuclear Waste Transportation and Disposal, and Market Acceptance. Although treated generically, the topics are presented in the context of the reactor concepts of the study

  5. Nuclear Power Options Viability Study. Volume 3. Nuclear discipline topics

    Energy Technology Data Exchange (ETDEWEB)

    Trauger, D B; White, J D; Bowers, H I; Braid, R B; Cantor, R A; Daniels, L; Davis, R M; Delene, J G; Gat, U; Hood, T C

    1986-09-01

    Innovative reactor concepts are described and evaluated in accordance with criteria established in the study. The reactors to be studied were chosen on the basis of three ground rules: (1) the potential for commercialization between 2000-2010, (2) economic competiveness with coal-fired plants, and (3) the degree of passive safety in the design. The concepts, classified by coolants, were light water reactors, liquid metal reactors, and high temperature reactors, and most were of modular design. All the concepts appear to be potentially viable in the time frame selected, but the information available is not adequate for a definitive evaluation of their economic competitiveness. This volume primarily reports in greater detail on several topics from the study. These are: Construction, Economics, Regulation, Safety and Economic Risk, Nuclear Waste Transportation and Disposal, and Market Acceptance. Although treated generically, the topics are presented in the context of the reactor concepts of the study.

  6. Survey of Biomass Gasification, Volume II: Principles of Gasification

    Energy Technology Data Exchange (ETDEWEB)

    Reed, T.B. (comp.)

    1979-07-01

    Biomass can be converted by gasification into a clean-burning gaseous fuel that can be used to retrofit existing gas/oil boilers, to power engines, to generate electricity, and as a base for synthesis of methanol, gasoline, ammonia, or methane. This survey describes biomass gasification, associated technologies, and issues in three volumes. Volume I contains the synopsis and executive summary, giving highlights of the findings of the other volumes. In Volume II the technical background necessary for understanding the science, engineering, and commercialization of biomass is presented. In Volume III the present status of gasification processes is described in detail, followed by chapters on economics, gas conditioning, fuel synthesis, the institutional role to be played by the federal government, and recommendations for future research and development.

  7. National Environmental Policy Act compliance guide. Volume II (reference book)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    This document (Volume II of the National Environmental Policy Act Compliance Guide) contains current copies of regulations and guidance from the Council on Environmental Quality, the Department of Energy, the Department of State, and the Environmental Protection Agency, related to compliance with the National Environmental Policy Act of 1969 (NEPA).

  8. Tokamak experimental power reactor conceptual design. Volume II

    International Nuclear Information System (INIS)

    1976-08-01

    Volume II contains the following appendices: (1) summary of EPR design parameters, (2) impurity control, (3) plasma computational models, (4) structural support system, (5) materials considerations for the primary energy conversion system, (6) magnetics, (7) neutronics penetration analysis, (8) first wall stress analysis, (9) enrichment of isotopes of hydrogen by cryogenic distillation, and (10) noncircular plasma considerations

  9. Nuclear reactor engineering: Reactor design basics. Fourth edition, Volume One

    International Nuclear Information System (INIS)

    Glasstone, S.; Sesonske, A.

    1994-01-01

    This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in design and operation of nuclear power plants. Extensively updated, the fourth edition includes new material on reactor safety and risk analysis, regulation, fuel management, waste management, and operational aspects of nuclear power. This volume contains the following: energy from nuclear fission; nuclear reactions and radiations; neutron transport; nuclear design basics; nuclear reactor kinetics and control; radiation protection and shielding; and reactor materials

  10. Mission Plan for the Civilian Radioactive Waste Management Program. Volume I. Part I. Overview and current program plans; Part II. Information required by the Nuclear Waste Policy Act of 1982

    International Nuclear Information System (INIS)

    1985-06-01

    The Misson Plan is divided into two parts. Part I describes the overall goals, objectives, and strategy for the disposal of spent nuclear fuel and high-level waste. It explains that, to meet the directives of the Nuclear Waste Policy Act, the DOE intends to site, design, construct, and start operating a mined geologic repository by January 31, 1998. The Act specifies that the costs of these activities will be borne by the owners and generators of the waste received at the repository. Part I further describes the other components of the waste-management program - monitored retrievable storage, Federal interim storage, and transportation - as well as systems integration activities. Also discussed are institutional plans and activities as well as the program-management system being implemented by the Office of Civilian Radioactive Waste Management. Part II of the Mission Plan presents the detailed information required by Section 301(a) of the Act - key issues and information needs; plans for obtaining the necessary information; potential financial, institutional, and legal issues; plans for the test and evaluation facility; the principal results obtained to date from site investigations; information on the site-characterization programs; information on the waste package; schedules; costs; and socioeconomic impacts. In accordance with Section 301(a) of the Act, Part II is concerned primarily with the repository program

  11. Experiments with radioactive nuclear beams II

    International Nuclear Information System (INIS)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A.; Lizcano C, D.; Garcia M, H.; Rosales M, P.

    2001-12-01

    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 12 C + 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)

  12. Nuclear Electronics II. Proceedings of the Conference on Nuclear Electronics. V. II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1962-04-15

    Nuclear instruments are used in almost every phase of atomic energy work, from assessing health hazards and prospecting for nuclear materials to plant control and nuclear physics experiments. The demands on nucleonic instrumentation are growing steadily. High-energy particle physics need such instruments for measuring extremely short times; in various research experiments most advanced electronic systems are required; and routine applications of radioisotopes call for more reliable instruments for automated counting facilities. In order to give designers and users of nuclear instrumentation an opportunity to discuss the research results and to exchange information on recent developments and new designs, the International Atomic Energy Agency, in co-operation with the Federal Nuclear Energy Commission of Yugoslavia, organized a Conference on Nuclear Electronics which was held in Belgrade from 15-20 May 1961. It was attended by more than 300 scientists from nearly 30 countries and five international organizations. Over 150 papers were read and discussed. As the field of nuclear electronics has expanded considerably, it was impossible to discuss all aspects of nuclear electronics in one series of meetings. Included in the main topics were radiation detectors, electronic circuitry in conventional and fast-pulse techniques and advanced electronic systems used in nuclear research. The Proceedings presented in these volumes contain the full records of the Conference, including discussions. The present state of technique, together with current trends and developments, are outlined. Of particular value should be the world-wide survey on progress recently made in such fields as those connected with semiconductor detectors, spark counters, luminescence chambers and fast electronic facilities for nuclear physics research. Together with the Proceedings of the Symposium on the same subject held in Paris and also published by the International Atomic Energy Agency, these volumes

  13. Proceedings of the second US Department of Energy environmental control symposium. Volume 2. Nuclear energy, conservation, and solar energy

    International Nuclear Information System (INIS)

    1980-06-01

    These proceedings document the presentations given at the Second Environmental Control Symposium. Symposium presentations highlighted environmental control activities which span the entire DOE. Volume II contains papers relating to: environmental control aspects of nuclear energy use and development; nuclear waste management; renewable energy sources; transportation and building conservation (fuel economy, gasohol, building standards, and industry); and geothermal energy, power transmission, and energy storage

  14. Proceedings of the second US Department of Energy environmental control symposium. Volume 2. Nuclear energy, conservation, and solar energy

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-06-01

    These proceedings document the presentations given at the Second Environmental Control Symposium. Symposium presentations highlighted environmental control activities which span the entire DOE. Volume II contains papers relating to: environmental control aspects of nuclear energy use and development; nuclear waste management; renewable energy sources; transportation and building conservation (fuel economy, gasohol, building standards, and industry); and geothermal energy, power transmission, and energy storage. (DMC)

  15. Activity report 1990-1992 and proceedings. Volume II

    International Nuclear Information System (INIS)

    Mayer-Rosa, D.; Waniek, L.; Suhadolc, P.

    1993-01-01

    A report of the European Seismological Commission (ESC) on 1990-1992 activities and Proceedings of the General Assembly of the ESC are presented in two volumes. Volume II covers the following topics: study of seismic sound, seismotectonic analysis, deep seismic sounding, the three-dimensional structure of the European lithosphere-asthenosphere system, complexity in earthquake occurrence, earthquake hazard, strong and weak earthquake ground motions, macroseismology, microzonation, and applications in earthquake engineering. One paper dealing with the connection between seismicity and the CO 2 - 222 Rn content in spring water has been inputted to INIS. (Z.S.)

  16. Manufacture of sockets of volume compensators in nuclear power plants

    International Nuclear Information System (INIS)

    Andreev, V.P.; Tshekotilo, L.V.; Shevtshenko, N.T.; Sevruk, A.N.; Wolacek, W.J.; Irsicek, L.; Vrbensky, J.

    1982-01-01

    Experience is reported with regard to electroslag casting of sockets of volume compensators or steam separators used in nuclear power plants. According to the method the raw pieces are casted directly at the surface of the enclosures

  17. Stereological estimation of nuclear volume in benign and atypical meningiomas

    DEFF Research Database (Denmark)

    Madsen, C; Schrøder, H D

    1993-01-01

    A stereological estimation of nuclear volume in benign and atypical meningiomas was made. The aim was to investigate whether this method could discriminate between these two meningeal neoplasms. The difference was significant and it was moreover seen that there was no overlap between the two groups....... The results demonstrate that atypical meningiomas can be distinguished from benign meningiomas by an objective stereological estimation of nuclear volume....

  18. S-1 project. Volume II. Hardware. 1979 annual report

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    This volume includes highlights of the design of the Mark IIA uniprocessor (SMI-2), and the SCALD II user's manual. SCALD (structured computer-aided logic design system) cuts the cost and time required to design logic by letting the logic designer express ideas as naturally as possible, and by eliminating as many errors as possible - through consistency checking, simulation, and timing verification - before the hardware is built. (GHT)

  19. Atucha II nuclear power plant digital simulation

    International Nuclear Information System (INIS)

    Santome, D.; Rovere, L.A.T.

    1987-01-01

    This paper describes the start-up of a digital simulation code apt to be performed in real time of Atucha II nuclear power plant, foreseeing its subsequent usage in a Basic Principles Simulator. Adaptability and modification of existing routines and development of modules in order to incorporate the necessary variables dynamics to couple the different modes, were the main tasks. The mathematical model used allows the representation of the following sub-systems: a) a reactor's core point model, which comprehends the neutronic kinetics, fission and decaying powers, thermal transfer and Xe-poisoning calculation; b) pressurizer, which considers two sub-systems that may or may not be in thermodynamic equilibrium, both in two phases; c) coolants and moderators bonds considering separate moderator loops with the aim of introducing asymmetric perturbations; d) secondary sub-subsystem, which includes the feed water loop, pumps, steam generators and control valves; e) steam generators; f) control and safety systems, including power control, steam generators levels, moderator's temperature primary loop system, limitations and protection. (Author)

  20. Mechanical Behaviour of Materials Volume II Fracture Mechanics and Damage

    CERN Document Server

    François, Dominique; Zaoui, André

    2013-01-01

    Designing new structural materials, extending lifetimes and guarding against fracture in service are among the preoccupations of engineers, and to deal with these they need to have command of the mechanics of material behaviour. This ought to reflect in the training of students. In this respect, the first volume of this work deals with elastic, elastoplastic, elastoviscoplastic and viscoelastic behaviours; this second volume continues with fracture mechanics and damage, and with contact mechanics, friction and wear. As in Volume I, the treatment links the active mechanisms on the microscopic scale and the laws of macroscopic behaviour. Chapter I is an introduction to the various damage phenomena. Chapter II gives the essential of fracture mechanics. Chapter III is devoted to brittle fracture, chapter IV to ductile fracture and chapter V to the brittle-ductile transition. Chapter VI is a survey of fatigue damage. Chapter VII is devoted to hydogen embrittlement and to environment assisted cracking, chapter VIII...

  1. ENC 94 International Nuclear Congress - Atoms for Energy. Transactions Vol.II: Poster Papers

    International Nuclear Information System (INIS)

    1995-01-01

    The transactions have been published in 2 volumes. Volume II contains the papers, which were orally presented in 4 sessions. In Session 1 'The need for nuclear energy in different parts of the world' was discussed in 17 contributions from the US, Korea, Turkey, Yugoslavia, Finland, the Netherlands, Poland, Russia, Croatia, Belgium and Germany. The other 3 sessions covered: Safety of operating nuclear plants (54 posters); Back-end of the fuel cycle (35 posters); Do we need new reactors to improve safety and economics ? (32 Posters)

  2. Nuclear reactor engineering: Reactor systems engineering. Fourth edition, Volume Two

    International Nuclear Information System (INIS)

    Glasstone, S.; Sesonske, A.

    1994-01-01

    This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in the design and operation of nuclear power plants. Extensively updated, the fourth edition includes new materials on reactor safety and risk analysis, regulation, fuel management, waste management and operational aspects of nuclear power. This volume contains the following: the systems concept, design decisions, and information tools; energy transport; reactor fuel management and energy cost considerations; environmental effects of nuclear power and waste management; nuclear reactor safety and regulation; power reactor systems; plant operations; and advanced plants and the future

  3. Atlas of total body radionuclide imaging. Volume I and II

    International Nuclear Information System (INIS)

    Fordham, E.W.; Ali, A.; Turner, D.A.; Charters, J.

    1982-01-01

    This two-volume work on total body imaging may well be regarded by future historians of nuclear medicine as representing the high points in the art of total body imaging in clinical nuclear medicine. With regard to information content and volume, it is the largest collection of well-interpreted, beautifully reproduced, total body images available to date. The primary goal of this atlas is to demonstrate patterns of abnormality in both typical and less typical variations. This goal is accomplished with many well-described examples of technical artifacts, of normal variants, of common and of rare diseases, and of pitfalls in interpretations. Volume I is entirely dedicated to skeletal imaging with Tc-99m labeled phosphates or phosphonates. The volume is divided into 22 chapters, which include chapters on methodology and instrumentation, chapters on the important bone diseases and other topics such as a treatise on false-negative and false-positive scans, and soft tissue and urinary tract abnormalities recognizable on bone scintigrams

  4. Bibliography on nuclear medicine. Volumes 28--30

    International Nuclear Information System (INIS)

    1975-07-01

    References to 3177 publications related to nuclear medicine announced in Nuclear Science Abstracts (NSA) volumes 28(July-Dec. 1973), 29(Jan-June 1974), and 30(July-Dec. 1974) are contained in this bibliography. Subject, report number, and personal author indexes are included. (U.S.)

  5. Nuclear regulatory legislation, 104th Congress, Volume 1, No. 4

    International Nuclear Information System (INIS)

    1997-12-01

    This document is the first of two volumes compiling statutes and material pertaining to nuclear regulatory legislation through the 104th Congress, 2nd Session. It is intended for use as a U.S. Nuclear Regulatory Commission (NRC) internal resource document. Legislative information reproduced in this document includes portions of the Atomic Energy Act, Energy Reorganization Act, Low-Level Radioactive Waste Policy Amendments Act, and Nuclear Waste Policy Act. Other information included in this volume pertains to NRC user fees, NRC authorizations, the Inspector General Act, and the Administrative Procedure Act

  6. Nuclear regulatory legislation, 104th Congress, Volume 1, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    This document is the first of two volumes compiling statutes and material pertaining to nuclear regulatory legislation through the 104th Congress, 2nd Session. It is intended for use as a U.S. Nuclear Regulatory Commission (NRC) internal resource document. Legislative information reproduced in this document includes portions of the Atomic Energy Act, Energy Reorganization Act, Low-Level Radioactive Waste Policy Amendments Act, and Nuclear Waste Policy Act. Other information included in this volume pertains to NRC user fees, NRC authorizations, the Inspector General Act, and the Administrative Procedure Act.

  7. Nuclear power. Volume 2: nuclear power project management

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The following topics are discussed: review of nuclear power plants; licensing procedures; safety analysis; project professional services; quality assurance and project organization; construction, scheduling and operation; construction, scheduling and operation; nuclear fuel handling and fuel management; and plant cost management. 116 references, 115 figures, 33 tables

  8. Nuclear Fuels & Materials Spotlight Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    I. J. van Rooyen,; T. M. Lillo; Y. Q. WU; P.A. Demkowicz; L. Scott; D.M. Scates; E. L. Reber; J. H. Jackson; J. A. Smith; D.L. Cottle; B.H. Rabin; M.R. Tonks; S.B. Biner; Y. Zhang; R.L. Williamson; S.R. Novascone; B.W. Spencer; J.D. Hales; D.R. Gaston; C.J. Permann; D. Anders; S.L. Hayes; P.C. Millett; D. Andersson; C. Stanek; R. Ali; S.L. Garrett; J.E. Daw; J.L. Rempe; J. Palmer; B. Tittmann; B. Reinhardt; G. Kohse; P. Ramuhali; H.T. Chien; T. Unruh; B.M. Chase; D.W. Nigg; G. Imel; J. T. Harris

    2014-04-01

    As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • The first identification of silver and palladium migrating through the SiC layer in TRISO fuel • A description of irradiation assisted stress corrosion testing capabilities that support commercial light water reactor life extension • Results of high-temperature safety testing on coated particle fuels irradiated in the ATR • New methods for testing the integrity of irradiated plate-type reactor fuel • Description of a 'Smart Fuel' concept that wirelessly provides real time information about changes in nuclear fuel properties and operating conditions • Development and testing of ultrasonic transducers and real-time flux sensors for use inside reactor cores, and • An example of a capsule irradiation test. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps to spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at INL, and hope that you find this issue informative.

  9. Nuclear proliferation. II. Monopoly or cartel

    International Nuclear Information System (INIS)

    Baker, S.J.

    1976-01-01

    Increasing competition between a growing number of nations exporting nuclear technology and recent exporting of full fuel-cycle facilities raise fears of nuclear proliferation and widespread nuclear weapons. As a result of the 1973 oil crisis, industrial nations seeking a share in the international nuclear market in order to protect their economic interests must also cooperate to protect these same interests from nuclear risks. Disagreement over the form of cooperation centers on the competing exporters' tactics of undercutting safeguards and political restrictions. Monopoly was never an option for even the United States. Government intervention in the international nuclear market in the form of subsidies and financial incentives is a more practical approach than a free market. A cartel arrangement is appropriate to nuclear energy in the sense of reducing economic uncertainties, but political objections would be strong and there would be some risk of independent nuclear development. As a strategy to forestall proliferation, however, the cartel can control exports of enrichment and reprocessing facilities and make it more expensive for nations to independently develop nuclear weapons. An enlargement of safeguards arrangements by nuclear suppliers will require nations to trade some of their economic interests in order to achieve international political objectives

  10. Tank waste source term inventory validation. Volume II. Letter report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This document comprises Volume II of the Letter Report entitled Tank Waste Source Term Inventory Validation. This volume contains Appendix C, Radionuclide Tables, and Appendix D, Chemical Analyte Tables. The sample data for selection of 11 radionuclides and 24 chemical analytes were extracted from six separate sample data sets, were arranged in a tabular format and were plotted on scatter plots for all of the 149 single-shell tanks, the 24 double-shell tanks and the four aging waste tanks. The solid and liquid sample data was placed in separate tables and plots. The sample data and plots were compiled from the following data sets: characterization raw sample data, recent core samples, D. Braun data base, Wastren (Van Vleet) data base, TRAC and HTCE inventories.

  11. Technology transfer package on seismic base isolation - Volume II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-14

    This Technology Transfer Package provides some detailed information for the U.S. Department of Energy (DOE) and its contractors about seismic base isolation. Intended users of this three-volume package are DOE Design and Safety Engineers as well as DOE Facility Managers who are responsible for reducing the effects of natural phenomena hazards (NPH), specifically earthquakes, on their facilities. The package was developed as part of DOE's efforts to study and implement techniques for protecting lives and property from the effects of natural phenomena and to support the International Decade for Natural Disaster Reduction. Volume II contains the proceedings for the Short Course on Seismic Base Isolation held in Berkeley, California, August 10-14, 1992.

  12. Tank waste source term inventory validation. Volume II. Letter report

    International Nuclear Information System (INIS)

    1995-04-01

    This document comprises Volume II of the Letter Report entitled Tank Waste Source Term Inventory Validation. This volume contains Appendix C, Radionuclide Tables, and Appendix D, Chemical Analyte Tables. The sample data for selection of 11 radionuclides and 24 chemical analytes were extracted from six separate sample data sets, were arranged in a tabular format and were plotted on scatter plots for all of the 149 single-shell tanks, the 24 double-shell tanks and the four aging waste tanks. The solid and liquid sample data was placed in separate tables and plots. The sample data and plots were compiled from the following data sets: characterization raw sample data, recent core samples, D. Braun data base, Wastren (Van Vleet) data base, TRAC and HTCE inventories

  13. Nuclear Fuels & Materials Spotlight Volume 5

    International Nuclear Information System (INIS)

    Petti, David Andrew

    2016-01-01

    As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • Evaluation and modeling of light water reactor accident tolerant fuel concepts • Status and results of recent TRISO-coated particle fuel irradiations, post-irradiation examinations, high-temperature safety testing to demonstrate the accident performance of this fuel system, and advanced microscopy to improve the understanding of fission product transport in this fuel system. • Improvements in and applications of meso and engineering scale modeling of light water reactor fuel behavior under a range of operating conditions and postulated accidents (e.g., power ramping, loss of coolant accident, and reactivity initiated accidents) using the MARMOT and BISON codes. • Novel measurements of the properties of nuclear (actinide) materials under extreme conditions, (e.g. high pressure, low/high temperatures, high magnetic field) to improve the scientific understanding of these materials. • Modeling reactor pressure vessel behavior using the GRIZZLY code. • New methods using sound to sense temperature inside a reactor core. • Improved experimental capabilities to study the response of fusion reactor materials to a tritium plasma. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at Idaho National Laboratory, and hope that you find this issue informative.

  14. Nuclear Fuels & Materials Spotlight Volume 5

    Energy Technology Data Exchange (ETDEWEB)

    Petti, David Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-10-01

    As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • Evaluation and modeling of light water reactor accident tolerant fuel concepts • Status and results of recent TRISO-coated particle fuel irradiations, post-irradiation examinations, high-temperature safety testing to demonstrate the accident performance of this fuel system, and advanced microscopy to improve the understanding of fission product transport in this fuel system. • Improvements in and applications of meso and engineering scale modeling of light water reactor fuel behavior under a range of operating conditions and postulated accidents (e.g., power ramping, loss of coolant accident, and reactivity initiated accidents) using the MARMOT and BISON codes. • Novel measurements of the properties of nuclear (actinide) materials under extreme conditions, (e.g. high pressure, low/high temperatures, high magnetic field) to improve the scientific understanding of these materials. • Modeling reactor pressure vessel behavior using the GRIZZLY code. • New methods using sound to sense temperature inside a reactor core. • Improved experimental capabilities to study the response of fusion reactor materials to a tritium plasma. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at Idaho National Laboratory, and hope that you find this issue informative.

  15. Three Mile Island: a report to the commissioners and to the public. Volume II, Part 1

    International Nuclear Information System (INIS)

    1979-01-01

    This is part one of three parts of the second volume of the Special Inquiry Group's report to the Nuclear Regulatory Commission on the accident at Three Mile Island. The first volume contained a narrative description of the accident and a discussion of the major conclusions and recommendations. This second volume is divided into three parts. Part 1 of Volume II focuses on the pre-accident licensing and regulatory background. This part includes an examination of the overall licensing and regulatory system for nuclear powerplants viewed from different perspectives: the system as it is set forth in statutes and regulations, as described in Congressional testimony, and an overview of the system as it really works. In addition, Part 1 includes the licensing, operating, and inspection history of Three Mile Island Unit 2, discussions of relevant regulatory matters, a discussion of specific precursor events related to the accident, a case study of the pressurizer design issue, and an analysis of incentives to declare commercial operation

  16. Nuclear Plant Analyzer: Installation manual. Volume 1

    International Nuclear Information System (INIS)

    Snider, D.M.; Wagner, K.L.; Grush, W.H.; Jones, K.R.

    1995-01-01

    This report contains the installation instructions for the Nuclear Plant Analyzer (NPA) System. The NPA System consists of the Computer Visual System (CVS) program, the NPA libraries, the associated utility programs. The NPA was developed at the Idaho National Engineering Laboratory under the sponsorship of the US Nuclear Regulatory Commission to provide a highly flexible graphical user interface for displaying the results of these analysis codes. The NPA also provides the user with a convenient means of interactively controlling the host program through user-defined pop-up menus. The NPA was designed to serve primarily as an analysis tool. After a brief introduction to the Computer Visual System and the NPA, an analyst can quickly create a simple picture or set of pictures to aide in the study of a particular phenomenon. These pictures can range from simple collections of square boxes and straight lines to complex representations of emergency response information displays

  17. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Volume 1, Summary description

    International Nuclear Information System (INIS)

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

    1988-02-01

    A data management system has been implemented which supports a variety of risk-related analyses and provides a repository of hardware component failure and human error probability data to the risk analyst. The Nuclear Computerized Library for Assessing Reactor Reliability, NUCLARR, is an interactive, graphically oriented system which resides on a personal computer (PC) or PC-compatible environment. An overview of the data management system, including a description of data collection, specification, data structure, and taxonomies, is presented in Volume I of this report. Programming activities, procedures for processing data, user's guide, and hard copy data manual are presented in Volumes II through V

  18. Minerals Yearbook, volume II, Area Reports—Domestic

    Science.gov (United States)

    ,

    2018-01-01

    The U.S. Geological Survey (USGS) Minerals Yearbook discusses the performance of the worldwide minerals and materials industries and provides background information to assist in interpreting that performance. Content of the individual Minerals Yearbook volumes follows:Volume I, Metals and Minerals, contains chapters about virtually all metallic and industrial mineral commodities important to the U.S. economy. Chapters on survey methods, summary statistics for domestic nonfuel minerals, and trends in mining and quarrying in the metals and industrial mineral industries in the United States are also included.Volume II, Area Reports: Domestic, contains a chapter on the mineral industry of each of the 50 States and Puerto Rico and the Administered Islands. This volume also has chapters on survey methods and summary statistics of domestic nonfuel minerals.Volume III, Area Reports: International, is published as four separate reports. These regional reports contain the latest available minerals data on more than 180 foreign countries and discuss the importance of minerals to the economies of these nations and the United States. Each report begins with an overview of the region’s mineral industries during the year. It continues with individual country chapters that examine the mining, refining, processing, and use of minerals in each country of the region and how each country’s mineral industry relates to U.S. industry. Most chapters include production tables and industry structure tables, information about Government policies and programs that affect the country’s mineral industry, and an outlook section.The USGS continually strives to improve the value of its publications to users. Constructive comments and suggestions by readers of the Minerals Yearbook are welcomed.

  19. Stereological estimation of the mean and variance of nuclear volume from vertical sections

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt

    1991-01-01

    The application of assumption-free, unbiased stereological techniques for estimation of the volume-weighted mean nuclear volume, nuclear vv, from vertical sections of benign and malignant nuclear aggregates in melanocytic skin tumours is described. Combining sampling of nuclei with uniform...... probability in a physical disector and Cavalieri's direct estimator of volume, the unbiased, number-weighted mean nuclear volume, nuclear vN, of the same benign and malignant nuclear populations is also estimated. Having obtained estimates of nuclear volume in both the volume- and number distribution...... to the larger malignant nuclei. Finally, the variance in the volume distribution of nuclear volume is estimated by shape-independent estimates of the volume-weighted second moment of the nuclear volume, vv2, using both a manual and a computer-assisted approach. The working procedure for the description of 3-D...

  20. 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)

  1. 9th Pacific Basin Nuclear Conference. Nuclear energy, science and technology - Pacific partnership. Proceedings Volume 2

    International Nuclear Information System (INIS)

    1994-04-01

    The theme of the 9th Pacific Basin Nuclear Conference held in Sydney from 1-6 May 1994, embraced the use of atom in energy production and in science and technology. The focus was on selected topics of current and on-going interest to countries around the Pacific Basin. The two-volume proceedings include both invited and contributed papers which have been indexed separately. This document, Volume 2 covers the following topics: education and training in Nuclear Science, public acceptance, nuclear safety and radiation protection, nuclear fuel resources and their utilisation, research reactors, cyclotrons and accelerators. refs., tabs., figs., ills

  2. 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)

  3. Energy paper II: Nuclear energy revival

    International Nuclear Information System (INIS)

    Anonymous

    2008-01-01

    ESI Energy paper is called 'Issue Paper' awarded by think-tank Energy Security Institute. The second issue focuses on the energy security of countries from the perspective of Renaissance of construction of nuclear power plants. Topicality is documented by fluctuations in fossil fuel prices on the world commodity markets and by extortionate potential, disposed by their main producers. The Slovak Republic is actively engaged into international dialogue on the need for the development of nuclear energy.

  4. Seismic coupling of nuclear explosions. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Larson, D B [ed.; Defense Advanced Research Projects Agency, Arlington, VA (United States)

    1989-12-31

    The new Giant Magnet Experimental Facility employing digital recording of explosion induced motion has been constructed and successfully tested. Particle velocity and piezoresistance gage responses can be measured simultaneously thus providing the capability for determining the multi-component stress-strain history in the test material. This capability provides the information necessary for validation of computer models used in simulation of nuclear underground testing, chemical explosion testing, dynamic structural response, earth penetration response, and etc. This report discusses fully coupled and cavity decoupled explosions of the same energy (0.622 kJ) were carried out as experiments to study wave propagation and attenuation in polymethylmethacrylate (PMMA). These experiments produced particle velocity time histories at strains from 2 {times} 10{sup {minus}3} to as low as 5.8 {times} 10{sup {minus}6}. Other experiments in PMMA, reported recently by Stout and Larson{sup 8} provide additional particle velocity data to strains of 10{sup {minus}1}.

  5. Stereological estimation of the mean and variance of nuclear volume from vertical sections

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt

    1991-01-01

    The application of assumption-free, unbiased stereological techniques for estimation of the volume-weighted mean nuclear volume, nuclear vv, from vertical sections of benign and malignant nuclear aggregates in melanocytic skin tumours is described. Combining sampling of nuclei with uniform...... probability in a physical disector and Cavalieri's direct estimator of volume, the unbiased, number-weighted mean nuclear volume, nuclear vN, of the same benign and malignant nuclear populations is also estimated. Having obtained estimates of nuclear volume in both the volume- and number distribution...... of volume, a detailed investigation of nuclear size variability is possible. Benign and malignant nuclear populations show approximately the same relative variability with regard to nuclear volume, and the presented data are compatible with a simple size transformation from the smaller benign nuclei...

  6. Stereological estimation of nuclear volume in benign and atypical meningiomas

    DEFF Research Database (Denmark)

    Madsen, C; Schrøder, H D

    1993-01-01

    A stereological estimation of nuclear volume in benign and atypical meningiomas was made. The aim was to investigate whether this method could discriminate between these two meningeal neoplasms. The difference was significant and it was moreover seen that there was no overlap between the two groups...

  7. Nuclear Fuel Cycle System Analysis (II)

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Won Il; Kwon, Eun Ha; Yoon, Ji Sup; Park, Seong Won

    2007-04-15

    As a nation develops strategies that provide nuclear energy while meeting its various objectives, it must begin with identification of a fuel cycle option that can be best suitable for the country. For such a purpose, this paper takes four different fuel cycle options that are likely adopted by the Korean government, considering the current status of nuclear power generation and the 2nd Comprehensive Nuclear Energy Promotion Plan (CNEPP) - Once-through Cycle, DUPIC Recycle, Thermal Reactor Recycle and GEN-IV Recycle. The paper then evaluates each option in terms of sustainability, environment-friendliness, proliferation-resistance, economics and technologies. Like all the policy decision, however, a nuclear fuel cycle option can not be superior in all aspects of sustainability, environment-friendliness, proliferation-resistance, economics, technologies and so on, which makes the comparison of the options extremely complicated. Taking this into consideration, the paper analyzes all the four fuel cycle options using the Multi-Attribute Utility Theory (MAUT) and the Analytic Hierarchy Process (AHP), methods of Multi-Attribute Decision Making (MADM), that support systematical evaluation of the cases with multi- goals or criteria and that such goals are incompatible with each other. The analysis shows that the GEN-IV Recycle appears to be most competitive.

  8. Sodium fast reactor safety and licensing research plan. Volume II.

    Energy Technology Data Exchange (ETDEWEB)

    Ludewig, H. (Brokhaven National Laboratory, Upton, NY); Powers, D. A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A. (Argonne National Laboratory, Argonne, IL); Phillips, J.; Zeyen, R. (Institute for Energy Petten, Saint-Paul-lez-Durance, France); Clement, B. (IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France); Garner, Frank (Radiation Effects Consulting, Richland, WA); Walters, Leon (Advanced Reactor Concepts, Los Alamos, NM); Wright, Steve; Ott, Larry J. (Oak Ridge National Laboratory, Oak Ridge, TN); Suo-Anttila, Ahti Jorma; Denning, Richard (Ohio State University, Columbus, OH); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki, Japan); Ohno, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Miyhara, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Yacout, Abdellatif (Argonne National Laboratory, Argonne, IL); Farmer, M. (Argonne National Laboratory, Argonne, IL); Wade, D. (Argonne National Laboratory, Argonne, IL); Grandy, C. (Argonne National Laboratory, Argonne, IL); Schmidt, R.; Cahalen, J. (Argonne National Laboratory, Argonne, IL); Olivier, Tara Jean; Budnitz, R. (Lawrence Berkeley National Laboratory, Berkeley, CA); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache, Cea, France); Natesan, Ken (Argonne National Laboratory, Argonne, IL); Carbajo, Juan J. (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin-Madison, Madison, WI); Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN); Bari, R. (Brokhaven National Laboratory, Upton, NY); Porter D. (Idaho National Laboratory, Idaho Falls, ID); Lambert, J. (Argonne National Laboratory, Argonne, IL); Hayes, S. (Idaho National Laboratory, Idaho Falls, ID); Sackett, J. (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.

    2012-05-01

    Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

  9. Sodium fast reactor safety and licensing research plan - Volume II

    International Nuclear Information System (INIS)

    Ludewig, H.; Powers, D.A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A.; Phillips, J.; Zeyen, R.; Clement, B.; Garner, Frank; Walters, Leon; Wright, Steve; Ott, Larry J.; Suo-Anttila, Ahti Jorma; Denning, Richard; Ohshima, Hiroyuki; Ohno, S.; Miyhara, S.; Yacout, Abdellatif; Farmer, M.; Wade, D.; Grandy, C.; Schmidt, R.; Cahalen, J.; Olivier, Tara Jean; Budnitz, R.; Tobita, Yoshiharu; Serre, Frederic; Natesan, Ken; Carbajo, Juan J.; Jeong, Hae-Yong; Wigeland, Roald; Corradini, Michael; Thomas, Justin; Wei, Tom; Sofu, Tanju; Flanagan, George F.; Bari, R.; Porter D.

    2012-01-01

    Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

  10. 9th Pacific Basin Nuclear Conference. Nuclear energy, science and technology - Pacific partnership. Proceedings Volume 1

    International Nuclear Information System (INIS)

    1994-04-01

    The theme of the 9th Pacific Basin Nuclear conference held in Sydney from 1-6 May 1994, embraced the use of the atom in energy production and in science and technology. The focus was on selected topics of current and ongoing interest to countries around the Pacific Basin. The two-volume proceedings include both invited and contributed papers. They have been indexed separately. This document, Volume 1 covers the following topics: Pacific partnership; perspectives on nuclear energy, science and technology in Pacific Basin countries; nuclear energy and sustainable development; economics of the power reactors; new power reactor projects; power reactor technology; advanced reactors; radioisotope and radiation technology; biomedical applications

  11. Savannah River Site Approved Site Treatment Plan, 2001 Annual Update (Volumes I and II)

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence, B.

    2001-04-30

    The Compliance Plan Volume (Volume I) identifies project activity scheduled milestones for achieving compliance with Land Disposal Restrictions. Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume II) and is provided for information.

  12. Reinforced soil structures. Volume II, Summary of research and systems information

    Science.gov (United States)

    1989-11-01

    Volume II was essentially prepared as an Appendix of supporting information for Volume I. This volume contains much of the supporting theory and a summary of the research used to verify the design approach contained in Volume I, as well as general in...

  13. Coastal effects of offshore energy systems. An assessment of oil and gas systems, deepwater ports, and nuclear power plants off the coast of New Jersey and Delaware. Volume II. Parts 1 and 2. Working papers 4 thru 10

    International Nuclear Information System (INIS)

    1976-11-01

    This report consists of ten working papers prepared as background material for the assessment of the effects of three proposed offshore energy systems on the coastal areas of New Jersey and Delaware. The three proposed offshore energy systems are: exploration for and development of offshore oil and gas, deepwater ports for supertankers, and floating nuclear powerplants. The 10 working papers cover: federal and state regulation of the three systems, the biological impacts, the risk of oil spills in developing oil and gas resources and operating deepwater ports, the air and water quality impacts, regional energy supply and demand considerations, the fiscal effects of developing the three systems, environmental studies, a safety analysis of floating nuclear powerplants, an analysis of fuel and waste handling of floating nuclear powerplants, and an analysis of the economic considerations of floating nuclear powerplants

  14. Technical summary of Groundwater Quality Protection Program at Savannah River Plant. Volume II. Radioactive waste

    International Nuclear Information System (INIS)

    Stone, J.A.; Christensen, E.J.

    1983-12-01

    This report (Volume II) presents representative monitoring data for radioactivity in groundwater at SRP. Four major groups of radioactive waste disposal sites and three minor sites are described. Much of the geohydrological and and other background information given in Volume I is applicable to these sites and is incorporated by reference. Several of the sites that contain mixed chemical and radioactive wastes are discussed in both Volumes I and II. Bulk unirradiated uranium is considered primarily a chemical waste which is addressed in Volume I, but generally not in Volume II

  15. Reproducibility of mean nuclear volume and correlation with mean nuclear area in breast cancer

    DEFF Research Database (Denmark)

    Baak, J P; Ladekarl, M; Sørensen, Flemming Brandt

    1994-01-01

    reproducible and strongly correlated with nuclear vv assessed in the TOTAL. In invasive breast cancer assessments in the whole tumor section can be used if delineation of the measurement area cannot be done easily. In small areas with a limited number of nuclei (eg, microinvasive parts) MNA can be easier......Previous studies have shown that quantitative, histopathologic features obtained from a carefully selected area in the tumor section ("selective" approach) have a strong prognostic value in breast cancer. On the other hand, it was found that mean nuclear volume estimation in the whole area...... as to their intraobserver and interobserver reproducibility in 22 invasive breast cancer cases. The mean nuclear volume (nuclear vv) was assessed both in the most atypical area (AREA) (selected on morphologic criteria) and in the whole tumor section (TOTAL). Furthermore, the correlation with mean nuclear (profile) area...

  16. Nuclear powerplant standardization: light water reactors. Volume 2. Appendixes

    International Nuclear Information System (INIS)

    1981-06-01

    This volume contains working papers written for OTA to assist in preparation of the report, NUCLEAR POWERPLANT STANDARDIZATION: LIGHT WATER REACTORS. Included in the appendixes are the following: the current state of standardization, an application of the principles of the Naval Reactors Program to commercial reactors; the NRC and standardization, impacts of nuclear powerplant standardization on public health and safety, descriptions of current control room designs and Duke Power's letter, Admiral Rickover's testimony, a history of standardization in the NRC, and details on the impact of standardization on public health and safety

  17. Barnwell Nuclear Fuels Plant applicability study. Volume III. Appendices

    International Nuclear Information System (INIS)

    1978-03-01

    Volume III suppliees supporting information to assist Congress in making a decision on the optimum utilization of the Barnwell Nuclear Fuels Plant. Included are applicable fuel cycle policies; properties of reference fuels; description and evaluation of alternative operational (flue cycle) modes; description and evaluation of safeguards systems and techniques; description and evaluation of spiking technology; waste and waste solidification evaluation; and Department of Energy programs relating to nonproliferation

  18. Intralesional and metastatic heterogeneity in malignant melanomas demonstrated by stereologic estimates of nuclear volume

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Erlandsen, M

    1990-01-01

    Regional variability of nuclear 3-dimensional size can be estimated objectively using point-sampled intercepts obtained from different, defined zones within individual neoplasms. In the present study, stereologic estimates of the volume-weighted mean nuclear volume, nuclear vv, within peripheral...... melanomas showed large interindividual variation. This finding emphasizes that unbiased estimates of nuclear vv are robust to regional heterogeneity of nuclear volume and thus suitable for purposes of objective, quantitative malignancy grading of melanomas....

  19. Nuclear instrumentation system operating experience and nuclear instrument testing in the EBR-II

    International Nuclear Information System (INIS)

    Yingling, G.E.; Curran, R.N.

    1980-01-01

    In March of 1972 three wide range nuclear channels were purchased from Gulf Atomics Corporation and installed in EBR-II as a test. The three channels were operated as a test until April 1975 when they became a permanent part of the reactor shutdown system. Also described are the activities involved in evaluating and qualifying neutron detectors for LMFBR applications. Included are descriptions of the ANL Components Technology Division Test Program and the EBR-II Nuclear Instrument Test Facilities (NITF) used for the in-reactor testing and a summary of program test results from EBR-II

  20. Models of cognitive behavior in nuclear power plant personnel. A feasibility study: main report. Volume 2

    International Nuclear Information System (INIS)

    Woods, D.D.; Roth, E.M.; Hanes, L.F.

    1986-07-01

    This report contains the results of a feasibility study to determine if the current state of models human cognitive activities can serve as the basis for improved techniques for predicting human error in nuclear power plants emergency operations. Based on the answer to this questions, two subsequent phases of research are planned. Phase II is to develop a model of cognitive activities, and Phase III is to test the model. The feasibility study included an analysis of the cognitive activities that occur in emergency operations and an assessment of the modeling concepts/tools available to capture these cognitive activities. The results indicated that a symbolic processing (or artificial intelligence) model of cognitive activities in nuclear power plants is both desirable and feasible. This cognitive model can be built upon the computational framework provided by an existing artificial intelligence system for medical problem solving called Caduceus. The resulting cognitive model will increase the capability to capture the human contribution to risk in probabilistic risk assessments studies. Volume I summarizes the major findings and conclusions of the study. Volume II provides a complete description of the methods and results, including a synthesis of the cognitive activities that occur during emergency operations, and a literature review on cognitive modeling relevant to nuclear power plants. 112 refs., 10 figs

  1. Nuclear regulatory legislation, 104th Congress. Volume 2, No. 4

    International Nuclear Information System (INIS)

    1997-12-01

    This document is the second of two volumes compiling statutes and material pertaining to nuclear regulatory legislation through the 104th Congress, 2nd Session. It is intended for use as a U.S. Nuclear Regulatory Commission (NRC) internal resource document. Legislative information reproduced in this document includes portions of the Paperwork Reduction Act, various acts pertaining to low-level radioactive waste, the Clean Air Act, the Federal Water Pollution Control Act, the National Environmental Policy Act, the Hazardous Materials Transportation Act, the West Valley Demonstration Project Act, Nuclear Non-Proliferation and Export Licensing Statutes, and selected treaties, agreements, and executive orders. Other information provided pertains to Commissioner tenure, NRC appropriations, the Chief Financial Officers Act, information technology management reform, and Federal civil penalties

  2. Nuclear regulatory legislation, 104th Congress. Volume 2, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    This document is the second of two volumes compiling statutes and material pertaining to nuclear regulatory legislation through the 104th Congress, 2nd Session. It is intended for use as a U.S. Nuclear Regulatory Commission (NRC) internal resource document. Legislative information reproduced in this document includes portions of the Paperwork Reduction Act, various acts pertaining to low-level radioactive waste, the Clean Air Act, the Federal Water Pollution Control Act, the National Environmental Policy Act, the Hazardous Materials Transportation Act, the West Valley Demonstration Project Act, Nuclear Non-Proliferation and Export Licensing Statutes, and selected treaties, agreements, and executive orders. Other information provided pertains to Commissioner tenure, NRC appropriations, the Chief Financial Officers Act, information technology management reform, and Federal civil penalties.

  3. Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 1: Procedural overview

    International Nuclear Information System (INIS)

    2007-01-01

    Accurate determinations of volume are a fundamental component of any measurement-based system of control and accountability in a facility that processes or stores nuclear materials in liquid form. Volume determinations are typically made with the aid of a calibration or volume measurement equation that relates the response of the tank's measurement system to some independent measure of tank volume. The ultimate purpose of the calibration exercise is to estimate the tank's volume measurement equation (the inverse of the calibration equation), which relates tank volume to measurement system response. The steps carried out to acquire data for estimating the tank's calibration or volume measurement equation are collectively described as the process of tank calibration. This part of ISO 18213 describes procedures for tank calibration and volume determination for nuclear process tanks equipped with pressure-measurement systems for determining liquid content. Specifically, overall guidance is provided for planning a calibration exercise undertaken to obtain the data required for the measurement equation to estimate a tank's volume. The key steps in the procedure are also presented for subsequently using the estimated volume-measurement equation to determine tank liquid volumes. The procedures presented apply specifically to tanks equipped with bubbler probe systems for measuring liquid content. Moreover, these procedures produce reliable results only for clear (i.e. without suspended solids), homogeneous liquids that are at both thermal and static equilibrium. The paper elaborates on scope, physical principles involved, the calibration model, equipment required, a typical tank calibration procedure, calibration planning and pre-calibration activities, and volume determination. A bibliography is provided

  4. Preliminary evaluation of alternative waste form solidification processes. Volume II. Evaluation of the processes

    International Nuclear Information System (INIS)

    1980-08-01

    This Volume II presents engineering feasibility evaluations of the eleven processes for solidification of nuclear high-level liquid wastes (HHLW) described in Volume I of this report. Each evaluation was based in a systematic assessment of the process in respect to six principal evaluation criteria: complexity of process; state of development; safety; process requirements; development work required; and facility requirements. The principal criteria were further subdivided into a total of 22 subcriteria, each of which was assigned a weight. Each process was then assigned a figure of merit, on a scale of 1 to 10, for each of the subcriteria. A total rating was obtained for each process by summing the products of the subcriteria ratings and the subcriteria weights. The evaluations were based on the process descriptions presented in Volume I of this report, supplemented by information obtained from the literature, including publications by the originators of the various processes. Waste form properties were, in general, not evaluated. This document describes the approach which was taken, the developent and application of the rating criteria and subcriteria, and the evaluation results. A series of appendices set forth summary descriptions of the processes and the ratings, together with the complete numerical ratings assigned; two appendices present further technical details on the rating process

  5. Nuclear carrier business volume projections, 1980-2000

    International Nuclear Information System (INIS)

    Lebo, R.G.; McKeown, M.S.; Rhyne, W.R.

    1980-05-01

    The expected number of shipments of commodities in the nuclear fuel cycle are projected for the years 1980 thru 2000. Projections are made for: yellowcake (U 3 O 8 ); natural, enriched and reprocessed uranium hexafluoride (UF 6 ); uranium dioxide powder (UO 2 ); plutonium dioxide powder (PuO 2 ); fresh UO 2 and mixed oxide (MOX) fuel; spent UO 2 fuel; low-level waste (LLW); transuranic (TRU) waste; high-activity TRU waste; high-level waste (HLW), and cladding hulls. Projections are also made for non-fuel cycle commodities such as defense TRU wastes and institutional wastes, since they also are shipped by the commercial transportation industry. Projections of waste shipments from LWRs are based on the continuation of current volume reduction and solidification techniques now used by the utility industry. Projections are also made based on a 5% per year reduction in LWR waste volume shipped which is assumed to occur as a result of increased implementation of currently available volume reduction systems. This assumption results in a net 64% decrease in the total waste shipped by the year 2000. LWR waste shipment projections, and essentially all other projections for fuel cycle commodities covered in this report, are normalized to BWR and PWR generating capacity projections set forth by the Department of Energy (DOE) in their low-growth projection of April, 1979. Therefore these commodity shipment projections may be altered to comply with future changes in generating capacity projections. Projected shipments of waste from the reprocessing of spent UO 2 fuel are based on waste generation rates proposed by Nuclear Fuels Services, Allied-General Nuclear Services, Exxon Nuclear, and the DOE. Reprocessing is assumed to begin again in 1990, with mixed oxide fresh fuel available for shipment by 1991

  6. Kilowatt isotope power system. Phase II plan. Volume I. Phase II program plan

    International Nuclear Information System (INIS)

    1978-01-01

    The development of a Kilowatt Isotope Power System (KIPS) was begun in 1975 for the purpose of satisfying the power requirements of satellites in the 1980's. The KIPS is a 238 PuO 2 -fueled organic Rankine cycle turbine power system to provide a design output of 500 to 2000 W. Phase II of the overall 3-phase KIPS program is described. This volume presents a program plan for qualifying the organic Rankine power system for flight test in 1982. The program plan calls for the design and fabrication of the proposed flight power system; conducting a development and a qualification program including both environmental and endurance testing, using an electrical and a radioisotope heat source; planning for flight test and spacecraft integration; and continuing ground demonstration system testing to act as a flight system breadboard and to accumulate life data

  7. Niels Bohr collected works, volume 9: Nuclear physics (1929-1952)

    International Nuclear Information System (INIS)

    Peierls, R.

    1985-01-01

    This volume deals with Bohr's work on nuclear physics which began in the pre-1932 days with his thinking deeply, but inconclusively about the seeming contradictions then presented by the evidence about the nucleus. In 1936 Bohr recognized and described the insights provided by neutron scattering experiments and the excitement of this new understanding and its extension and consolidation occupied much of the subsequent years. In 1939 he was again first in understanding the essential features of the newly discovered phenomenon of fission, applying successfully the point of view of nuclear reactions which he had developed over the past three years. Later, in 1949-50, he was impressed by the success of the nuclear shell model, which on the face of it seemed hard to reconcile with the picture of the closely interacting nucleons which he had pioneered in 1936 and he put much effort into clarifying this paradox. As in earlier volumes the published papers are supported by appropriate selections from unpublished notes and drafts, and by relevant correspondence. CONTENTS: Foreword. Part I: Papers and Manuscripts Related to Nuclear Physics. Part II: Selected Correspondence (1929-1949). Inventory of Relevant Manuscripts in the Niels Bohr Archive. Index

  8. Publications of Los Alamos Research, 1977-1981: formerly Publications of LASL Research. Volume II

    International Nuclear Information System (INIS)

    Sheridan, C.J.; Garcia, C.A.

    1983-03-01

    This volume is a bibliography of Los Alamos publications during the specified period in the following areas: general physics; nuclear physics; particles and fields; radioisotope and radiation applications; nuclear materials security safeguards; solar energy; theoretical plasma physics; and transportation of property and nuclear materials

  9. SAFEPAQ-II. User manual[Nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Forrest, R.A

    2001-03-01

    SAFEPAQ-II is the new software tool that has been developed to enable efficient production of the EAF nuclear data libraries that are required as input to the FISPACT activation code. It forms part of the European Activation System (EASY), and replaces SAFEPAQ and SYMPAL that were used previously. It enables all the nuclear data to be stored in relational databases (Access) and by using an interactive user interface allows the data to be viewed, modified, validated and then produced in the required EAF format as text files. It is written in Visual Basic and runs under the Windows NT4 and 98 operating systems. The Windows operating system has the great advantage of portability and SAFEPAQ-II has been successfully installed at two external sites for use by UKAEA's international collaborators. It has been used in the production of the EAF-2001 data libraries. (author)

  10. Principles of quantum computation and information volume II

    International Nuclear Information System (INIS)

    Kok, P

    2007-01-01

    Any new textbook in quantum information has some pretty strong competition to contend with. Not only is there the classic text by Nielsen and Chuang from 2000, but also John Preskill's lecture notes, available for free online. Nevertheless, a proper textbook seems more enduring than online notes, and the field has progressed considerably in the seven years since Nielsen and Chuang was published. A new textbook is a great opportunity to give a snapshot of our current state of knowledge in quantum information. Therein also lies a problem: The field has expanded so much that it is impossible to cover everything at the undergraduate level. Quantum information theory is relevant to an extremely large portion of physics, from solid state and condensed matter physics to particle physics. Every discipline that has some relation to quantum mechanics is affected by our understanding of quantum information theory. Those who wish to write a book on quantum information therefore have to make some profound choices: Do you keep the ultimate aim of a quantum computer in mind, or do you focus on quantum communication and precision measurements as well? Do you describe how to build a quantum computer with all possible physical systems or do you present only the underlying principles? Do you include only the tried and tested ideas, or will you also explore more speculative directions? You don't have to take a black-or-white stance on these questions, but how you approach them will profoundly determine the character of your book. The authors of 'Principles of Quantum Computation and Information (Volume II: Basic Tools and Special Topics)' have chosen to focus on the construction of quantum computers, but restrict themselves mainly to general techniques. Only in the last chapter do they explicitly address the issues that arise in the different implementations. The book is the second volume in a series, and consists of four chapters (labelled 5 to 8) called 'Quantum Information Theory

  11. Optimal design of condenser volume in nuclear power plant

    International Nuclear Information System (INIS)

    Zheng Jing; Yan Changqi; Wang Jianjun

    2011-01-01

    The condenser is an important component in the nuclear power plant,whose dimension will influence the economy and the arrangement of the nuclear power plant.In this paper, the calculation model was established according to the design experience. The corresponding codes were also developed. The sensitivity of design parameters which influence the condenser Janume was analyzed. The present optimal design of the condenser, aiming at the volume minimization, was carried out with the self-developed complex-genetic algorithm. The results show that the reference condenser design is far from the best scheme. In addition, the results also verify the feasibility of the complex-genetic algorithm. Furthermore, the results of this paper can provide reference for the design of the condenser. (authors)

  12. Nuclear materials 1993 annual report. Volume 8, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    This annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1993. The report is published in two parts. NUREG-1272, Vol. 8, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports, diagnostic evaluations, and reports to the NRC`s Operations Center. NUREG-1272, Vol. 8, No. 2, covers nuclear materials and presents a review of the events and concerns during 1993 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Note that the subtitle of No. 2 has been changed from ``Nonreactors`` to ``Nuclear Materials.`` Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from 1980 through 1993.

  13. Nuclear materials 1993 annual report. Volume 8, No. 2

    International Nuclear Information System (INIS)

    1995-05-01

    This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1993. The report is published in two parts. NUREG-1272, Vol. 8, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports, diagnostic evaluations, and reports to the NRC's Operations Center. NUREG-1272, Vol. 8, No. 2, covers nuclear materials and presents a review of the events and concerns during 1993 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Note that the subtitle of No. 2 has been changed from ''Nonreactors'' to ''Nuclear Materials.'' Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from 1980 through 1993

  14. Classification of tubulo-papillary renal cortical tumours using estimates of nuclear volume

    DEFF Research Database (Denmark)

    Brooks, B; Sørensen, Flemming Brandt; Olsen, S

    1993-01-01

    The classification of renal cortical tumours is problematic, with no clear division of benign from malignant tumours. Unbiased stereological estimates of volume-weighted nuclear volume (nuclear vv) were obtained by point sampling of nuclear intercepts in a retrospective study of 36 variably sized...

  15. Safety Specialist Manpower, Manpower Resources. Volumes II and III.

    Science.gov (United States)

    Booz Allen and Hamilton, Inc., Washington, DC.

    These second and third volumes of a four-volume study of manpower in state highway safety programs over the next decade estimate manpower resources by state and in national aggregate and describe present and planned training programs for safety specialists. For each educational level, both total manpower and manpower actually available for…

  16. An Independent Scientific Assessment of Well Stimulation in California Volume II

    Energy Technology Data Exchange (ETDEWEB)

    Long, Jane C.S. [California Council on Science and Technology, Sacramento, CA (United States); Feinstein, Laura C. [California Council on Science and Technology, Sacramento, CA (United States); Bachmann, Corinne E. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Birkholzer, Jens T. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Camarillo, Mary Kay [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Domen, Jeremy K. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Foxall, William [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Houseworth, James [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Jin, Ling [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Jordan, Preston D. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Maddalena, Randy L. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); McKone, Thomas E. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Millstein, Dev E. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Reagan, Matthew T. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Sandelin, Whitney L. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Stringfellow, William T. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Varadharajan, Charuleka [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Cooley, Heather [Pacific Inst., Oakland, CA (United States); Donnelly, Kristina [Pacific Inst., Oakland, CA (United States); Heberger, Matthew G. [Pacific Inst., Oakland, CA (United States); Hays, Jake [PSE Healthy Energy, Berkeley, CA (United States); Shonkoff, Seth B.C. [PSE Healthy Energy, Berkeley, CA (United States); Brandt, Adam [Stanford Univ., CA (United States); Englander, Jacob G. [Stanford Univ., CA (United States); Hamdoun, Amro [Univ. of California of San Diego, La Jolla, CA (United States); Nicklisch, Sascha C.T. [Univ. of California of San Diego, La Jolla, CA (United States); Harrison, Robert J. [Univ. of California, San Francisco, CA (United States); Wettstein, Zachary S. [Univ. of California, San Francisco, CA (United States); Banbury, Jenner [California State Univ. Stanislaus, Turlock, CA (United States); Cypher, Brian L. [California State Univ. Stanislaus, Turlock, CA (United States); Phillips, Scott E. [California State Univ. Stanislaus, Turlock, CA (United States)

    2015-07-01

    This study is issued in three volumes. Volume I, issued in January 2015, describes how well stimulation technologies work, how and where operators deploy these technologies for oil and gas production in California, and where they might enable production in the future. Volume II, the present volume, discusses how well stimulation could affect water, atmosphere, seismic activity, wildlife and vegetation, and human health. Volume II reviews available data, and identifies knowledge gaps and alternative practices that could avoid or mitigate these possible impacts. Volume III, also issued in July 2015, presents case studies that assess environmental issues and qualitative risks for specific geographic regions. A final Summary Report summarizes key findings, conclusions and recommendations of all three volumes.

  17. Preliminary feasibility study on storage of radioactive wastes in Columbia River basalts. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    ,

    1976-11-01

    Volume II comprises four appendices: analytical data and sample locations for basalt flow type localities; Analytical data and sample locations for measured field sections in Yakima basalts; core hole lithology and analytical data; and geophysical logs. (LK)

  18. POWER-GEN '90 conference papers: Volume 7 (Fossil plant performance availability and improvement) and Volume 8 (Nuclear power issues)

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    This is book 4 of papers presented at the Third International Exhibition and Conference for the Power Generation Industries, December 4-6, 1990. This book contains Volume 7, Fossil Plant Performance Availability and Improvement, and Volume 8, Nuclear Power Issues. The topics of the papers include computer applications in plant operations and maintenance, managing aging plants, plant improvements, plant operations and maintenance, the future of nuclear power, achieving cost effective plant operation, managing nuclear plant aging and license renewal, and the factors affecting a decision to build a new nuclear plant

  19. Atlas of Ohio Aquatic Insects: Volume II, Plecoptera.

    Science.gov (United States)

    DeWalt, R Edward; Grubbs, Scott A; Armitage, Brian J; Baumann, Richard W; Clark, Shawn M; Bolton, Michael J

    2016-01-01

    We provide volume II of a distributional atlas of aquatic insects for the eastern USA state of Ohio. This treatment of stoneflies (Plecoptera) is companion to Armitage et al. (2011) on caddisflies (Trichoptera). We build on a recent analysis of Ohio stonefly diversity patterns based on large drainages (DeWalt et al. 2012), but add 3717 new records to the data set. We base most analyses on the United States Geological Survey Hierarchical Unit Code eight (HUC8) drainage scale. In addition to distributional maps for each species, we provide analyses of species richness versus HUC8 drainage area and the number of unique locations in a HUC8 drainage, species richness versus Ohio counties, analyze adult presence phenology throughout the year, and demonstrate stream size range affiliation for each species. This work is based on a total of 7797 specimen records gathered from 21 regional museums, agency data, personal collections, and from the literature Table 1. To our knowledge this is the largest stonefly data set available for a similarly sized geopolitical area anywhere in the world. These data are made available as a Darwin Core Archive supported by the Pensoft Integrated Publishing Toolkit (DeWalt et al. 2016b). All known published papers reporting stoneflies from Ohio are detailed in Suppl. material 1. We recovered 102 species from Ohio, including all nine Nearctic families Table 2​. Two species were removed from the DeWalt et al. (2012) list and two new state records added. Perlidae (32 spp.) was most speciose, compared to the low diversity Pteronarcyidae (2 spp.) and Peltoperlidae (1 sp.). The richest HUC8 drainages occurred in northeastern, south-central, and southern regions of the state where drainages were heavily forested, had the highest slopes, and were contained within or adjacent to the unglaciated Allegheny and Appalachian Plateaus. Species poor drainages occurred mainly in the northwestern region where Wisconsinan aged lake plains climaxed to an

  20. A Curriculum Activities Guide to Water Pollution and Environmental Studies, Volume II - Appendices.

    Science.gov (United States)

    Hershey, John T., Ed.; And Others

    This publication, Volume II of a two volume set of water pollution studies, contains seven appendices which support the studies. Appendix 1, Water Quality Parameters, consolidates the technical aspects of water quality including chemical, biological, computer program, and equipment information. Appendix 2, Implementation, outlines techniques…

  1. Three Mile Island: a report to the commissioners and to the public. Volume II, Part 3

    International Nuclear Information System (INIS)

    1979-01-01

    This is the third and final part of the second volume of a study of the Three Mile Island accident. Part 3 of Volume II contains descriptions and assessments of responses to the accident by the utility and by the NRC and other government agencies

  2. Measurement of volumic activities of radon in air in houses and in working rooms with solid state nuclear track detectors

    International Nuclear Information System (INIS)

    Hakam, O.K.

    1993-01-01

    In this work, a new method of measuring volumic activity of radon has been developed. This method is based on using solid state nuclear track detectors LR-115 type II. It has been applied to measurement of volumic activities of radon in air in houses and in working rooms in different regions of Morocco. These measurements, carried out for the first time in the country, allowed to estimate the dose equivalents of radon received by the population of the studied regions. 59 refs., 38 figs., 38 tabs. (F.M.)

  3. TIBER II/ETR: Nuclear Performance Analysis Group Report

    International Nuclear Information System (INIS)

    1987-09-01

    A Nuclear Performance Analysis Group was formed to develop the nuclear technology mission of TIBER-II under the leadership of Argonne National Laboratory reporting to LLNL with major participation by the University of California - Los Angeles (test requirements, R and D needs, water-cooled test modules, neutronic tests). Additional key support was provided by GA Technologies (helium-cooled test modules), Hanford Engineering Development Laboratory (material-irradiation tests), Sandia National Laboratory - Albuquerque (high-heat-flux component tests), and the Idaho National Engineering Laboratory (safety tests). Support also was provided by Rennselaer Polytechnic Institute, Grumman Aerospace Corporation, and the Canadian Fusion Fuels Technology Program. This report discusses these areas and provides a schedule for their completion

  4. Improved nuclear gage development - phase i and ii. Interim report

    International Nuclear Information System (INIS)

    Chan, E.L.; Champion, F.C.; Castanon, D.R.; Chang, J.C.; Hannon, J.B.

    1976-09-01

    This report contains Phase I and II of an investigation covering the design and construction of a prototype nuclear-moisture-density backscatter gage. Gage development was based upon the analysis of several factors which affect gage performance. This research indicated that the prototype gage measurements are approximately equivalent to measurements obtained by a commercial transmission gage. The implication of this research finding concerns the qualification of the backscatter test method as a valid, reliable, and expedient procedure for determining in-situ soil conditions

  5. EMPIRE-II statistical model code for nuclear reaction calculations

    Energy Technology Data Exchange (ETDEWEB)

    Herman, M [International Atomic Energy Agency, Vienna (Austria)

    2001-12-15

    EMPIRE II is a nuclear reaction code, comprising various nuclear models, and designed for calculations in the broad range of energies and incident particles. A projectile can be any nucleon or Heavy Ion. The energy range starts just above the resonance region, in the case of neutron projectile, and extends up to few hundreds of MeV for Heavy Ion induced reactions. The code accounts for the major nuclear reaction mechanisms, such as optical model (SCATB), Multistep Direct (ORION + TRISTAN), NVWY Multistep Compound, and the full featured Hauser-Feshbach model. Heavy Ion fusion cross section can be calculated within the simplified coupled channels approach (CCFUS). A comprehensive library of input parameters covers nuclear masses, optical model parameters, ground state deformations, discrete levels and decay schemes, level densities, fission barriers (BARFIT), moments of inertia (MOMFIT), and {gamma}-ray strength functions. Effects of the dynamic deformation of a fast rotating nucleus can be taken into account in the calculations. The results can be converted into the ENDF-VI format using the accompanying code EMPEND. The package contains the full EXFOR library of experimental data. Relevant EXFOR entries are automatically retrieved during the calculations. Plots comparing experimental results with the calculated ones can be produced using X4TOC4 and PLOTC4 codes linked to the rest of the system through bash-shell (UNIX) scripts. The graphic user interface written in Tcl/Tk is provided. (author)

  6. Draft Site Treatment Plan (DSTP), Volumes I and II

    International Nuclear Information System (INIS)

    D'Amelio, J.

    1994-01-01

    Site Treatment Plans (STP) are required for facilities at which the DOE generates or stores mixed waste. This Draft Site Treatment Plan (DSTP) the second step in a three-phase process, identifies the currently preferred options for treating mixed waste at the Savannah River Site (SRS) or for developing treatment technologies where technologies do not exist or need modification. The DSTP reflects site-specific preferred options, developed with the state's input and based on existing available information. To the extent possible, the DSTP identifies specific treatment facilities for treating the mixed waste and proposes schedules. Where the selection of specific treatment facilities is not possible, schedules for alternative activities such as waste characterization and technology assessment are provided. All schedule and cost information presented is preliminary and is subject to change. The DSTP is comprised of two volumes: this Compliance Plan Volume and the Background Volume. This Compliance Plan Volume proposes overall schedules with target dates for achieving compliance with the land disposal restrictions (LDR) of RCRA and procedures for converting the target dates into milestones to be enforced under the Order. The more detailed discussion of the options contained in the Background Volume is provided for informational purposes only

  7. Environmental law and climate change : Volumes I & II

    NARCIS (Netherlands)

    Verschuuren, Jonathan

    Two volume set that brings together 54 of the most influential and important scientific journal articles in the field of climate law, thematically grouped together as follows: introducing climate law, theories and approaches, climate change mitigation, climate change adaptation, climate justice,

  8. Role of nuclear hexokinase II in DNA repair

    International Nuclear Information System (INIS)

    Khanna, S.; Bhatt, A.N.; Dwarakanath, B.S.; Kalaiarasan, P.; Brahmachari, V.

    2012-01-01

    A common signature of many cancer cells is a high glucose catabolic rate primarily due to the over expression of Type II hexokinase (HKII; responsible for the phosphorylation of glucose), generally known as cytosolic and mitochondrial bound enzyme that also suppresses cell death. Although, nuclear localization and transcriptional regulation of HKII has been reported in yeast; we and few others have recently demonstrated its nuclear localization in malignant cell lines. Interestingly, modification of a human glioma cell line (BMG-1) for enhancing glycolysis through mitochondrial respiration (OPMBMG cells) resulted in a higher nuclear localization of HKII as compared to the parental cells with concomitant increase in DNA repair and radio-resistance. Further, the glucose phosphorylation activity of the nuclear HKII was nearly 2 folds higher in the relatively more radioresistant HeLa cells (human cervical cancer cell line) as compared to MRC-5 cells (human normal lung fibroblast cell line). Therefore, we hypothesize that nuclear HKII facilitates DNA repair, in a hither to unknown mechanism, that may partly contribute to the enhanced resistance of highly glycolytic cells to radiation. Sequence alignment studies suggest that the isoenzymes, HKI and HKII share strong homology in the kinase active site, which is also found in few protein kinases. Interestingly HKI has been shown to phosphorylate H2A in-vitro. Further, in-silico protein-protein interaction data suggest that HKII can interact with several DNA repair proteins including ATM. Taken together; available experimental evidences as well as in-silico predictions strongly suggest that HKII may play a role in DNA repair by phosphorylation of certain DNA repair proteins. (author)

  9. INEL environmental characterization report. Volume II. Appendices A-D

    International Nuclear Information System (INIS)

    1984-09-01

    This volume contains appendices: (1) a socioeconomic data base for southeastern Idaho; (2) an ecological characterization of the INEL; (3) site-specific climatology summary, NPR primary and alternate sites; (4) NPR site borehole completion; (5) an investigation of the principal lineament at the INEL; (6) an investigation of Clay Butte, Idaho; (7) Arco and Howe fault study; (8) seismology of the INEL; (9) geologic map of the INEL; and (1) geologic ages of the INEL

  10. Basic Quechua. Volume I: Quechua Reader. Volume II: Quechua Grammar and Dictionary.

    Science.gov (United States)

    Aitken-Soux, Percy G.; Crapo, Richley H.

    Volume I, the reader, has 86 lessons consisting of short passages and vocabulary lists. The language and the stories presented were learned and collected at the Indian community and Hacienda of Cayara near Potosi, Bolivia. Translations of the passages are provided in a separate section. The second volume presents the grammar and phonology of the…

  11. Fukushima Daiichi Unit 1 Uncertainty Analysis-Exploration of Core Melt Progression Uncertain Parameters-Volume II.

    Energy Technology Data Exchange (ETDEWEB)

    Denman, Matthew R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brooks, Dusty Marie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-08-01

    Sandia National Laboratories (SNL) has conducted an uncertainty analysi s (UA) on the Fukushima Daiichi unit (1F1) accident progression wit h the MELCOR code. Volume I of the 1F1 UA discusses the physical modeling details and time history results of the UA. Volume II of the 1F1 UA discusses the statistical viewpoint. The model used was developed for a previous accident reconstruction investigation jointly sponsored by the US Department of Energy (DOE) and Nuclear Regulatory Commission (NRC). The goal of this work was to perform a focused evaluation of uncertainty in core damage progression behavior and its effect on key figures - of - merit (e.g., hydrogen production, fraction of intact fuel, vessel lower head failure) and in doing so assess the applicability of traditional sensitivity analysis techniques .

  12. DNA-index and stereological estimation of nuclear volume in primary and metastatic malignant melanomas

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Kristensen, I B; Grymer, F

    1990-01-01

    The aim of this study was to investigate the relationship between physical nuclear volume and ploidy level in malignant melanomas, and to analyse the heterogeneity of these two parameters among primary and corresponding secondary tumours. Unbiased stereological estimates of nuclear volume can...

  13. Safety analysis report for the TRUPACT-II shipping package (condensed version). Volume 1, Rev. 14

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-10-01

    The condensed version of the TRUPACT-II Contact Handled Transuranic Waste Safety Analysis Report for Packaging (SARP) contains essential material required by TRUPACT-II users, plus additional contents (payload) information previously submitted to the U.S. Nuclear Regulatory Commission. All or part of the following sections, which are not required by users of the TRUPACT-II, are deleted from the condensed version: (i) structural analysis, (ii) thermal analysis, (iii) containment analysis, (iv) criticality analysis, (v) shielding analysis, and (vi) hypothetical accident test results.

  14. Safety analysis report for the TRUPACT-II shipping package (condensed version). Volume 1, Rev. 14

    International Nuclear Information System (INIS)

    1994-10-01

    The condensed version of the TRUPACT-II Contact Handled Transuranic Waste Safety Analysis Report for Packaging (SARP) contains essential material required by TRUPACT-II users, plus additional contents (payload) information previously submitted to the U.S. Nuclear Regulatory Commission. All or part of the following sections, which are not required by users of the TRUPACT-II, are deleted from the condensed version: (i) structural analysis, (ii) thermal analysis, (iii) containment analysis, (iv) criticality analysis, (v) shielding analysis, and (vi) hypothetical accident test results

  15. Lanchester-Type Models of Warfare. Volume II

    Science.gov (United States)

    1980-10-01

    ii7 L HOWES and THRALL (1972) ,HT n HTY HT m HTX jini ijl HOLTER (1973) and ANDERSON (1979) CHA HAx Y tAs in the preceding table, SPUDICH (1968) - the...detail can one afford? A recent U. S. General Accounting Office ( GAO ) report [150, pp. 28-29] points out that there is a strong inconsistency between...further details). 65. A recent U. S. Getueral Accounting Office ( GAO ) [1501 study has emphasized that empirical study is necessary to strengthen the

  16. USAF Summer Faculty Research Program. 1981 Research Reports. Volume II.

    Science.gov (United States)

    1981-10-01

    Spec ialty : IIS F ,re ign Policy ; American Indiana State University Nat ioinal Security Policy Dept. of Political Science A. si ,niled: A! Terre Haute...0 C-4 44 C E) I IC C z)~ w z . 0 cnCd d CCC C’) 0-4-9- ..- E-4 (-4 7-A.A).)).) (QUADI) was constructed in the same manner as for the plate bending...IV modifications in accordance with current policy . They are to expedite safety modifications that could ground airborne systems or inactivate ground

  17. HIBAL Program. Preliminary Warhead-Design. Volume II. Appendices.

    Science.gov (United States)

    1980-09-15

    Mild Steel (iAi i018). ............. 11-2 B. SAE 4130 .. .. .. .... ...... ....... 11-3 C. SAE 4140 ......... .... .... ......... 11-3 D, SAE 4340...11-7 - Test Data for SAE 4140 Steel Frag- ments ...... ................ 11-14 Figure II-7A - 4142 ... .............. 11-15 Figure 11-8 - Test Data...included the following types of steel: SAE 1018, 4130, 4140 and 4340; 5-317 and 5-876 Carpenter tool steel; Anico HY-80 and SSS-100 steel; AISI-S7

  18. The world made by Noble prize : chemistry volume II

    International Nuclear Information System (INIS)

    2007-06-01

    This book has two parts of items related chemistry. The contents of the first part are Preface, Alfred Bemhard Nobel, Pioneers without Nobel Prize, Garbage Bag, Non-sticky Frying Pan, Nylon Stockings, Plastic Electricity, Synthetic Dyestuff, Gin and Tonic, Soccer Ball, Fertilizer, DDT, Dentifrice, Kimchi, Makgeolli, Ice cream, Anodyne, and firefly. The contents of the second part are PET-MRI, Color photo, Holography, Art diamond, an incandescent lamp and Neon Sign, Imitation works, Alchemy, Nuclear Power plant, Synthetic Oil and Sugar, Propane gas, Water Car, Estate agency Mars, and reference.

  19. The world made by Noble prize : chemistry volume II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-06-15

    This book has two parts of items related chemistry. The contents of the first part are Preface, Alfred Bemhard Nobel, Pioneers without Nobel Prize, Garbage Bag, Non-sticky Frying Pan, Nylon Stockings, Plastic Electricity, Synthetic Dyestuff, Gin and Tonic, Soccer Ball, Fertilizer, DDT, Dentifrice, Kimchi, Makgeolli, Ice cream, Anodyne, and firefly. The contents of the second part are PET-MRI, Color photo, Holography, Art diamond, an incandescent lamp and Neon Sign, Imitation works, Alchemy, Nuclear Power plant, Synthetic Oil and Sugar, Propane gas, Water Car, Estate agency Mars, and reference.

  20. Proceedings of the American Power Conference. Volume 58-II

    International Nuclear Information System (INIS)

    McBride, A.E.

    1996-01-01

    This book is part 2 of the proceedings of the American Power Conference, Technology for Competition and Globalization, 1996. The topics of the papers include structural plant design; challenges of the global marketplace; thermal hydraulic methods for nuclear power plant safety and operation; decontamination and decommissioning; competitive operations and maintenance; fuel opportunities; cooling; competitive power pricing; operations; transformers; relays; plant controls; training to meet the competitive future; burning technologies; ash and byproducts utilization; advanced systems; computer tools for plant design; globalization of power; power system protection and power quality; life extension; grounding; and transmission line equipment

  1. Time series analysis of nuclear instrumentation in EBR-II

    International Nuclear Information System (INIS)

    Imel, G.R.

    1996-01-01

    Results of a time series analysis of the scaler count data from the 3 wide range nuclear detectors in the Experimental Breeder Reactor-II are presented. One of the channels was replaced, and it was desired to determine if there was any statistically significant change (ie, improvement) in the channel's response after the replacement. Data were collected from all 3 channels for 16-day periods before and after detector replacement. Time series analysis and statistical tests showed that there was no significant change after the detector replacement. Also, there were no statistically significant differences among the 3 channels, either before or after the replacement. Finally, it was determined that errors in the reactivity change inferred from subcritical count monitoring during fuel handling would be on the other of 20-30 cents for single count intervals

  2. Nuclear Regulatory Commission issuances. Volume 17, No. 3

    International Nuclear Information System (INIS)

    1983-03-01

    This report contains the Issuances received during March 1983 from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors Decisions (DD), and the Denials of Petition for Rulemaking (DPRM). The Issuances concerned the following facilities: Three Mile Island Nuclear Station, Unit No. 1; Comanche Peak Steam Electric Station, Units 1 and 2; Vallecitos Nuclear Center; Floating Nuclear Power Plants; San Onofre Nuclear Generating Station, Units 2 and 3; Point Beach Nuclear Plant, Unit 1; Perry Nuclear Power Plant, Units 1 and 2; Shoreham Nuclear Power Station, Unit 1; Western New York Nuclear Service Center; Limerick Generating Station, Units 1 and 2; Seabrook Station, Units 1 and 2; Black Fox Station, Units 1 and 2; WmH Zimmer Nuclear Power Station, Unit 1; WPPSS Nuclear Project No. 1; Zion Nuclear Plant, Units 1 and 2; and South Texas Project, Units 1 and 2

  3. Commingled uranium-tailings study. Volume II. Technical report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-06-30

    Public Law 96-540, Section 213, directs the Secretary of Energy to develop a plan for a cooperative program to provide assistance in the stabilization and management of defense-related uranium mill tailings commingled with other tailings. In developing the plan, the Secretary is further directed to: (1) establish the amount and condition of tailings generated under federal contracts; (2) examine appropriate methodologies for establishing the extent of federal assistance; and (3) consult with the owners and operators of each site. This technical report summarizes US Department of Energy (DOE) and contractor activities in pursuit of items (1), (2), and (3) above. Recommendations regarding policy and a cooperative plan for federal assistance are under separate cover as Volume I.

  4. Nuclear material inventory estimation in solvent extraction contractors II

    International Nuclear Information System (INIS)

    Beyerlein, A.

    1987-11-01

    The effectiveness of near-real-time nuclear materials accounting in reprocessing facilities can be limited by inventory variations in the separations contactors. Investigations are described in three areas: (i) Improvements in the model that the authors have described previously for the steady state inventory estimation in mixer-settler contactors, (ii) extension for the model for steady state inventory estimation to transient inventory estimation for non-steady state conditions, and (iii) the development of a computer model CUSEP (Clemson University Solvent Extraction Program) for simulating the concentration profiles and nuclear material inventories in pulsed column contactors. Improvements in the steady state model that are described in this report are the simplification of the methods for evaluating model parameters and development of methods for reducing the equation which estimates the total inventory of the set of contactors directly. The pulsed column computer model CUSEP (Clemson University Solvent Extraction Program) was developed. Concentration profiles and inventories calculated from CUSEP are compared with measured data from pilot scale contactors containing uranium. Excellent agreement between measured and simulated data for both the concentration profile and inventories is obtained, demonstrating that the program correctly predicts the concentration dispersion caused by pulsing and the dispersed phase holdup within the contactor. Further research to investigate (i) correction of the MUF (Material Unaccounted For) and CUMUF (Cumulative Material Unaccounted For) tests for mixer-settler contactor inventory using the simplified model developed in this work, (ii) development of a simple inventory estimation model for pulsed column contactors similar to that developed for mixer-settler contactors using CUSEP to provide necessary database, and (iii) sources of bias appearing in the MUF and CUMUF tests using computer simulation techniques are planned. Refs

  5. Nuclear legislation. Analytical study. Regulatory and Institutional framework for nuclear activities in OECD Member countries. Volume I

    International Nuclear Information System (INIS)

    1983-01-01

    This study is part of a series of analytical studies of the major aspects of nuclear legislation in OECD Member countries and is published in two volumes. This Volume I of the study is a revision and an expansion of a 1969 study concerning the organisation and general regime governing nuclear activities. The national studies were prepared, to the extent possible, following a standard plan for all countries to facilitate information retrieval and comparison. (NEA) [fr

  6. Paul Scherrer Institute Scientific Report 1998. Volume II: Life Sciences

    Energy Technology Data Exchange (ETDEWEB)

    Gschwend, Beatrice; Jaussi, Rolf [eds.

    1999-09-01

    The Department of Life Sciences, is aiming to perform high quality research in biosciences focused primarily on oncology and in close interaction with the technical facilities at PSI e.g. proton therapy, SINQ, SLS, and the national and international bioscience community. Within this department, the Division of Radiation Protection and Radioactive Waste Treatment is responsible for the radiological safety of the personnel, the installations and the environment at PSI, and it is charged with dismantling obsolete nuclear installations at PSI. The principal research and development activities of this division concern novel methods for neutron dosimetry, and the study of presence and pathways of natural and man made radioactivity in humans and in the environment. (author) figs., tabs., refs.

  7. Paul Scherrer Institute Scientific Report 1998. Volume II: Life Sciences

    International Nuclear Information System (INIS)

    Gschwend, Beatrice; Jaussi, Rolf

    1999-01-01

    The Department of Life Sciences, is aiming to perform high quality research in biosciences focused primarily on oncology and in close interaction with the technical facilities at PSI e.g. proton therapy, SINQ, SLS, and the national and international bioscience community. Within this department, the Division of Radiation Protection and Radioactive Waste Treatment is responsible for the radiological safety of the personnel, the installations and the environment at PSI, and it is charged with dismantling obsolete nuclear installations at PSI. The principal research and development activities of this division concern novel methods for neutron dosimetry, and the study of presence and pathways of natural and man made radioactivity in humans and in the environment. (author)

  8. NJOY nuclear data processing system. Volume IV. The ERRORR and COVR modules

    International Nuclear Information System (INIS)

    Muir, D.W.; MacFarlane, R.E.

    1985-12-01

    The NJOY nuclear data processing system is a comprehensive computer code package for producing cross sections and related nuclear parameters from ENDF/B evaluated nuclear data. This volume provides detailed descriptions of the NJOY modules ERRORR and COVR, which are concerned with the covariances (uncertainties and correlations) of multigroup cross sections and fission neutron yield (anti nu) values. 17 refs

  9. 10. National Nuclear Science and Technology Congress Proceedings Book, Volume 2

    International Nuclear Information System (INIS)

    2009-01-01

    X. National Nuclear Science and Technologies Congress was held on 6-9 October 2009 in Mugla, Turkey in the course of collaborative organization undertaken by Turkish Atomic Energy Authority, Mugla University and Sitki Kocman Foundation. This second volume of Proceedings Book contains 91 submitted presentations and 51 of them are full texts on applications of basic nuclear sciences, nuclear energy and safety.

  10. Subseabed disposal program annual report, January-December 1979. Volume II. Appendices (principal investigator progress reports). Part 2 of 2

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1981-04-01

    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 II, 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-O; Part 2 contains Appendices P-FF. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base

  11. Nuclear Regulatory Commission issuances, January 1997. Volume 45, Number 1

    International Nuclear Information System (INIS)

    1997-01-01

    This book contains issuances of the Atomic Safety and Licensing Board, Nuclear Regulatory Commission and Director's Decision for January 1997. The issuances concern Sequoyah Fuels Corporation and General Atomics Gore, Oklahoma Site decontamination and decommissioning funding; Louisiana Energy Services, Claiborne Enrichment Center denies appeal to review emergency planning; General Public Utilities Nuclear Corporation, Oyster Creek Nuclear Generating station, challenges to technical specifications concerning spent fuel pool; and Consumers Power Company, Palisades Nuclear Plant dry cask storage of spent nuclear fuel

  12. An excursion through elementary mathematics, volume ii euclidean geometry

    CERN Document Server

    Caminha Muniz Neto, Antonio

    2018-01-01

    This book provides a comprehensive, in-depth overview of elementary mathematics as explored in Mathematical Olympiads around the world. It expands on topics usually encountered in high school and could even be used as preparation for a first-semester undergraduate course. This second volume covers Plane Geometry, Trigonometry, Space Geometry, Vectors in the Plane, Solids and much more. As part of a collection, the book differs from other publications in this field by not being a mere selection of questions or a set of tips and tricks that applies to specific problems. It starts from the most basic theoretical principles, without being either too general or too axiomatic. Examples and problems are discussed only if they are helpful as applications of the theory. Propositions are proved in detail and subsequently applied to Olympic problems or to other problems at the Olympic level. The book also explores some of the hardest problems presented at National and International Mathematics Olympiads, as well as many...

  13. Characterization of large volume HPGe detectors. Part II: Experimental results

    International Nuclear Information System (INIS)

    Bruyneel, Bart; Reiter, Peter; Pascovici, Gheorghe

    2006-01-01

    Measurements on a 12-fold segmented, n-type, large volume, irregular shaped HPGe detector were performed in order to determine the parameters of anisotropic mobility for electrons and holes as charge carriers created by γ-ray interactions. To characterize the electron mobility the complete outer detector surface was scanned in small steps employing photopeak interactions at 60keV. A precise measurement of the hole drift anisotropy was performed with 356keV γ-rays. The drift velocity anisotropy and crystal geometry cause considerable rise time differences in pulse shapes depending on the position of the spatial charge carrier creation. Pulse shapes of direct and transient signals are reproduced by weighting potential calculations with high precision. The measured angular dependence of rise times is caused by the anisotropic mobility, crystal geometry, changing field strength and space charge effects. Preamplified signals were processed employing digital spectroscopy electronics. Response functions, crosstalk contributions and averaging procedures were taken into account implying novel methods due to the segmentation of the Ge-crystal and digital signal processing electronics

  14. Soil microbiology in land reclamation volume II - mycorrhizae

    Energy Technology Data Exchange (ETDEWEB)

    Graves, D.H. (ed.)

    1984-01-01

    This volume contains three separate reports: RRTAC 84-4 (Greenhouse pot studies dealing with amendment of oil sand tailings: effects of peat, sewage sludge and fertilizer on plant growth, mycorrhizae and microbial activity); RRTAC 84-8 (Vesicular-arbuscular mycorrhizal (VAM) development of slender wheatgrass on amended oil sand tailings and subalpine coal mines spoil); RRTAC 84-7 (Ectomycorrhizae in amended oil sand tailings and subalpine coal mine spoil and in undisturbed Jack pine and spruce stands). In the first report mixtures of two peats were used to amend oil sand tailings and either mineral fertilizers or sewage sludge were added at different rates. The growth of slender wheat grass and jack pine grown in the greenhouse in these media were monitored. In the second report the VAM development of slender wheatgrass was monitored over a 4 year period; in the third the mycorrhizal status of jack pine and bear berry grown in oil sand tailings treated with various amendments and of white spruce and willow grown in subalpine coal mine spoil were monitored over the same period.

  15. NWTS waste package program plan. Volume II. Program logic networks

    International Nuclear Information System (INIS)

    1981-10-01

    This document describes the work planned for developing the technology to design, test and produce packages used for the long-term isolation of nuclear waste in deep geologic repositories. Waste forms considered include spent fuel and high-level waste. The testing and selection effort for barrier materials for radionuclide containment is described. The NWTS waste package program is a design-driven effort; waste package conceptual designs are used as input for preliminary designs, which are upgraded to a final design as materials and testing data become available. Performance assessment models are developed and validated. Milestones and a detailed schedule are given for the waste package development effort. Program logic networks defining work flow, interfaces among the NWTS Projects, and interrelationships of specific activities are presented. Detailed work elements are provided for the Waste Package Program Plan subtasks - design and development, waste form, barrier materials, and performance evaluation - for salt and basalt, host rocks for which the state of waste package knowledge and the corresponding data base are advanced

  16. Boiling water reactor turbine trip (TT) benchmark. Volume II: Summary Results of Exercise 1

    International Nuclear Information System (INIS)

    Akdeniz, Bedirhan; Ivanov, Kostadin N.; Olson, Andy M.

    2005-06-01

    The OECD Nuclear Energy Agency (NEA) completed under US Nuclear Regulatory Commission (NRC) sponsorship a PWR main steam line break (MSLB) benchmark against coupled system three-dimensional (3-D) neutron kinetics and thermal-hydraulic codes. Another OECD/NRC coupled-code benchmark was recently completed for a BWR turbine trip (TT) transient and is the object of the present report. Turbine trip transients in a BWR are pressurisation events in which the coupling between core space-dependent neutronic phenomena and system dynamics plays an important role. The data made available from actual experiments carried out at the Peach Bottom 2 plant make the present benchmark particularly valuable. While defining and coordinating the BWR TT benchmark, a systematic approach and level methodology not only allowed for a consistent and comprehensive validation process, but also contributed to the study of key parameters of pressurisation transients. The benchmark consists of three separate exercises, two initial states and five transient scenarios. The BWR TT Benchmark will be published in four volumes as NEA reports. CD-ROMs will also be prepared and will include the four reports and the transient boundary conditions, decay heat values as a function of time, cross-section libraries and supplementary tables and graphs not published in the paper version. BWR TT Benchmark - Volume I: Final Specifications was issued in 2001 [NEA/NSC/DOC(2001)]. The benchmark team [Pennsylvania State University (PSU) in co-operation with Exelon Nuclear and the NEA] has been responsible for coordinating benchmark activities, answering participant questions and assisting them in developing their models, as well as analysing submitted solutions and providing reports summarising the results for each phase. The benchmark team has also been involved in the technical aspects of the benchmark, including sensitivity studies for the different exercises. Volume II summarises the results for Exercise 1 of the

  17. Nuclear criticality safety experiments, calculations, and analyses: 1958 to 1982. Volume 1. Lookup tables

    International Nuclear Information System (INIS)

    Koponen, B.L.; Hampel, V.E.

    1982-01-01

    This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains - in chronological order - the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41

  18. Controlled air incinerator for radioactive waste. Volume II. Engineering design references manual

    International Nuclear Information System (INIS)

    Koenig, R.A.; Draper, W.E.; Newmyer, J.M.; Warner, C.L.

    1982-11-01

    This two-volume report is a detailed design and operating documentation of the Los Alamos National Laboratory Controlled Air Incinerator (CAI) and is an aid to technology transfer to other Department of Energy contractor sites and the commercial sector. Volume I describes the CAI process, equipment, and performance, and it recommends modifications based on Los Alamos experience. It provides the necessary information for conceptual design and feasibility studies. Volume II provides descriptive engineering information such as drawings, specifications, calculations, and costs. It aids duplication of the process at other facilities

  19. Los Alamos Controlled Air Incinerator for radioactive waste. Volume II. Engineering design reference manual

    Energy Technology Data Exchange (ETDEWEB)

    Koenig, R.A.; Draper, W.E.; Newmyer, J.M.; Warner, C.L.

    1982-10-01

    This two-volume report is a detailed design and operating documentation of the Los Alamos National Laboratory Controlled Air Incinerator (CAI) and is an aid to technology transfer to other Department of Energy contractor sites and the commercial sector. Volume I describes the CAI process, equipment, and performance, and it recommends modifications based on Los Alamos experience. It provides the necessary information for conceptual design and feasibility studies. Volume II provides descriptive engineering information such as drawings, specifications, calculations, and costs. It aids duplication of the process at other facilities.

  20. Los Alamos Controlled Air Incinerator for radioactive waste. Volume II. Engineering design reference manual

    International Nuclear Information System (INIS)

    Koenig, R.A.; Draper, W.E.; Newmyer, J.M.; Warner, C.L.

    1982-10-01

    This two-volume report is a detailed design and operating documentation of the Los Alamos National Laboratory Controlled Air Incinerator (CAI) and is an aid to technology transfer to other Department of Energy contractor sites and the commercial sector. Volume I describes the CAI process, equipment, and performance, and it recommends modifications based on Los Alamos experience. It provides the necessary information for conceptual design and feasibility studies. Volume II provides descriptive engineering information such as drawings, specifications, calculations, and costs. It aids duplication of the process at other facilities

  1. Energy policy study. Volume 10. Nuclear power regulation

    International Nuclear Information System (INIS)

    Nikodem, Z.D.; Reynolds, A.W.; Clark, R.G.

    1980-05-01

    This report examines the programs for regulating the safety, design, and operation of domestic nuclear power plants. The first part of the study describes the Federal and State regulatory procedures. It describes the legal foundations for the Federal licensing process and the associated State regulatory activities. It then analyzes the aspects of these procedures that affect the cost and supply of nuclear-generated electricity. The second part of this study examines the effects of nuclear safety regulations on the planning and construction lead time for nuclear power stations, the cost of nuclear power, and, ultimately, the decision to invest in nuclear power

  2. Intralesional and metastatic heterogeneity in malignant melanomas demonstrated by stereologic estimates of nuclear volume

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Erlandsen, M

    1990-01-01

    Regional variability of nuclear 3-dimensional size can be estimated objectively using point-sampled intercepts obtained from different, defined zones within individual neoplasms. In the present study, stereologic estimates of the volume-weighted mean nuclear volume, nuclear vv, within peripheral...... on average larger in the peripheral zones of primary melanomas, than nuclear vv in central zones (2p = 6.7 x 10(-4), whereas no zonal differences were demonstrated in metastatic lesions (2p = 0.21). A marked intraindividual variation was demonstrated between primary and corresponding secondary melanomas (2p...... melanomas showed large interindividual variation. This finding emphasizes that unbiased estimates of nuclear vv are robust to regional heterogeneity of nuclear volume and thus suitable for purposes of objective, quantitative malignancy grading of melanomas....

  3. Nuclear Law Bulletin No. 92 - Volume 2013/2

    International Nuclear Information System (INIS)

    Chennoufi, F.; Pelzer, N.; Martirosyan, A.; Cook, H.; Fischer, D.; Clark, S.; Rothschild, T.; Touitou-Durand, F.; Guezou, O.; Manson, S.; Tafili, V.; Bolger, I.; Majerus, P.; Sieczak, K.; Sousa-Ferro, M.; Pospisil, M.; Skraban, A.; Portmann-Bochsler, F.; Shvytai, V.; Puig, D.; Durand, A.; Rivera, S.; Reyners, P.; Ryan-Taix, V.

    2013-01-01

    The Nuclear Law Bulletin is a unique international publication for both professionals and academics in the field of nuclear law. It provides authoritative and comprehensive information on nuclear law developments. Published twice a year in both English and French, it features topical articles written by renowned legal experts, covers nuclear legislative developments worldwide and reports on relevant case law, bilateral and international agreements and regulatory activities of international organisations. The topical articles of this issue deal with: - Uranium mining and production: A legal perspective on regulating an important resource by Lisa Thiele; - Turkish nuclear legislation: Developments for a nuclear newcomer by Erinc Ercan and Horst Schneider; - Nuclear law and environmental law in the licensing of nuclear installations by Christian Raetzke

  4. Proceedings of the advanced coal-fired power systems `95 review meeting, Volume II

    Energy Technology Data Exchange (ETDEWEB)

    McDaniel, H.M.; Mollot, D.J.; Venkataraman, V.K.

    1995-06-01

    This report contains papers which were presented at the advanced coal-fired power sytems review meeting. This is volume II. Topics include: hot gas filter issues, hazardous air pollutants, sorbent development, and separation technologies. Individual papers were processed separately for the United States Department of Energy databases.

  5. Kilowatt isotope power system, Phase II Plan. Volume IV. Teledyne FSCD vs GDS

    Energy Technology Data Exchange (ETDEWEB)

    1978-03-15

    This Volume contains Teledyne's input to the Kilowatt Isotope Power System Phase II Plan. Included is a description of the Flight System Heat Generation System, Flight System Radiator, Thermal Insulation Stability, GDS Heat Generation System and GDS Radiator.

  6. Discourse, Paragraph, and Sentence Structure in Selected Philippine Languages. Final Report. Volume II, Sentence Structure.

    Science.gov (United States)

    Longacre, Robert E.

    Volume II of "Discourse, Paragraph, and Sentence Structure in Selected Philippine Languages" begins with an explanation of certain assumptions and postulates regarding sentence structure. A detailed treatment of systems of sentence structure and the parameters of such systems follows. Data in the various indigenous languages are…

  7. Biennial Survey of Education, 1916-18. Volume II. Bulletin, 1919, No. 89

    Science.gov (United States)

    Bureau of Education, Department of the Interior, 1921

    1921-01-01

    Volume II of the Biennial Survey of Education, 1916-1918 includes the following chapters: (1) Education in Great Britain and Ireland (I. L. Kandel); (2) Education in parts of the British Empire: Educational Developments in the Dominion of Canada (Walter A. Montgomery), Public School System of Jamaica (Charles A. Asbury), Recent Progress of…

  8. 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.

  9. Proceedings of the natural gas RD&D contractors review meeting, Volume II

    Energy Technology Data Exchange (ETDEWEB)

    Malone, R.D. [ed.

    1995-04-01

    This is volume II of papers which were presented at the natural gas RD&D contractors review meeting. Topics include: natural gas upgrading, storage, well drilling, completion, and stimulation. Individual papers were processed separately for the United States Department of Energy databases.

  10. Calibration of a solid state nuclear track detector for the measurements of volumic activity of Radon

    International Nuclear Information System (INIS)

    HAKAM, O.K.; LFERDE, M.; BERRADA, M.

    1994-01-01

    Time - integrated measurements of environmental radiation activity are commonly carried out using solid state nuclear track detectors ( SSNTD ). These detectors should be calibrated of volumic activity of radon. This paper reports the results of experiments conducted to calibrate cellulose nitrate films LR - 115 type II used for measurements of volumic activity of radon in indoor air in dwellings and enclosed work areas in Morocco. Calibration measurements were made in laboratory using a calibration chamber and a radon source. The calibration chamber is a cylindric box ( 2613,6 cm sup 3)which we have manufactured of aluminium. The radon source is a natural sample rich of aluminium (17,29 + 0 ,12) Bq/g. The films are placed in detector holder with membrane and exposed inside the calibration chamber to varying concentrations of radon. Following the exposure, the films were chemically etched in sodium hydroxide (2,5 N) at 60 C for 120 minutes. The number of registered alpha particle tracks were counted with an optical microscope. In the used etching conditions, the removed mean thickness is in the order of 6 micro m. Therefore, we have normalized the track density to this value . We obtained a calibration factor of 0, 58 tracks . cm sup -2/ K Bq . h . m sup -3 . 1 tab.; 1 fig.; 2 refs. (author)

  11. US Nuclear Regulatory Commission annual report, 1985. Volume 2

    International Nuclear Information System (INIS)

    1986-01-01

    The decisions and actions of the Nuclear Regulatory Commission (NRC) during fiscal year 1985 are reported. Areas covered include reactor regulation, cleanup at Three Mile Island, analysis and evaluation of operational experience, nuclear materials, waste management, safeguards, inspection, enforcement, quality assurance, emergency preparedness, and nuclear regulatory research. Also, cooperation with the states, international programs, proceedings and litigation, and management are discussed

  12. Stereological estimates of nuclear volume in squamous cell carcinoma of the uterine cervix and its precursors

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Bichel, P; Jakobsen, A

    1991-01-01

    Using modern stereology, this study was carried out to obtain base-line data concerning three-dimensional, mean nuclear size in precancerous and invasive lesions of the uterine cervix. Unbiased estimates of the volume-weighted mean nuclear volume (nuclear vv) were obtained by point-sampling of nu......Using modern stereology, this study was carried out to obtain base-line data concerning three-dimensional, mean nuclear size in precancerous and invasive lesions of the uterine cervix. Unbiased estimates of the volume-weighted mean nuclear volume (nuclear vv) were obtained by point......-sampling of nuclear intercepts in 51 pre-treatment biopsies from patients with invasive squamous cell carcinomas (SCC). Vertical sections from 27 specimens with cervical intraepithelial neoplasia (CIN) grades I through III were also investigated, along with 10 CIN III associated with microinvasion (CIN III + M......). On average, nuclear vv was larger in SCC than in CIN III and CIN III + M together (2 P = 8.9 . 10(-5). A conspicuous overlap of nuclear vv existed between all investigated lesional groups. The reproducibility of estimates of nuclear vv in biopsies with SCC was acceptable (r = 0.85 and r = 0.84 in intra...

  13. International and Domestic Market Opportunities for Biomass Power: Volumes I and II

    Energy Technology Data Exchange (ETDEWEB)

    1998-09-01

    This report examines the domestic and international markets for biopower. Domestic and foreign markets present fundamentally different challenges to private power developers. Volume I focuses on the domestic market for biopower. The domestic challenge lies in finding economically viable opportunities for biopower. Vol. I outlines the current state of the U.S. biomass industry, discusses policies affecting biomass development, describes some demonstration projects currently underway, and discusses the future direction of the industry. Volume II focuses on the international market for biopower. Recent literature states that the electricity investment and policy climate in foreign markets are the key elements in successful private project development. Vol. II discusses the financing issues, policy climate, and business incentives and barriers to biopower development. As India and China are the largest future markets for biopower, they are the focus of this volume. Three other top markets- -Brazil, Indonesia, and the Philippines--are also discussed. Potential financial resources wrap up the discussion.

  14. Nuclear Safety: Volume 29, No. 3: Technical progress review

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1988-07-01

    Nuclear Safety is a review journal that covers significant development in the field of nuclear safety. Its scope included the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated. Individual papers have been cataloged separately.

  15. Nuclear Law Bulletin No. 96. Volume 2015/2

    International Nuclear Information System (INIS)

    Reynolds, M.; Thiele, L.; Touitou-Durand, F.; Pelzer, N.; Tafili, V.; Manually, Y.; Adomaityte, U.; Adamczyk, K.; Nowacki, T.; Chiripus, V.; Pistekova, Z.; Skraban, A.; Knopp Pisi, S.; Hoang, V.; Rothschild, T.; Durand, A.; Rivera, S.R.; Salter, I.

    2015-01-01

    The Nuclear Law Bulletin is a unique international publication for both professionals and academics in the field of nuclear law. It provides readers with authoritative and comprehensive information on nuclear law developments. Published free online twice a year in both English and French, it features topical articles written by renowned legal experts, covers legislative developments worldwide and reports on relevant case law, bilateral and international agreements as well as regulatory activities of international organisations. Feature articles in this issue include 'Treaty implementation applied to conventions on nuclear safety' and 'Crisis, criticism, change: Regulatory reform in the wake of nuclear accidents'. (authors)

  16. Nuclear Law Bulletin No. 93, Volume 2014/1

    International Nuclear Information System (INIS)

    2014-01-01

    The Nuclear Law Bulletin is a unique international publication for both professionals and academics in the field of nuclear law. It provides authoritative and comprehensive information on nuclear law developments. Published free online twice a year in both English and French, it features topical articles written by renowned legal experts, covers legislative developments worldwide and reports on relevant case law, bilateral and international agreements as well as regulatory activities of international organisations. Feature articles in this issue include: 'Progress towards a global nuclear liability regime'; 'The Convention on Supplementary Compensation for Nuclear Damage and participation by developing countries: A South African perspective'; 'Fusion energy and nuclear liability considerations'; and 'Nuclear energy and Indian society: Public engagement, risk assessment and legal frameworks'

  17. Nuclear Law Bulletin No. 94, Volume 2014/2

    International Nuclear Information System (INIS)

    2014-01-01

    The Nuclear Law Bulletin is a unique international publication for both professionals and academics in the field of nuclear law. It provides subscribers with authoritative and comprehensive information on nuclear law developments. Published free online twice a year in both English and French, it features topical articles written by renowned legal experts, covers legislative developments worldwide and reports on relevant case law, bilateral and international agreements as well as regulatory activities of international organisations. Feature articles in this issue include 'Facilitating the entry into force and implementation of the Amendment to the Convention on the Physical Protection of Nuclear Material: Observations, challenges and benefits'; 'The legal status of nuclear power in Germany'; 'Challenges facing the insurance industry since the modernisation of the international nuclear third party liability regime'; 'Draft Federal Act of the Russian Federation, 'The Civil Liability for Nuclear Damage and its Financial Security''. (authors)

  18. HYDRA-II: A hydrothermal analysis computer code: Volume 1, Equations and numerics

    International Nuclear Information System (INIS)

    McCann, R.A.

    1987-04-01

    HYDRA-II is a hydrothermal computer code capable of three-dimensional analysis of coupled conduction, convection, and thermal radiation problems. This code is especially appropriate for simulating the steady-state performance of spent fuel storage systems. The code has been evaluated for this application for the US Department of Energy's Commercial Spent Fuel Management Program. HYDRA-II provides a finite difference solution in Cartesian coordinates to the equations governing the conservation of mass, momentum, and energy. A cylindrical coordinate system may also be used to enclose the Cartesian coordinate system. This exterior coordinate system is useful for modeling cylindrical cask bodies. The difference equations for conservation of momentum are enhanced by the incorporation of directional porosities and permeabilities that aid in modeling solid structures whose dimensions may be smaller than the computational mesh. The equation for conservation of energy permits of modeling of orthotropic physical properties and film resistances. Several automated procedures are available to model radiation transfer within enclosures and from fuel rod to fuel rod. The documentation of HYDRA-II is presented in three separate volumes. This volume, Volume I - Equations and Numerics, describes the basic differential equations, illustrates how the difference equations are formulated, and gives the solution procedures employed. Volume II - User's Manual contains code flow charts, discusses the code structure, provides detailed instructions for preparing an input file, and illustrates the operation of the code by means of a model problem. The final volume, Volume III - Verification/Validation Assessments, presents results of numerical simulations of single- and multiassembly storage systems and comparisons with experimental data. 4 refs

  19. Security programs for Category I or II nuclear material or certain nuclear facilities. Regulatory guide G-274

    International Nuclear Information System (INIS)

    2003-03-01

    The purpose of this regulatory guide is to help applicants for a Canadian Nuclear Safety Commission (CNSC) licence in respect of Category I or II nuclear material - other than a licence to transport - , or a nuclear facility consisting of a nuclear reactor that may exceed 10 MW thermal power during normal operation, prepare and submit the security information to be included with the application, pursuant to the Nuclear Safety and Control Act (NSCA). Category I and II nuclear material are defined in Appendix B to this guide. This guide describes: the security information that should typically be included with the application for any licence referred to above; how the security information may be organized and presented in a separate document (hereinafter 'the security program description'), in order to assist CNSC review and processing of the application; and, the administrative procedures to be followed when preparing, submitting or revising the security program description. (author)

  20. Nuclear Law Bulletin No. 95. Volume 2015/1

    International Nuclear Information System (INIS)

    2015-01-01

    The Nuclear Law Bulletin is a unique international publication for both professionals and academics in the field of nuclear law. It provides readers with authoritative and comprehensive information on nuclear law developments. Published free online twice a year in both English and French, it features topical articles written by renowned legal experts, covers legislative developments worldwide and reports on relevant case law, bilateral and international agreements as well as regulatory activities of international organisations. Feature articles in this issue include 'Entry into force of the Convention on Supplementary Compensation for Nuclear Damage: Opening the umbrella'; 'Towards a new international framework for nuclear safety: Developments from Fukushima to Vienna'; 'Nuclear arbitration: Interpreting non-proliferation agreements'. Other chapters deal with case laws, legislative and regulatory activities, intergovernmental organisation activities, and documents and legal texts

  1. Nuclear Regulatory Commission issuances. Volume 40, Number 5

    International Nuclear Information System (INIS)

    1994-11-01

    This book contains issuances of the Atomic Safety and Licensing Boards for November 1994. The issuances include Cameo Diagnostic Centre, Inc. byproduct material license; Georgia Power Company license amendment, transfer to Southern Nuclear for Vogtle Electric Generating Plant, units 1 and 2; Indiana Regional Cancer Center, order modifying and suspending byproduct material license; Louisiana Energy Services, special nuclear material license; Pacific Gas and Electric Company, construction period recovery, facility operating license, Diablo Canyon Nuclear Power plant; and Sequoyah Fuels Corporation, source materials license

  2. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposl of radioactive and hazardous waste. Volume II

    International Nuclear Information System (INIS)

    1997-01-01

    The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type.Volume II is an integral part of the Office of Environmental Management''s (EM''s) Waste Management Programmatic Environmental Impact Statement (WM PEIS), which portrays the impacts of EM''s waste management activities at each of the 17 major DOE sites evaluated in the WM PEIS

  3. Subseabed disposal program annual report, January-December 1979. Volume II. Appendices (principal investigator progress reports). Part 1 of 2

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1981-04-01

    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-O; Part 2 contains Appendices P-FF. Separate abstracts have been prepared of each Appendix for inclusion in the Energy Data Base

  4. 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.

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

    International Nuclear Information System (INIS)

    Hinga, K.R.

    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

  6. Nuclear Law Bulletin No. 98. Volume 2016/2

    International Nuclear Information System (INIS)

    Wetherall, Anthony C.; Soedersten, Anna; Berger, Marjorie; Paez, M.R.; Touitou-Durand, F.; Pelzer, N.; Adomaityte, U.; Majerus, P.; Nowacki, T.; Pospisil, M.; Skraban, A.; Noelliste, N.E.; Popov, A.; Drillat, C.; Reynaers Kini, E.

    2016-01-01

    The Nuclear Law Bulletin is a unique international publication for both professionals and academics in the field of nuclear law. It provides readers with authoritative and comprehensive information on nuclear law developments. Published free online twice a year in both English and French, it features topical articles written by renowned legal experts, covers legislative developments worldwide and reports on relevant case law, bilateral and international agreements as well as regulatory activities of international organisations. Feature articles in this issue include 'Strengthening the international legal framework for nuclear security: Better sooner rather than later'; 'Brexit, Euratom and nuclear proliferation'; and 'McMunn et al. v Babcock and Wilcox Power Generation Group, Inc., et al.: The long road to dismissal'

  7. Nuclear Law Bulletin No. 99. Volume 2017/1

    International Nuclear Information System (INIS)

    Burns, Stephen G.; Lamm, Vanda; Pelzer, Norbert; Popov, A.; ); Chirtes, A.P.; ); Raetzke, C.; Chennoufi, F.; Beyens, M.; Vandeputte, G.; Saric, J.; Touitou-Durand, F.; Pelzer, N.; Adomaityte, U.; Pavlovic, P.; Skraban, A.; Carroll, S.; Averbach, A.; Brown, O.; Irving, I.; Joyner, D.

    2017-01-01

    The Nuclear Law Bulletin is a unique international publication for both professionals and academics in the field of nuclear law. It provides readers with authoritative and comprehensive information on nuclear law developments. Published free online twice a year in both English and French, it features topical articles written by renowned legal experts, covers legislative developments worldwide and reports on relevant case law, bilateral and international agreements as well as regulatory activities of international organisations. Feature articles in this issue include: 'Reformed and reforming: Adapting the licensing process to meet new challenges'; 'Reflections on the development of international nuclear law'; and 'Facing the challenge of nuclear mass tort processing'

  8. Nuclear Law Bulletin No. 97. Volume 2016/1

    International Nuclear Information System (INIS)

    Fischer, D.; Saric, J.; Touitou-Durand, F.; Mannully, Y.; Parle, M.; Adomaityte, U.; Majerus, P.; Adamczyk, K.; Nowacki, T.; Pavlovic, P.; Dovale Hernandez, I.; Ammon, B.; Popov, A.; Drillat, C.; Reynaers Kini, E.

    2016-01-01

    The Nuclear Law Bulletin is a unique international publication for both professionals and academics in the field of nuclear law. It provides readers with authoritative and comprehensive information on nuclear law developments. Published free online twice a year in both English and French, it features topical articles written by renowned legal experts, covers legislative developments worldwide and reports on relevant case law, bilateral and international agreements as well as regulatory activities of international organisations. Feature articles in this issue include 'Nuclear third party liability in Germany' and 'Towards nuclear disarmament: State of affairs in the international legal framework'. Other chapters deal with case laws, legislative and regulatory activities, intergovernmental organisation activities, and documents and legal texts

  9. 10. National Nuclear Science and Technologies Congress Proceedings Full Texts Volume 1

    International Nuclear Information System (INIS)

    2009-01-01

    X. National Nuclear Science and Technologies Congress was held on 6-9 October 2009 in Mugla, Turkey in the course of collaborative organization undertaken by Turkish Atomic Energy Authority, Mugla University and Sitki Kocman Foundation. This first volume of Proceedings Book contains 75 submitted presentations and 36 of them are full texts on applications of nuclear techniques.

  10. Stereological quantification of tumor volume, mean nuclear volume and total number of melanoma cells correlated with morbidity and mortality

    DEFF Research Database (Denmark)

    Bønnelykke-Behrndtz, Marie Louise; Sørensen, Flemming Brandt; Damsgaard, Tine Engberg

    2008-01-01

    potential indicators of prognosis. Sixty patients who underwent surgery at the Department of Plastic Surgery, Aarhus University Hospital, from 1991 to 1994 were included in the study. Total tumor volume was estimated by the Cavalieri technique, total number of tumor cells by the optical dissector principle...... showed a significant impact on both disease-free survival (p=0.001) and mortality (p=0.009). In conclusion, tumor volume and total number of cancer cells were highly reproducible but did not add additional, independent prognostic information regarding the study population.......Stereological quantification of tumor volume, total number of tumor cells and mean nuclear volume provides unbiased data, regardless of the three-dimensional shape of the melanocytic lesion. The aim of the present study was to investigate whether these variables are reproducible and may represent...

  11. The NJOY nuclear data processing system: Volume 2, The NJOY, RECONR, BROADR, HEATR, and THERMR modules

    International Nuclear Information System (INIS)

    MacFarlane, R.E.; Muir, D.W.; Boicourt, R.M.

    1982-05-01

    The NJOY nuclear data processing system is a comprehensive computer code package for producing cross sections and related nuclear parameters from ENDF/B evaluated nuclear data. This volume provides detailed descriptions of the NJOY module, which contains the executive program and utility subroutines used by the other modules, and it discusses the theory and computational methods of four of the modules used for producing pointwise cross sections: RECONR, BROADR, HEATR, and THERMR

  12. International Source Book: Nuclear Fuel Cycle Research and Development Vol 1 Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, K. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lakey, L. T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    1983-07-01

    This document starts with an overview that summarizes nuclear power policies and waste management activities for nations with significant commercial nuclear fuel cycle activities either under way or planned. A more detailed program summary is then included for each country or international agency conducting nuclear fuel cycle and waste management research and development. This first volume includes the overview and the program summaries of those countries listed alphabetically from Argentina to Italy.

  13. Recommendations for a Department of Energy Nuclear Energy R and D Agenda Volume 2 Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The current US nuclear energy policy is primarily formulated as part of the nation`s overall energy policy. In addition, nuclear energy policy is impacted by other US policies, such as those for defense and environment, and by international obligations through their effects on nuclear weapons dismantlement and stewardship, continued reliance on space and naval nuclear power sources, defense waste cleanup, and on nuclear nonproliferation. This volume is composed of the following appendices: Appendix 1--Objectives of the Federal Government Nuclear Energy Related Policies and Research and Development Programs; Appendix 2--Nuclear Energy and Related R and D in the US; Appendix 3--Summary of Issues That Drive Nuclear Energy Research and Development; Appendix 4: Options for Policy and Research and Development; Appendix 5--Pros and Cons of Objectives and Options; and Appendices 6--Recommendations.

  14. Recommendations for a Department of Energy Nuclear Energy R and D Agenda Volume 2 Appendices

    International Nuclear Information System (INIS)

    1997-01-01

    The current US nuclear energy policy is primarily formulated as part of the nation's overall energy policy. In addition, nuclear energy policy is impacted by other US policies, such as those for defense and environment, and by international obligations through their effects on nuclear weapons dismantlement and stewardship, continued reliance on space and naval nuclear power sources, defense waste cleanup, and on nuclear nonproliferation. This volume is composed of the following appendices: Appendix 1--Objectives of the Federal Government Nuclear Energy Related Policies and Research and Development Programs; Appendix 2--Nuclear Energy and Related R and D in the US; Appendix 3--Summary of Issues That Drive Nuclear Energy Research and Development; Appendix 4: Options for Policy and Research and Development; Appendix 5--Pros and Cons of Objectives and Options; and Appendices 6--Recommendations

  15. Pokhran II and Beyond (Emerging Indian Nuclear Posture)

    National Research Council Canada - National Science Library

    Mishra, Jeetendra

    2002-01-01

    .... The nuclear forces, however, are sought only to be minimum possible to credibly deter nuclear weapons use or coercion against India, Considering the imperatives of the Indian deterrence posture...

  16. Monterey Peninsula Water Supply Project. Supplemental Draft Environmental Impact Report/Statement II. Volume 2.

    Science.gov (United States)

    1993-02-01

    Fueled 7,634,0(X) 51 Geothermal 1,302,M(K) 9 Nuclear 2,160,(MX) 14 Total Thermal 11,096,(kM) 74 Hydroelectric 3,877,M(X) 26 Solar 0 0t Total Company...Nuclear 16,273,963 17 "Total Thermal 48,094,316 50 Hydroelectric 8,007,631 8 Solar 35 0 Total Company Generation 56,101,982 58 Helms Pumpback Energy...returnable beverage containers, prohibition of disposable diapers , and other measures to reduce the volume of the urban solid waste streams. Appeaidix 19-B

  17. Nuclear Regulatory Commission issuances, Volume 44, No. 4

    International Nuclear Information System (INIS)

    1996-10-01

    This report includes the issuances received in October 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. 15 issuances were received and are abstracted individually in the database: Louisiana Energy Services, U.S. Enrichment Corporation, Yankee Atomic Electric Company, General Public Utilities Nuclear Corporation, James L. Shelton, Juan Guzman, Northern States Power Company, TESTCO Inc., Washington Public Power Supply System, all nuclear plants, Cleveland Electric Illuminating Company, Duke Power Company, Florida Power Corporation, and Northeast Nuclear Energy Company (2 issuances). No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

  18. Nuclear Regulatory Commission issuances, September 1995. Volume 42, Number 3

    International Nuclear Information System (INIS)

    1995-09-01

    This book contains an issuance of the Atomic Safety and Licensing Board and a Director's Decision, both of the US Nuclear Regulatory Commission. The issuance concerns the dismissal of a case by adopting a settlement reached by the Staff of the Nuclear Regulatory Commission and a Radiation Safety Officer of a hospital in which the safety officer pled guilty to deliberate misconduct. The Director's Decision was to deny a petition to impose a fine on Tennessee Valley Authority concerning alleged harassment of the petitioner and to appoint an independent arbitration board to review all past complaints filed against TVA concerning the Watts Bar Nuclear Plant

  19. Nuclear Regulatory legislation: 103d Congress. Volume 1, No. 3

    International Nuclear Information System (INIS)

    1995-08-01

    This document is a compilation of nuclear regulatory legislation and other relevant material through the 103d Congress, 2d Session. This compilation has been prepared for use as a resource document, which the NRC intends to update at the end of every Congress. The contents of NUREG-0980 include the Atomic Energy Act of 1954, as amended; Energy Reorganization Act of 1974, as amended, Uranium Mill Tailings Radiation Control Act of 1978; Low-Level Radioactive Waste Policy Act; Nuclear Waste Policy Act of 1982; and NRC Authorization and Appropriations Acts. Other materials included are statutes and treaties on export licensing, nuclear non-proliferation, and environmental protection

  20. Nuclear regulatory legislation, 102d Congress. Volume 2, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    This document is a compilation of nuclear regulatory legislation and other relevant material through the 102d Congress, 2d Session. This compilation has been prepared for use as a resource document, which the NRC intends to update at the end of every Congress. The contents of NUREG-0980 include The Atomic Energy Act of 1954, as amended; Energy Reorganization Act of 1974, as amended, Uranium Mill Tailings Radiation Control Act of 1978; Low-Level Radioactive Waste Policy Act; Nuclear Waste Policy Act of 1982; and NRC Authorization and Appropriations Acts. Other materials included are statutes and treaties on export licensing, nuclear non-proliferation, and environmental protection.

  1. Nuclear regulatory legislation: 102d Congress. Volume 1, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    This document is a compilation of nuclear regulatory legislation and other relevant material through the 102d Congress, 2d Session. This compilation has been prepared for use as a resource document, which the NRC intends to update at the end of every Congress. The contents of NUREG-0980 include: The Atomic Energy Act of 1954, as amended; Energy Reorganization Act of 1974, as amended, Uranium Mill Tailings Radiation Control Act of 1978; Low-Level Radioactive Waste Policy Act; Nuclear Waste Policy Act of 1982; and NRC Authorization and Appropriations Acts. Other materials included are statutes and treaties on export licensing, nuclear non-proliferation, and environmental protection.

  2. Nuclear Regulatory Commission issuances, September 1995. Volume 42, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This book contains an issuance of the Atomic Safety and Licensing Board and a Director`s Decision, both of the US Nuclear Regulatory Commission. The issuance concerns the dismissal of a case by adopting a settlement reached by the Staff of the Nuclear Regulatory Commission and a Radiation Safety Officer of a hospital in which the safety officer pled guilty to deliberate misconduct. The Director`s Decision was to deny a petition to impose a fine on Tennessee Valley Authority concerning alleged harassment of the petitioner and to appoint an independent arbitration board to review all past complaints filed against TVA concerning the Watts Bar Nuclear Plant.

  3. US Nuclear Regulatory Commission, 1984 annual report. Volume 1

    International Nuclear Information System (INIS)

    1985-01-01

    This is the 10th annual report of the US Nuclear Regulatory Commission (NRC). This report covers the major activities, events, decisions and planning that took place during fiscal year 1984 (October 1983 through September 1984) within the NRC or involving the NRC. Information is presented concerning 1984 highlights and planning for 1985; reactor regulation; cleanup at Three Mile Island Unit 2; operational experience; nuclear materials; safeguards; waste management; inspection, enforcement, quality assurance, and emergency preparedness; cooperation with the States; international programs; nuclear regulatory research; proceedings and litigation; and management and communication

  4. Nuclear Regulatory legislation: 103d Congress. Volume 1, No. 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    This document is a compilation of nuclear regulatory legislation and other relevant material through the 103d Congress, 2d Session. This compilation has been prepared for use as a resource document, which the NRC intends to update at the end of every Congress. The contents of NUREG-0980 include the Atomic Energy Act of 1954, as amended; Energy Reorganization Act of 1974, as amended, Uranium Mill Tailings Radiation Control Act of 1978; Low-Level Radioactive Waste Policy Act; Nuclear Waste Policy Act of 1982; and NRC Authorization and Appropriations Acts. Other materials included are statutes and treaties on export licensing, nuclear non-proliferation, and environmental protection.

  5. Nuclear Regulatory legislation: 103d Congress. Volume 2, No. 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    This document is a compilation of nuclear regulatory legislation and other relevant material through the 103d Congress, 2d Session. This compilation has been prepared for use as a resource document, which the NRC intends to update at the end of every Congress. The contents of NUREG-0980 include the Atomic Energy Act of 1954, as amended; Energy Reorganization Act of 1974, as amended, Uranium Mill Tailings Radiation Control Act of 1978; Low-Level Radioactive Waste Policy Act; Nuclear Waste Policy Act of 1982; and NRC Authorization and Appropriations Acts. Other materials included are statutes and treaties on export licensing, nuclear non-proliferation, and environmental protection.

  6. Nuclear Regulatory Commission issuances, Volume 44, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    This report includes the issuances received in October 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. 15 issuances were received and are abstracted individually in the database: Louisiana Energy Services, U.S. Enrichment Corporation, Yankee Atomic Electric Company, General Public Utilities Nuclear Corporation, James L. Shelton, Juan Guzman, Northern States Power Company, TESTCO Inc., Washington Public Power Supply System, all nuclear plants, Cleveland Electric Illuminating Company, Duke Power Company, Florida Power Corporation, and Northeast Nuclear Energy Company (2 issuances). No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.

  7. Nuclear Regulatory legislation: 103d Congress. Volume 2, No. 3

    International Nuclear Information System (INIS)

    1995-08-01

    This document is a compilation of nuclear regulatory legislation and other relevant material through the 103d Congress, 2d Session. This compilation has been prepared for use as a resource document, which the NRC intends to update at the end of every Congress. The contents of NUREG-0980 include the Atomic Energy Act of 1954, as amended; Energy Reorganization Act of 1974, as amended, Uranium Mill Tailings Radiation Control Act of 1978; Low-Level Radioactive Waste Policy Act; Nuclear Waste Policy Act of 1982; and NRC Authorization and Appropriations Acts. Other materials included are statutes and treaties on export licensing, nuclear non-proliferation, and environmental protection

  8. Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1

    International Nuclear Information System (INIS)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety

  9. Proton nuclear magnetic resonance and spectrophotometric studies of nickel(II)-iron(II) hybrid hemoglobins

    International Nuclear Information System (INIS)

    Shibayama, N.; Inubushi, T.; Morimoto, H.; Yonetani, T.

    1987-01-01

    Ni(II)-Fe(II) hybrid hemoglobins, α(Fe) 2 β(Ni) 2 and α(Ni) 2 β(Fe) 2 , have been characterized by proton nuclear magnetic resonance with Ni(II) protoporphyrin IX (Ni-PP) incorporated in apoprotein, which serves as a permanent deoxyheme. α(Fe) 2 β(Ni) 2 , α(Ni) 2 β(Fe) 2 , and NiHb commonly show exchangeable proton resonances at 11 and 14 ppm, due to hydrogen-bonded protons in a deoxy-like structure. Upon binding of carbon monoxide (CO) to α(Fe) 2 β(Ni) 2 , these resonances disappear at pH 6.5 to pH 8.5. On the other hand, the complementary hybrid α(Ni) 2 β(Fe-CO) 2 showed the 11 and 14 ppm resonances at low pH. Upon raising pH, the intensities of both resonances are reduced, although these changes are not synchronized. Electronic absorption spectra and hyperfine-shifted proton resonances indicate that the ligation of CO in the β(Fe) subunits induced changes in the coordination and spin states of Ni-PP in the α subunits. In a deoxy-like structure, the coordination of Ni-PP in the α subunits is predominantly in a low-spin (S = 0) four-coordination state, whereas in an oxy-like structure the contribution of a high-spin (S = 1) five-coordination state markedly increased. Ni-PP in the β subunits always takes a high-spin five-coordination state regardless of solution conditions and the state of ligation in the partner α(Fe) subunits. In the β(Ni) subunits, a significant downfield shift of the proximal histidyl N/sub δ/H resonance and a change in the absorption spectrum of Ni-PP were detected, upon changing the quaternary structure of the hybrid. The chemical shifts were analyzed in terms of the E11-Val methyls vs. the porphyrin rings in hybrid Hbs

  10. Simulation model for wind energy storage systems. Volume II. Operation manual. [SIMWEST code

    Energy Technology Data Exchange (ETDEWEB)

    Warren, A.W.; Edsinger, R.W.; Burroughs, J.D.

    1977-08-01

    The effort developed a comprehensive computer program for the modeling of wind energy/storage systems utilizing any combination of five types of storage (pumped hydro, battery, thermal, flywheel and pneumatic). An acronym for the program is SIMWEST (Simulation Model for Wind Energy Storage). The level of detail of SIMWEST is consistent with a role of evaluating the economic feasibility as well as the general performance of wind energy systems. The software package consists of two basic programs and a library of system, environmental, and load components. Volume II, the SIMWEST operation manual, describes the usage of the SIMWEST program, the design of the library components, and a number of simple example simulations intended to familiarize the user with the program's operation. Volume II also contains a listing of each SIMWEST library subroutine.

  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. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

    International Nuclear Information System (INIS)

    Cottrell, W.B.; Passiakos, M.

    1982-06-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index

  13. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Passiakos, M.

    1982-06-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

  14. Nuclear safety, Volume 38, Number 1, January--March 1997

    Energy Technology Data Exchange (ETDEWEB)

    None

    1997-03-01

    This journal contains nine articles which fall under the following categories: (1) general safety considerations; (2) control and instrumentation; (3) design features (4) environmental effects; (5) US Nuclear Regulatory Commission information and analyses; and (6) recent developments.

  15. Nuclear fuel cycle. International overview. Updating of volume 1

    International Nuclear Information System (INIS)

    1985-01-01

    It is presented the updating of the vol.I of the 'Nuclear fuel cycle - International overview' series which informs about the nuclear fuel cycle in the main countries that supply and /or use nuclear energy. It intends to serve the managerial staff since it gives a global view of the fuel cycle as well as its extent in each of the countries focalized. Information about Japan, Federal Republic of Germany, United Kingdon, France and Canada are presented. At first a summary about the situation of each country is presented and then all data for each country is presented in a tree - graphyic type, using an analysis and synthesis method, developed at the Nuclear Information Center, Brazil. (E.G.) [pt

  16. Ocean Thermal Energy Converstion (OTEC) test facilities study program. Final report. Volume II. Part B

    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 B provides an annotated test list and describes component tests and system tests.

  17. Results of site validation experiments. Volume II. Supporting documents 5 through 14

    Energy Technology Data Exchange (ETDEWEB)

    1983-01-01

    Volume II contains the following supporting documents: Summary of Geologic Mapping of Underground Investigations; Logging of Vertical Coreholes - ''Double Box'' Area and Exploratory Drift; WIPP High Precision Gravity Survey; Basic Data Reports for Drillholes, Brine Content of Facility Internal Strata; Mineralogical Content of Facility Interval Strata; Location and Characterization of Interbedded Materials; Characterization of Aquifers at Shaft Locations; and Permeability of Facility Interval Strate.

  18. Nuclear electric propulsion mission engineering study. Volume 2: Final report

    Science.gov (United States)

    1973-01-01

    Results of a mission engineering analysis of nuclear-thermionic electric propulsion spacecraft for unmanned interplanetary and geocentric missions are summarized. Critical technologies associated with the development of nuclear electric propulsion (NEP) are assessed, along with the impact of its availability on future space programs. Outer planet and comet rendezvous mission analysis, NEP stage design for geocentric and interplanetary missions, NEP system development cost and unit costs, and technology requirements for NEP stage development are studied.

  19. Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2

    International Nuclear Information System (INIS)

    Osborn, R.N.; Olson, J.; Sommers, P.E.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators

  20. Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.7--Nuclear electronics and nuclear detection technology sub-volume

    International Nuclear Information System (INIS)

    2014-05-01

    Progress report on nuclear science and technology in China (Vol. 3) includes 57 articles which are communicated on the third national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the seventh one, the content is about Nuclear electronics and nuclear detection technology sub-volume

  1. Improving nuclear regulation. NEA regulatory guidance booklets volumes 1-14

    International Nuclear Information System (INIS)

    2011-01-01

    A common theme throughout the series of NEA regulatory guidance reports, or 'green booklets', is the premise that the fundamental objective of all nuclear safety regulatory bodies is to ensure that nuclear facilities are continuously maintained and operated in an acceptably safe manner. In meeting this objective the regulator must bear in mind that it is the operator that has responsibility for safely operating the nuclear facility; the role of the regulator is to assess and to provide assurance regarding the operator's activities in terms of assuming that responsibility. The full series of these reports was brought together in one edition for the first time in 2009 and was widely found to be a useful resource. This second edition comprises 14 volumes, including the latest on The Nuclear Regulator's Role in Assessing Licensee Oversight of Vendor and Other Contracted Services. The reports address various challenges that could apply throughout the lifetime of a nuclear facility, including design, siting, manufacturing, construction, commissioning, operation, maintenance and decommissioning. The compilation is intended to serve as a knowledge management tool both for current regulators and the new nuclear professionals and organisations entering the regulatory field. Contents: Executive Summary; Regulatory Challenges: 1. The Role of the Nuclear Regulator in Promoting and Evaluating Safety Culture; 2. Regulatory Response Strategies for Safety Culture Problems; 3. Nuclear Regulatory Challenges Related to Human Performance; 4. Regulatory Challenges in Using Nuclear Operating Experience; 5. Nuclear Regulatory Review of Licensee Self-assessment (LSA); 6. Nuclear Regulatory Challenges Arising from Competition in Electricity Markets; 7. The Nuclear Regulatory Challenge of Judging Safety Back-fits; 8. The Regulatory Challenges of Decommissioning Nuclear Reactors; 9. The Nuclear Regulator's Role in Assessing Licensee Oversight of Vendor and Other Contracted Services

  2. Provisions relating to Nuclear Energy. II - International Conventions

    International Nuclear Information System (INIS)

    This book published by the Portuguese Junta de Energia Nuclear (Nuclear Energy Commission) reproduces in Portuguese and in the original language (English or French), texts of a series of international conventions in the nuclear field and the Statutes of international nuclear organisations and undertakings. The following are among the texts included: the Statutes of the IAEA, NEA, Eurochemic; the Euratom Treaty; the Tlatelolco Treaty; the co-operation agreement between Portugal and the United States on the peaceful uses of nuclear energy. (NEA) [fr

  3. Review of the KBS II plan for handling and final storage of unreprocessed spent nuclear fuel

    International Nuclear Information System (INIS)

    1980-01-01

    The Swedish utilities programme for disposal of spent nuclear fuel elements (KBS II) is summarized. Comments and criticism to the programme are given by experts from several foreign or international institutions. (L.E.)

  4. Estimating the cold war mortgage: The 1995 baseline environmental management report. Volume II: Site summaries

    International Nuclear Information System (INIS)

    1995-03-01

    This volume, Volume II presents the site data that was used to generate the Department of Energy's (DOE) initial Baseline Environmental Management Report (BEMR). The raw data was obtained by DOE field personnel from existing information sources and anticipated environmental management strategies for their sites and was tempered by general assumptions and guidance developed by DOE Headquarters personnel. This data was then integrated by DOE Headquarters personnel and modified to ensure that overall constraints such as funding and waste management capacity were addressed. The site summaries are presented by State and broken out by discrete activities and projects. The Volume I Glossary has been repeated to facilitate the reader's review of Volume II. The information presented in the site summaries represents the best data and assumptions available as of February 1, 1995. Assumptions that have not been mandated by formal agreement with appropriate regulators and other stakeholders do not constitute decisions by the Department nor do they supersede existing agreements. In addition, actions requiring decisions from external sources regarding unknowns such as future land use and funding/scheduling alternatives, as well as internal actions such as the Department's Strategic Realignment initiative, will alter the basis and general assumptions used to generate the results for this report. Consequently, the numbers presented in the site summaries do not represent outyear budget requests by the field installations

  5. State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants

    International Nuclear Information System (INIS)

    1980-04-01

    A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report

  6. Classification of tubulo-papillary renal cortical tumours using estimates of nuclear volume

    DEFF Research Database (Denmark)

    Brooks, B; Sørensen, Flemming Brandt; Olsen, S

    1993-01-01

    The classification of renal cortical tumours is problematic, with no clear division of benign from malignant tumours. Unbiased stereological estimates of volume-weighted nuclear volume (nuclear vv) were obtained by point sampling of nuclear intercepts in a retrospective study of 36 variably sized...... = 241 microns 3) and 15 tumours classified as renal cell carcinomas with diameters > 3 cm, or aggressive histological pattern (average nuclear vv = 229 microns 3) (2p = 0.68). In this subtype of renal cortical tumours, estimates of nuclear vv do not support the historical convention of using a 3 cm...... tumour diameter as the dividing line between adenomas and carcinomas, but support the theory of a single group of tumours. As most of the truly incidental renal cortical tumours are less than 1 cm in diameter, this limit could be considered. Such small benign cortical nodules have never been reported...

  7. Models of cognitive behavior in nuclear power plant personnel. A feasibility study: summary of results. Volume 1

    International Nuclear Information System (INIS)

    Woods, D.D.; Roth, E.M.; Hanes, L.F.

    1986-07-01

    This report summarizes the results of a feasibility study to determine if the current state of models of human cognitive activities can serve as the basis for improved techniques for predicting human error in nuclear power plants emergency operations. Based on the answer to this question, two subsequent phases of research are planned. Phase II is to develop a model of cognitive activities, and Phase III is to test the model. The feasibility study included an analysis of the cognitive activities that occur in emergency operations and an assessment of the modeling concepts/tools available to capture these cognitive activities. The results indicated that a symbolic processing (or artificial intelligence) model of cognitive activities in nuclear power plants is both desirable and feasible. This cognitive model can be built upon the computational framework provided by an existing artificial intelligence system for medical problem solving, called Caduceus. The resulting cognitive model will increase the capability to capture the human contribution to risk in probabilistic risk assessment studies. Volume 1 summarizes the major findings and conclusions of the study. Volume 2 provides a complete description of the methods and results, including a synthesis of the cognitive activities that occur during emergency operations, and a literature review on cognitive modeling relevant to nuclear power plants. 19 refs

  8. Nuclear safety. Volume 36, Number 2, July--December 1995

    Energy Technology Data Exchange (ETDEWEB)

    None

    1995-12-01

    The primary scope of the journal is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. The following subjects are covered here: (1) the Chernobyl accident; (2) general safety considerations; (3) accident analysis; (4) design features; (5) environmental effects; (6) operating experiences; (7) US NRC information and analyses; and (8) recent developments. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  9. Nuclear Power Options Viability Study. Volume 4. Bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Trauger, D B; White, J D; Sims, J W [eds.

    1986-09-01

    Documents in the Nuclear Power Options Viability Study (NPOVS) bibliography are classified under one of four headings or categories as follows: nuclear options; light water reactors; liquid metal reactors; and high temperature reactors. The collection and selection of these documents, beginning early in 1984 and continuing through March of 1986, was carried out in support of the study's objective: to explore the viabilities of several nuclear electric power generation options for commercial deployment in the United States between 2000 and 2010. There are approximately 550 articles, papers, reports, and books in the bibliography that have been selected from some 2000 surveyed. The citations have been made computer accessible to facilitate rapid on-line retrieval by keyword, author, corporate author, title, journal name, or document number.

  10. Nuclear Power Options Viability Study. Volume 4. Bibliography

    International Nuclear Information System (INIS)

    Trauger, D.B.; White, J.D.; Sims, J.W.

    1986-09-01

    Documents in the Nuclear Power Options Viability Study (NPOVS) bibliography are classified under one of four headings or categories as follows: nuclear options; light water reactors; liquid metal reactors; and high temperature reactors. The collection and selection of these documents, beginning early in 1984 and continuing through March of 1986, was carried out in support of the study's objective: to explore the viabilities of several nuclear electric power generation options for commercial deployment in the United States between 2000 and 2010. There are approximately 550 articles, papers, reports, and books in the bibliography that have been selected from some 2000 surveyed. The citations have been made computer accessible to facilitate rapid on-line retrieval by keyword, author, corporate author, title, journal name, or document number

  11. Current Status of World Nuclear Fuel Cycle Technology (II): Japan

    International Nuclear Information System (INIS)

    Jeong, Chang Joon; Ko, Won Il

    2007-06-01

    Japan needs to import around 80% of its energy requirements. In 1966, the first nuclear power plant began operation, nuclear energy has been a national strategic priority since 1973. Currently, 55 reactors provide around 30% of the country's electricity. Japanese energy policy has been conducted by the energy security and minimization of dependence of energy imports. The main factors regarding nuclear power are: - Continue to have nuclear power as a main factor of electricity production. - Recycle uranium and plutonium, and start domestic reprocessing from 2005. - Continue to develop fast breeder reactors to increase uranium utilization. - Promote the nuclear transparency to the public, emphasizing safety and non-proliferation. Also, the prospects of Asia's nuclear energy growth has been reviewed

  12. Nuclear Regulatory Commission issuances. Volume 44, Number 2

    International Nuclear Information System (INIS)

    1996-08-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decision on Petitions for Rulemaking (DPRM). The topics of this publication include the dismissal of a suit brought against Georgia Power Company in the transfer of Vogtle Electric Generating Plant, units 1 and 2 to Southern Nuclear; and denial of a petition to review the entire licensing process for Watts Bar Nuclear Plant, Unit 1 operated by the Tennessee Valley Authority

  13. Nuclear electric propulsion mission engineering study. Volume 1: Executive summary

    Science.gov (United States)

    1973-01-01

    Results of a mission engineering analysis of nuclear-thermionic electric propulsion spacecraft for unmanned interplanetary and geocentric missions are summarized. Critical technologies associated with the development of nuclear electric propulsion (NEP) are assessed. Outer planet and comet rendezvous mission analysis, NEP stage design for geocentric and interplanetary missions, NEP system development cost and unit costs, and technology requirements for NEP stage development are studied. The NEP stage design provides both inherent reliability and high payload mass capability. The NEP stage and payload integration was found to be compatible with the space shuttle.

  14. Safe Management and disposal of nuclear waste. Volume 3

    International Nuclear Information System (INIS)

    1993-01-01

    These proceedings of the international conference Safewaste 93, volume 3 are divided into three poster sessions bearing on: poster session P-1: Radioactive waste management and actinide burning; poster session P-2: Safety aspects of radioactive waste disposal; poster session P-3: Transport and disposal

  15. 17th DOE nuclear air cleaning conference: proceedings. Volume 2

    International Nuclear Information System (INIS)

    First, M.W.

    1983-02-01

    Volume 2 contains papers presented at the following sessions: adsorption; noble gas treatment; personnel education and training; filtration and filter testing; measurement and instrumentation; air cleaning equipment response to accident related stress; containment venting air cleaning; and an open end session. Twenty-eight papers were indexed separately for inclusion in the Energy Data Base. Ten papers had been entered earlier

  16. 17th DOE nuclear air cleaning conference: proceedings. Volume 1

    International Nuclear Information System (INIS)

    First, M.W.

    1983-02-01

    Volume 1 contains papers presented at the following sessions: fuel reprocessing; radioidine; waste processing;filtration and filter testing; and contamination control and personnel protection. Twenty-three individual papers were indexed for inclusion in the Energy Data Base. Nine papers were entered into the data base previously

  17. 17th DOE nuclear air cleaning conference: proceedings. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    First, M.W. (ed.)

    1983-02-01

    Volume 2 contains papers presented at the following sessions: adsorption; noble gas treatment; personnel education and training; filtration and filter testing; measurement and instrumentation; air cleaning equipment response to accident related stress; containment venting air cleaning; and an open end session. Twenty-eight papers were indexed separately for inclusion in the Energy Data Base. Ten papers had been entered earlier.

  18. Aseismic design of the Heysham II Nuclear Power Station

    International Nuclear Information System (INIS)

    Day, J.W.

    1983-01-01

    A brief description of the seismic criteria established for use with the Steam Generating Heavy Water Reactor (SCHWR) and taken for the Heysham II Project is given. The qualification strategy adopted for Heysham II is described, and a brief overview is given of some of the more important design changes required for seismic purposes on that station

  19. Nuclear Regulatory Commission issuances, January 1995. Volume 41, Number 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-01

    This book contains issuances of the Atomic Safety and Licensing Boards for January 1995. The issuances include Babcock and Wilcox Company materials license; Hydro Resources, Inc. application for uranium mining; low-level waste storage in Utah; communication of emerging and existing generic, technical issues with PWR owners groups; and radioactive waste management by Sierra Nuclear Corporation.

  20. Nuclear Regulatory Commission issuances: August 1994. Volume 40, Number 2

    International Nuclear Information System (INIS)

    1994-08-01

    This report contains the collected issuances of the US Nuclear Regulatory Commission for the month of August, 1994. The report includes issuances of the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. Some of the entities involved include Gulf States Utility company, Sequoyah Fuels Corporation and General Atomics, Georgia Power Company, and Arizona Public Service Company

  1. Nuclear Regulatory Commission issuances, January 1995. Volume 41, Number 1

    International Nuclear Information System (INIS)

    1995-01-01

    This book contains issuances of the Atomic Safety and Licensing Boards for January 1995. The issuances include Babcock and Wilcox Company materials license; Hydro Resources, Inc. application for uranium mining; low-level waste storage in Utah; communication of emerging and existing generic, technical issues with PWR owners groups; and radioactive waste management by Sierra Nuclear Corporation

  2. Delays in nuclear power plant construction. Volume I. Final report

    International Nuclear Information System (INIS)

    1977-01-01

    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

  3. Recovery of Navy distillate fuel from reclaimed product. Volume II. Literature review

    Energy Technology Data Exchange (ETDEWEB)

    Brinkman, D.W.; Whisman, M.L.

    1984-11-01

    In an effort to assist the Navy to better utilize its waste hydrocarbons, NIPER, with support from the US Department of Energy, is conducting research designed to ultimately develop a practical technique for converting Reclaimed Product (RP) into specification Naval Distillate Fuel (F-76). This first phase of the project was focused on reviewing the literature and available information from equipment manufacturers. The literature survey has been carefully culled for methodology applicable to the conversion of RP into diesel fuel suitable for Navy use. Based upon the results of this study, a second phase has been developed and outlined in which experiments will be performed to determine the most practical recycling technologies. It is realized that the final selection of one particular technology may be site-specific due to vast differences in RP volume and available facilities. A final phase, if funded, would involve full-scale testing of one of the recommended techniques at a refueling depot. The Phase I investigations are published in two volumes. Volume 1, Technical Discussion, includes the narrative and Appendices I and II. Appendix III, a detailed Literature Review, includes both a narrative portion and an annotated bibliography containing about 800 references and abstracts. This appendix, because of its volume, has been published separately as Volume 2.

  4. Is nuclear energy safe for workers and the public. II

    International Nuclear Information System (INIS)

    Rasmussen, N.

    1976-01-01

    Dr. Rasmussen first examines the safety and economics records of nuclear power and finds them unassailable. Since these two items could not cause dissension, he observes that dissension evolves from safety of the power plant itself, the issue of diversion to use nuclear materials to make weapons, and from the disposal of wastes. He reviews how radioactivity can be released to cause an accident, and then cites figures comparing accidents each year in the U.S. with those projected for nuclear accidents. To date, not one person has been killed with the operation of a nuclear power plant. Dr. Rasmussen believes that taking advantage of nuclear power far outweighs its risks since ''we have seen what unemployment at the level of 9 or 10 percent has done in this country...to go without power that our industrial society needs to provide livelihood for our citizens will almost surely result in something much more dramatic than that.''

  5. Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 1: Title II design report

    International Nuclear Information System (INIS)

    1995-09-01

    The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. Volume 1 provides a comprehensive narrative description of the proposed facility and systems, the basis for each of the systems design, and the engineering assessments that were performed to support the technical basis of the Title II design. The intent of the system description presented is to provide WHC an understanding of the facilities and equipment provided and the A/E's perspective on how these systems will operate

  6. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 1

    International Nuclear Information System (INIS)

    Wuschke, D.M.; Gillespie, P.A.; Main, D.E.

    1985-07-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second assessment was performed in 1984 and is documented in the Second Interim assessment of the Canadian Concept for Nuclear Fuel Waste Disposal Volumes 1 to 4. This volume, entitled Summary, is a condensation of Volumes 2, 3 and 4. It briefly describes the Canadian nuclear fuel waste disposal concept, and the methods and results of the second interim pre-closure and post-closure assessments of that concept. 46 refs

  7. Airborne gamma-ray spectrometer and magnetometer survey: Cameron A, Arizona, detail area. Volume II A. Final report

    International Nuclear Information System (INIS)

    1983-01-01

    Volume II A contains appendices for: stacked profiles; geologic histograms; geochemical histograms; speed and altitude histograms; geologic statistical tables; geochemical statistical tables; magnetic and ancillary profiles; and test line data

  8. Airborne gamma-ray spectrometer and magnetometer survey: Monument Valley B, Utah, detail area. Volume II A. Final report

    International Nuclear Information System (INIS)

    1983-01-01

    Volume II A contains appendices for: stacked profiles; geologic histograms; geochemical histograms; speed and altitude histograms; geologic statistical tables; geochemical statistical tables; magnetic and ancillary profiles; and test line data

  9. Airborne gamma-ray spectrometer and magnetometer survey: Monument Valley B, Utah, detail area. Volume II B. Final report

    International Nuclear Information System (INIS)

    1983-01-01

    Volume II B contains appendices for: flight line maps; geology maps; explanation of geologic legend; flight line/geology maps; radiometric contour maps; magnetic contour maps; and geochemical factor analysis maps

  10. Airborne gamma-ray spectrometer and magnetometer survey: Monument Valley A, Utah, detail area. Volume II B. Final report

    International Nuclear Information System (INIS)

    1983-01-01

    Volume II B contains appendices for: flight line maps; geology maps; explanation of geologic legend; flight line/geology maps; radiometric contour maps; magnetic contour maps; multi-variant analysis maps; and geochemical factor analysis maps

  11. Nuclear Regulatory Commission issuances, April 1995. Volume 41, Number 4

    International Nuclear Information System (INIS)

    1995-04-01

    This book contains issuances of the Nuclear Regulatory Commission and of the Atomic Safety and Licensing Boards, and an issuance of the Director's decision. The issuances concern a petition filed by Dr. James E Bauer seeking interlocutory Commission review of the Atomic Safety and Licensing Board's order imposing several restrictions on Dr. Bauer; a denial of an Interveners' Petition for Review addressing the application of Babcock and Wilcox for a renewal of its Special Nuclear Materials License; granting a motion for a protective order, by Sequoyah Fuel Corporation and General Atomics, limiting the use of the protected information to those individuals participating in the litigation and for the purposes of the litigation only; granting a Petitioner's petition for leave to intervene and request for a hearing concerning Georgia Institute of Technology (Georgia Tech Research Reactor) renewal of a facility license; and a denial of a petition filed by Mr. Ted Dougherty requesting a shutdown of the San Onofre Nuclear Generating Station based on concerns regarding the vulnerability of the plant to earthquakes and defensibility of the plant to a terrorist threat

  12. Nuclear Regulatory Commission issuances, April 1995. Volume 41, Number 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This book contains issuances of the Nuclear Regulatory Commission and of the Atomic Safety and Licensing Boards, and an issuance of the Director`s decision. The issuances concern a petition filed by Dr. James E Bauer seeking interlocutory Commission review of the Atomic Safety and Licensing Board`s order imposing several restrictions on Dr. Bauer; a denial of an Interveners` Petition for Review addressing the application of Babcock and Wilcox for a renewal of its Special Nuclear Materials License; granting a motion for a protective order, by Sequoyah Fuel Corporation and General Atomics, limiting the use of the protected information to those individuals participating in the litigation and for the purposes of the litigation only; granting a Petitioner`s petition for leave to intervene and request for a hearing concerning Georgia Institute of Technology (Georgia Tech Research Reactor) renewal of a facility license; and a denial of a petition filed by Mr. Ted Dougherty requesting a shutdown of the San Onofre Nuclear Generating Station based on concerns regarding the vulnerability of the plant to earthquakes and defensibility of the plant to a terrorist threat.

  13. Modeling of the core of Atucha II nuclear power plant

    International Nuclear Information System (INIS)

    Blanco, Anibal

    2007-01-01

    This work is part of a Nuclear Engineer degree thesis of the Instituto Balseiro and it is carried out under the development of an Argentinean Nuclear Power Plant Simulator. To obtain the best representation of the reactor physical behavior using the state of the art tools this Simulator should couple a 3D neutronics core calculation code with a thermal-hydraulics system code. Focused in the neutronic nature of this job, using PARCS, we modeled and performed calculations of the nuclear power plant Atucha 2 core. Whenever it is possible, we compare our results against results obtained with PUMA (the official core code for Atucha 2). (author) [es

  14. Management of Large Volumes of Waste Arising in a Nuclear or Radiological Emergency

    International Nuclear Information System (INIS)

    2017-10-01

    This publication, prepared in light of the IAEA Action Plan on Nuclear Safety developed after the accident at the Fukushima Daiichi nuclear power plant, addresses the management of large volumes of radioactive waste arising in a nuclear or radiological emergency, as part of overall emergency preparedness. The management of large volumes of waste will be one of many efforts to be dealt with to allow recovery of affected areas, to support return of evacuated or relocated populations and preparations for normal social and economic activities, and/or to mitigate additional environmental impacts. The publication is intended to be of use to national planners and policy makers, facility and programme managers, and other professionals responsible for developing and implementing national plans and strategies to manage radioactive waste arising from nuclear or radiological emergencies.

  15. Volumes, Masses, and Surface Areas for Shippingport LWBR Spent Nuclear Fuel in a DOE SNF Canister

    International Nuclear Information System (INIS)

    J.W. Davis

    1999-01-01

    The purpose of this calculation is to estimate volumes, masses, and surface areas associated with (a) an empty Department of Energy (DOE) 18-inch diameter, 15-ft long spent nuclear fuel (SNF) canister, (b) an empty DOE 24-inch diameter, 15-ft long SNF canister, (c) Shippingport Light Water Breeder Reactor (LWBR) SNF, and (d) the internal basket structure for the 18-in. canister that has been designed specifically to accommodate Seed fuel from the Shippingport LWBR. Estimates of volumes, masses, and surface areas are needed as input to structural, thermal, geochemical, nuclear criticality, and radiation shielding calculations to ensure the viability of the proposed disposal configuration

  16. Proceedings of the 21st DOE/NRC nuclear air cleaning conference; Volume 2, Sessions 9--16

    Energy Technology Data Exchange (ETDEWEB)

    First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

    1991-02-01

    The 21st meeting of the Department of Energy/Nuclear Regulatory Commission (DOE/NRC) Nuclear Air Cleaning Conference was held in San Diego, CA on August 13--16, 1990. The proceedings have been published as a two volume set. Volume 2 contains sessions covering adsorbents, nuclear codes and standards, modelling, filters, safety, containment venting and a review of nuclear air cleaning programs around the world. Also included is the list of attendees and an index of authors and speakers. (MHB)

  17. Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository - Volume 3: Appendices

    International Nuclear Information System (INIS)

    Taylor, L.L.; Wilson, J.R.; Sanchez, L.C.; Aguilar, R.; Trellue, H.R.; Cochrane, K.; Rath, J.S.

    1998-01-01

    The United States Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3)

  18. Joining of Tungsten Cermet Nuclear Fuel, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — Nuclear Thermal Propulsion (NTP) has been identified as a critical technology needed for human missions to Mars and beyond due to its increased specific impulse...

  19. Progress on Chinese evaluated nuclear parameter library (CENPL) (II)

    International Nuclear Information System (INIS)

    Su Zhongdi; Ge Zhigang; Zhou Chunmei

    1993-01-01

    CENPL collected, evaluated and compiled nuclear basic constants and model parameters. CENPL-1 contain six sub-libraries, they are: (1) Atomic masses and characteristic constants for nuclear ground states; (2) discrete level schemes and branch ratios of γ decay; (3) level density parameters; (4) giant dipole resonance parameters for γ-ray strength function (5) fission barrier parameter; (6) optical model parameters. Their progresses are introduced

  20. Nuclear data standards - International Evaluation Co-operation volume 7

    International Nuclear Information System (INIS)

    Carlson, A.D.; Shibata, K.; Vonach, H.; Hambsch, F.J.; Chen, Z.; Hofmann, H.M.; Oh, S.Y.; Badikov, S.A.; Gai, E.V.; Pronyaev, V.G.; Smith, D.L.; Hale, G.M.; Kawano, T.; Larson, N.M.

    2006-01-01

    A Working Party on International Evaluation Co-operation was established under the sponsorship of the OECD/NEA Nuclear Science Committee (NSC) to promote the exchange of information on nuclear data evaluations, validation and related topics. Its aim is also to provide a framework for co-operative activities between members of the major nuclear data evaluation projects. This includes the possible exchange of scientists in order to encourage co-operation. Requirements for experimental data resulting from this activity are compiled. The working party determines common criteria for evaluated nuclear data files with a view to assessing and improving the quality and completeness of evaluated data. The parties to the project are: ENDF (United States), JEFF/EFF (NEA Data Bank member countries) and JENDL (Japan). Co-operation with evaluation projects of non-OECD countries is organised through the Nuclear Data Section of the International Atomic Energy Agency (IAEA). This report was issued by Subgroup 7, which was in charge of producing new evaluated neutron cross-section standards. When starting the project, there was a general consensus on the need to update these standards, as significant improvements had been made to the experimental database since 1991 when the last evaluation of these standards was performed. The present work was accomplished through efficient collaboration between a task force of the US Cross-section Evaluation Working Group (CSEWG), a Co-ordinated Research Project (CRP) of the International Atomic Energy Agency (IAEA) and Subgroup 7 of the Working Party on International Evaluation Co-operation (WPEC) of the NEA Nuclear Science Committee. Work is reported on the results of an international effort to evaluate the neutron cross-section standards. The evaluations include the H(n,n), 6 Li(n,t), 10 B(n,α), 10 B(n,α1γ), 197 Au(n,γ), 235 U(n,f) and 238 U(n,f) standard reactions. Evaluations were also produced for the non-standard 238 U(n,γ) and 239 Pu

  1. Nuclear Regulatory Commission Issuances: February 1995. Volume 41, Number 2

    International Nuclear Information System (INIS)

    1995-02-01

    This book contains an issuance of the Nuclear Regulatory Commission and a Director's Decision. The issuance concerns consideration by the Commission of appeals from both the Initial Decision and a Reconsideration Order issued by the Presiding Officer involving two materials license amendment applications filed by the University of Missouri. The Director's Decision from the Office of Enforcement denies petitions filed by Northeast Utilities employees requesting that accelerated enforcement action be taken against Northeast Utilities for activities concerned with NU's fitness-for-duty program

  2. Nuclear Regulatory Commission issuances, Volume 46, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    This report includes the issuances received in October 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. Five issuances were received on the following subjects: (1) decontamination and decommissioning funding for Sequoyah Fuels Corporation and General Atomics; (2) involvement in NRC-licensed activities by Aharon Ben-Haim; (3) Barnett Industrial X-Ray, Inc.; (4) spent fuel storage installation at Northern States Power Company; and (5) Vermont Yankee Nuclear Power Station. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.

  3. Nuclear Regulatory Commission issuances, Volume 46, No. 4

    International Nuclear Information System (INIS)

    1997-10-01

    This report includes the issuances received in October 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. Five issuances were received on the following subjects: (1) decontamination and decommissioning funding for Sequoyah Fuels Corporation and General Atomics; (2) involvement in NRC-licensed activities by Aharon Ben-Haim; (3) Barnett Industrial X-Ray, Inc.; (4) spent fuel storage installation at Northern States Power Company; and (5) Vermont Yankee Nuclear Power Station. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

  4. Nuclear Regulatory Commission issuances. Volume 44, Number 3

    International Nuclear Information System (INIS)

    1996-09-01

    This report includes issuances received during September 1996. After reviewing in detail each of the claims made in this informal proceeding the presiding officer sustained the staff of the USNRC in its determination that the applicant did not pass the written portion of his examination to become a licensed operator of a nuclear power plant. In the proceeding concerning citizen group challenges to the decommissioning plan for the Rowe Yankee power station, the licensing board grants licensee Yankee Atomic Electric Company's motion for summary disposition

  5. Nuclear Regulatory Commission issuances. Volume 44, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    This report includes issuances received during September 1996. After reviewing in detail each of the claims made in this informal proceeding the presiding officer sustained the staff of the USNRC in its determination that the applicant did not pass the written portion of his examination to become a licensed operator of a nuclear power plant. In the proceeding concerning citizen group challenges to the decommissioning plan for the Rowe Yankee power station, the licensing board grants licensee Yankee Atomic Electric Company`s motion for summary disposition.

  6. 2009 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

    International Nuclear Information System (INIS)

    2009-01-01

    After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety (safety organisation, general measures, measures related to various risks, inspections, control of emergency situations, audits and second level control, measures in basic nuclear installations) and radioprotection (organisation, significant facts, dosimeter results). It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of measurements of releases and of their impact on the environment (chemical and radiological assessment). Then after a description of measures to limit the volume of stored radioactive wastes and their impact on health and on the environment, tables indicate the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation) for which a significant event occurred on the 6 October 2009. For these installations, release measurements concern gaseous and liquid releases

  7. 2007 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

    International Nuclear Information System (INIS)

    2007-01-01

    After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety: safety organisation, general measures, measures related to various risks, control of emergency situations, inspections, audits and second level control, measures in basic nuclear installations. It describes the measures concerning the radioprotection on this site: organisation, significant facts, and dose measurement results. It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of release measurements and of radiological and chemical assessments of the impact these releases on the environment. The report then describes measures implemented to limit the volume of stored radioactive wastes and also their impact on health and on the environment. It provides a series of tables indicating the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. It reports the recommendations expressed by the CHSCT (committee on hygiene, security and working conditions) after the 2006 report. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation), for which the significant events occurred on the 13. of March and on the 25. of May 2007. For these installations, release measurements concern gaseous and liquid releases

  8. Volume I. Environmental effects on contents of Cs-137 and Sr-90 in milk. Volume II. Appendices

    International Nuclear Information System (INIS)

    1981-01-01

    Milk, animal fodders, soils, humans, livestock, and wildlife on or near 55 dairy farms in Utah were assayed for radionuclide content. Effects of soil chemistry, water supply, plant type, farming practices, geographic location, altitude, rainfall, and other ecological differences were sought by intensive analysis. Although many analyses have not been completed, several cause-effect relationships have been defined. Wet-lands yield more 137 Cs, 131 I, or 90 Sr to milk under like conditions of fallout intensity than dry-lands. In most cases, the station with the highest yield is also practicing wet grazing. 90 Sr and 137 Cs content of milk is enhanced by sandy soils. Increased altitude and higher rainfall lead to higher yields of 90 Sr and 137 Cs in milk. Levels of 137 Cs in milk increase from south to north, and Utah can be divided into several regions, each having a characteristic level of 90 Sr and 137 Cs in milk, meat, and fodders. Poor pastures (over-grazed to the extent that stem bases are eaten and much soil is exposed) yield more 137 Cs and 90 Sr than improved pastures. Feeding green chop alfalfa or putting the animals on the meadows causes marked but temporary increases in the 90 Sr and 137 Cs content of the milk. However, the annual yield for two stations of similar ecology in the same geographic area is essentially the same. Experimental details are presented in Volume I. The appendices in Volume II are made up primarily of the data compiled at the 78 stations

  9. World Energy Data System (WENDS). Volume II. Country data, CZ-KS

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-06-01

    The World Energy Data System contains organized data on those countries and international organizations that may have critical impact on the world energy scene. Included in this volume, Vol. II, are Czechoslovakia, Denmark, Egypt, Finland, France, Germany (East), Germany (West), Greece, Guinea, India, Indonesia, Iran, Italy, Japan, and Korea (South). The following topics are covered for most of the countries: economic, demographic, and educational profiles; energy policy; indigenous energy resources and uses; forecasts, demand, exports, imports of energy supplies; environmental considerations of energy use; power production facilities; energy industries; commercial applications of energy; research and development activities of energy; and international activities.

  10. Final report of the Multiprogram Laboratory Panel Energy Research Advisory Board. Volume II. Support studies

    International Nuclear Information System (INIS)

    Spiewak, I.; Guthrie, M.P.; Nichols, J.P.; Preston, E.L.; West, C.D.; Wilbanks, T.J.; Wilkes, B.Y.; Zerby, A.C.

    1982-09-01

    Volume II - support studies for nine national laboratories include: report of statistical data on the multiprogram laboratories; examples of national laboratory use in foreign countries; domestic models for national laboratory utilization; relationships of laboratories with industry and universities; uses of laboratories for training industrial R and D personnel; legal mandates and constraints on the national laboratories; with appendices on facts about Harwell, CEN-Saclay, TNO, Studsvik, and JAERI-Tokai; the Requirements Boards of the United Kingdom Department of Industry; impact of President's FY 1983 budget; and the PNL experiment

  11. Dead layer and active volume determination for GERDA Phase II detectors

    Energy Technology Data Exchange (ETDEWEB)

    Lehnert, Bjoern [TU Dresden (Germany); Collaboration: GERDA-Collaboration

    2013-07-01

    The GERDA experiment investigates the neutrinoless double beta decay of {sup 76}Ge and is currently running Phase I of its physics program. Using the same isotope as the Heidelberg Moscow (HDM) experiment, GERDA aims to directly test the claim of observation by a subset of the HDM collaboration. For the update to Phase II of the experiment in 2013, the collaboration organized the production of 30 new Broad Energy Germanium (BEGe) type detectors from original 35 kg enriched material and tested their performance in the low background laboratory HADES in SCK.CEN, Belgium. With additional 20 kg of detectors, GERDA aims to probe the degenerated hierarchy scenario. One of the crucial detector parameters is the active volume (AV) fraction which directly enters into all physics analysis. This talk presents the methodology of dead layer and AV determination with different calibration sources such as {sup 241}Am, {sup 133}Ba, {sup 60}Co and {sup 228}Th and the results obtained for the new Phase II detectors. Furthermore, the AV fraction turned out to be the largest systematic uncertainty in the analysis of Phase I data which makes it imperative to reduce its uncertainty for Phase II. This talk addresses the major contributions to the AV uncertainty and gives an outlook for improvements in Phase II analysis.

  12. Personal, societal, and ecological values of wilderness: Sixth World Wilderness Congress proceedings on research, management, and allocation, Volume II

    Science.gov (United States)

    Alan E. Watson; Greg H. Aplet; John C. Hendee

    2000-01-01

    The papers contained in Volume II of these Proceedings represent a combination of papers originally scheduled for the delayed 1997 meeting of the World Wilderness Congress and those submitted in response to a second call for papers when the Congress was rescheduled for October 24-29, 1998, in Bangalore, India. Just as in Volume I, the papers are divided into seven...

  13. Forecasting the Future Food Service World of Work. Final Report. Volume II. Centralized Food Service Systems. Service Management Reports.

    Science.gov (United States)

    Powers, Thomas F., Ed.; Swinton, John R., Ed.

    Volume II of a three-volume study on the future of the food service industry considers the effects that centralized food production will have on the future of food production systems. Based on information from the Fair Acres Project and the Michigan State University Vegetable Processing Center, the authors describe the operations of a centralized…

  14. Kempe's engineers year-book for 1977. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    Prockter, C.E. (ed.)

    1977-01-01

    The second volume of this two-volume yearbook contains data on: electrical and electronic engineering; aerodynamics and aircraft propulsion; gas turbines; internal combustion engines; motor vehicles; fuels; fluidics; nuclear energy; gas and gas engineering; steam engineering and steam turbines; marine diesel engines; naval architecture; mining engineering; industrial explosives; air compression, pneumatic equipment, etc.; refrigeration, heating, ventilation and air conditioning; lighting; industrial safety and protection; fire protection; highway engineering; surveying; foundation and earthwork; cements, mortars and clay products; buildings; public health engineering; concretes; design of steel structures; bridges and bridgework; paints and coatings; patents, designs and trade marks; depreciation; legal notes for engineers; factory planning and layout; and agricultural engineering. (1325p.) A subject index is provided. (LCL)

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

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

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

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

    International Nuclear Information System (INIS)

    1980-06-01

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

  17. Nuclear-Recoil Energy Scale in CDMS II Silicon Dark-Matter Detectors

    Energy Technology Data Exchange (ETDEWEB)

    Agnese, R.; et al.

    2018-03-07

    The Cryogenic Dark Matter Search (CDMS II) experiment aims to detect dark matter particles that elastically scatter from nuclei in semiconductor detectors. The resulting nuclear-recoil energy depositions are detected by ionization and phonon sensors. Neutrons produce a similar spectrum of low-energy nuclear recoils in such detectors, while most other backgrounds produce electron recoils. The absolute energy scale for nuclear recoils is necessary to interpret results correctly. The energy scale can be determined in CDMS II silicon detectors using neutrons incident from a broad-spectrum $^{252}$Cf source, taking advantage of a prominent resonance in the neutron elastic scattering cross section of silicon at a recoil (neutron) energy near 20 (182) keV. Results indicate that the phonon collection efficiency for nuclear recoils is $4.8^{+0.7}_{-0.9}$% lower than for electron recoils of the same energy. Comparisons of the ionization signals for nuclear recoils to those measured previously by other groups at higher electric fields indicate that the ionization collection efficiency for CDMS II silicon detectors operated at $\\sim$4 V/cm is consistent with 100% for nuclear recoils below 20 keV and gradually decreases for larger energies to $\\sim$75% at 100 keV. The impact of these measurements on previously published CDMS II silicon results is small.

  18. Symposium on engineering with nuclear explosives. Proceedings. Volume 2

    International Nuclear Information System (INIS)

    1970-05-01

    This symposium on 'Engineering with Nuclear Explosives' reports to the Plowshare community, both national and international, the progress achieved since April 1964, the date of the Third Plowshare Symposium. In structuring the technical presentations, contributions of broadest interest were placed at the beginning, thus forming a common base of current information and applied science understanding developed in support of Plowshare technology. Sessions of speciality or pertaining to specific areas of application and engineering follow logically in the program. The Plenary Session reviewed the current status of the Plowshare Program from the technical, government, and industrial points of view. The 112 papers presented at 15 technical sessions covered all technical aspects of the Plowshare Program. The conference summary reviewed principal themes, areas of significant advance, and subjects requiring further attention that emerged during the technical conference. This proceedings is the record of the symposium

  19. Symposium on engineering with nuclear explosives. Proceedings. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1970-05-15

    This symposium on 'Engineering with Nuclear Explosives' reports to the Plowshare community, both national and international, the progress achieved since April 1964, the date of the Third Plowshare Symposium. In structuring the technical presentations, contributions of broadest interest were placed at the beginning, thus forming a common base of current information and applied science understanding developed in support of Plowshare technology. Sessions of speciality or pertaining to specific areas of application and engineering follow logically in the program. The Plenary Session reviewed the current status of the Plowshare Program from the technical, government, and industrial points of view. The 112 papers presented at 15 technical sessions covered all technical aspects of the Plowshare Program. The conference summary reviewed principal themes, areas of significant advance, and subjects requiring further attention that emerged during the technical conference. This proceedings is the record of the symposium.

  20. Nuclear Power Options Viability Study. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    Trauger, D.B.; White, J.D.; Booth, R.S.

    1986-09-01

    Innovative reactor concepts are described and evaluated in accordance with criteria established in the study. The reactors to be studied were selected on the basis of three ground rules: (1) the potential for commercialization between 2000 to 2010, (2) economic competitiveness with coal, and (3) the degree of passive safety in the design. The concepts, classified by coolants, were light water reactors, liquid metal reactors, and high-temperature reactors, and most were of modular design. Although the information available is not adequate for a definitive evaluation of economic competitiveness, all of the concepts appear to be potentially viable in the time frame selected. Public and institutional acceptance of nuclear power was found to be affected primarily by four issues: (1) operational safety, (2) waste handling and disposal, (3) construction and operating costs, and (4) the adequacy of management and regulatory controls

  1. Nuclear Regulatory Commission issuances: Volume 39, Number 6

    International Nuclear Information System (INIS)

    1994-06-01

    This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). Issuances of the Nuclear Regulatory Commission include: (1) Advanced Medical Systems, Inc.; (2) Henry Allen, Diane Marrone, and Susan Settino; and (3) Westinghouse Electric Corporation. Issuances of the Atomic Safety and Licensing Boards include: (1) Sequoyah Fuels Corporation and General Atomics Corporation and (2) Umetco Minerals Corporation. Issuances of Director's Decisions include: (1) Advanced Medical Systems, Inc., and (2) Boston Edison Company and all boiling water reactors. The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

  2. Development of methods for measuring materials nuclear characteristics, Phases, I, II, II and IV

    International Nuclear Information System (INIS)

    Maglic, R.

    1963-04-01

    This report contains the following phases of the project 'measurement of nuclear characteristics of reactor materials': nuclear performances of the neutron chopper; method for measuring total effective cross sections by transmission method on the chopper; review of methods for measuring activation cross sections; measurement of neutron spectra of the RA reactor and measurement of total effective cross section of gold by using the chopper

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

    International Nuclear Information System (INIS)

    1979-12-01

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

  4. Estimates of nuclear volume in plaque and tumor-stage mycosis fungoides. A new prognostic indicator

    DEFF Research Database (Denmark)

    Brooks, B; Sørensen, Flemming Brandt; Thestrup-Pedersen, K

    1994-01-01

    It is well documented that mycosis fungoides (MF), a cutaneous T-cell lymphoma, has a variable clinical course. Unbiased stereological estimates of three-dimensional volume-weighted mean nuclear size (nucl vV) of mycosis cells were obtained in a retrospective study of 18 patients with a total of ...

  5. Nuclear Fuel Recovery and Recycling Center. License application, PSAR, volume 3

    International Nuclear Information System (INIS)

    1976-01-01

    Volume 3 comprises Chapter 5 which provides descriptive information on Nuclear Fuel Recovery and Recycling Center buildings and other facilities, including their locations. The design features discussed include those used to withstand environmental and accidental forces and to insure radiological protection

  6. Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 3: Specifications

    International Nuclear Information System (INIS)

    1995-09-01

    The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. Volume 3 is a compilation of the construction specifications that will constitute the Title II materials and performance specifications. This volume contains CSI specifications for non-equipment related construction material type items, performance type items, and facility mechanical equipment items. Data sheets are provided, as necessary, which specify the equipment overall design parameters

  7. Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 3: Specifications

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. Volume 3 is a compilation of the construction specifications that will constitute the Title II materials and performance specifications. This volume contains CSI specifications for non-equipment related construction material type items, performance type items, and facility mechanical equipment items. Data sheets are provided, as necessary, which specify the equipment overall design parameters.

  8. 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)

  9. Stereological estimates of nuclear volume in the prognostic evaluation of primary flat carcinoma in situ of the urinary bladder

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Jacobsen, F

    1991-01-01

    Primary, flat carcinoma in situ of the urinary bladder is rare and its behaviour is unpredictable. The aim of this retrospective study was to obtain base-line data and investigate the prognostic value of unbiased, stereological estimates of the volume-weighted mean nuclear volume, nuclear vv, in ...

  10. 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.)

  11. Performances on nuclear activation analysis by TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Capannesi, G.; Rosada, A.

    1986-01-01

    Progresses in methodological research and connected applications in the field of activation analysis are introduced. Some peculiar characteristics on the TRIGA MARK II reactor have enabled the possibility of obtaining interesting results. The particular, the rotating radiation device Lazy Susan, with a capability of 40 positionings, permits homogeneity in neutron flux and energy spectrum stability within 15%. High level of precision and accuracy are obtained in analytic. Applications of major interest have been: - reference material certification; - forensic applications; - electrolytic cell productivity evaluation. The TRIGA MARK II reactor is equipped with a thermal column throughout a D 2 O diaphragm with a thickness of 70 cm. The available neutron flux has no fast and epithermal components. Via this facility a method has been tested for the instrumental determination of Al in Si metal of solar and electronic degree. (author)

  12. Environmental control implications of generating electric power from coal. Technology status report. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-12-01

    This is the first in a series of reports evaluating environmental control technologies applicable to the coal-to-electricity process. The technologies are described and evaluated from an engineering and cost perspective based upon the best available information obtained from utility experience and development work in progress. Environmental control regulations and the health effects of pollutants are also reviewed. Emphasis is placed primarily upon technologies that are now in use. For SO/sub 2/ control, these include the use of low sulfur coal, cleaned coal, or flue-gas desulfurization systems. Electrostatic precipitators and fabric filters used for the control of particulate matter are analyzed, and combustion modifications for NO/sub x/ control are described. In each area, advanced technologies still in the development stage are described briefly and evaluated on the basis of current knowledge. Fluidized-bed combustion (FBC) is a near-term technology that is discussed extensively in the report. The potential for control of SO/sub 2/ and NO/sub x/ emissions by use of FBC is analyzed, as are the resulting solid waste disposal problems, cost estimates, and its potential applicability to electric utility systems. Volume II presents the detailed technology analyses complete with reference citations. This same material is given in condensed form in Volume I without references. A brief executive summary is also given in Volume I.

  13. Nuclear pulse. II - Ensuring delivery of the doomsday signal

    Science.gov (United States)

    Broad, W. J.

    1981-06-01

    The ability of the communications systems on which U.S. strategic forces depend to survive the electromagnetic pulse (EMP) effects of a nuclear blast in the upper atmosphere is examined. It is shown that the Bell system telephone network, Autovon, on which much military communication presently depends, is especially vulnerable to EMP; while satellite and microwave communications networks are expected to be more resistant to attack. Satellites are, though, vulnerable to killer-satellite attack. Much promise is seen in the conversion of ground communications links to fiber-optic form, which is inherently highly resistant to EMP. A nuclear bomb detonated 200 miles above Nebraska would affect communications equipment throughout the contiguous U.S. with peak fields of 500,000 volts/meter.

  14. 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

    ...). This report covers Phase II findings and recommendations. In Phase II, the Task Force found that the lack of interest in and attention to the nuclear mission and nuclear deterrence, as discussed in our Phase I report, go well beyond the Air...

  15. 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.

  16. Draft Environmental Impact Statement on a proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel. Volume 1

    International Nuclear Information System (INIS)

    1995-03-01

    The United States Department of Energy and United States Department of State are jointly proposing to adopt a policy to manage spent nuclear fuel from foreign research reactors. Only spent nuclear fuel containing uranium enriched in the United States would be covered by the proposed policy. The purpose of the proposed policy is to promote U.S. nuclear weapons nonproliferation policy objectives, specifically by seeking to reduce highly-enriched uranium from civilian commerce. Environmental effects and policy considerations of three Management Alternative approaches for implementation of the proposed policy are assessed. The three Management Alternatives analyzed are: (1) acceptance and management of the spent nuclear fuel by the Department of Energy in the United States, (2) management of the spent nuclear fuel at one or more foreign facilities (under conditions that satisfy United States nuclear weapons nonproliferation policy objectives), and (3) a combination of components of Management Alternatives 1 and 2 (Hybrid Alternative). A No Action Alternative is also analyzed. For each Management Alternative, there are a number of alternatives for its implementation. For Management Alternative 1, this document addresses the environmental effects of various implementation alternatives such as varied policy durations, management of various quantities of spent nuclear fuel, and differing financing arrangements. Environmental impacts at various potential ports of entry, along truck and rail transportation routes, at candidate management sites, and for alternate storage technologies are also examined. For Management Alternative 2, this document addresses two subalternatives: (1) assisting foreign nations with storage; and (2) assisting foreign nations with reprocessing of the spent nuclear fuel. Management Alternative 3 analyzes a hybrid alternative. This document is Vol. 1 of 2 plus summary volume

  17. Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society

    International Nuclear Information System (INIS)

    Koponen, B.L.; Hampel, V.E.

    1982-01-01

    This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41

  18. Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society

    Energy Technology Data Exchange (ETDEWEB)

    Koponen, B.L.; Hampel, V.E.

    1982-10-21

    This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41.

  19. Stereological estimation of nuclear volume and other quantitative histopathological parameters in the prognostic evaluation of supraglottic laryngeal squamous cell carcinoma

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Bennedbaek, O; Pilgaard, J

    1989-01-01

    The aim of this study was to investigate various approaches to the grading of malignancy in pre-treatment biopsies from patients with supraglottic laryngeal squamous cell carcinoma. The prospects of objective malignancy grading based on stereological estimation of the volume-weighted mean nuclear...... volume, nuclear Vv, and nuclear volume fraction, Vv(nuc/tis), along with morphometrical 2-dimensional estimation of nuclear density index, NI, and mitotic activity index, MI, were investigated and compared with the current morphological, multifactorial grading system. The reproducibility among two...... observers of the latter was poor in the material which consisted of 35 biopsy specimens. Unbiased estimates of nuclear Vv were on the average 385 microns3 (CV = 0.44), with more than 90% of the associated variance attributable to differences in nuclear Vv among individual lesions. Nuclear Vv was positively...

  20. Nuclear criticality experiments from 1943 to 1978. An annotated bibliography: Volume 1, main listing

    International Nuclear Information System (INIS)

    Koponen, B.L.; Wilcox, T.P.; Hampel, V.E.

    1979-05-01

    This report only describes the bibliography which contains 1067 citations from the literature of critical and near-critical nuclear experiments. The bibliography provides an up-to-date index to reports containing useful data for many types of criticality studies. Most of the reports can provide specifications for relatively simple critical configurations necessary for validating nuclear constants and calculational techniques. The reports of more than 1143 experimentors at 38 international facilities since 1943 are cross-referenced. This collection contains the prototypes of many different designs of nuclear reactors and studies performed to ensure the safe use of fissile materials in chemical processing plants, storage facilities, and transportation containers. The bibliography has three volumes. Volume 1 contains the main listing of citations with abstracts. Volume 2 is a set of indexes organized by report number, publication date, experimental facility, and author name. Volume 3 provides a subject index, concorded on the significant keyphrases derived from titles, and an index of key terms extracted from titles and abstracts. The bibliography was printed by computer as a selection from a computerized system at Lawrence Livermore Laboratory containing information and data on criticality experiments

  1. Nuclear criticality experiments from 1943 to 1978: an annotated bibliography. Volume 1. Main listing

    Energy Technology Data Exchange (ETDEWEB)

    Koponen, B.L.; Wilcox, T.P.; Hampel, V.E.

    1979-04-24

    The bibliography contains 1067 citations from the literature of critical and near-critical nuclear experiments. It provides an up-to-date index to reports containing useful data for many types of criticality studies. Most of the reports can provide specifications for relatively simple critical configurations necessary for validating nuclear constants and calculational techniques. The reports of more than 1143 experimentors at 38 international facilities since 1943 are cross-referenced. The collection contains the prototypes of many different designs of nuclear reactors and studies performed to insure the safe use of fissile materials in chemical processing plants, storage facilities, and transportation containers. The bibliography has three volumes. Volume 1 contains the main listing of citations with abstracts. Volume 2 is a set of indexes organized by report number, publication date, experimental facility, and author name. Volume 3 provides a subject index, concorded on the significant keyphrases derived from titles, and an index of keyterms derived from titles, and an index of keyterms extracted from titles and abstracts. The bibliography was printed by computer as a selection from a computerized system at Lawrence Livermore Laboratory contaning information and data on criticality experiments.

  2. Quark-nuclear hybrid star equation of state with excluded volume effects

    Science.gov (United States)

    Kaltenborn, Mark Alexander Randolph; Bastian, Niels-Uwe Friedrich; Blaschke, David Bernhard

    2017-09-01

    A two-phase description of the quark-nuclear matter hybrid equation of state that takes into account the effect of excluded volume in both the hadronic and the quark-matter phases is introduced. The nuclear phase manifests a reduction of the available volume as density increases, leading to a stiffening of the matter. The quark-matter phase displays a reduction of the effective string tension in the confining density functional from available volume contributions. The nuclear equation of state is based upon the relativistic density-functional model DD2 with excluded volume. The quark-matter equation of state is based upon a quasiparticle model derived from a relativistic density-functional approach and will be discussed in greater detail. The interactions are decomposed into mean scalar and vector components. The scalar interaction is motivated by a string potential between quarks, whereas the vector interaction potential is motivated by higher-order interactions of quarks leading to an increased stiffening at high densities. As an application, we consider matter under compact star constraints of electric neutrality and β equilibrium. We obtain mass-radius relations for hybrid stars that form a third family, disconnected from the purely hadronic star branch, and fulfill the 2 M⊙ constraint.

  3. Optimization in the nuclear fuel cycle II: Surface contamination

    International Nuclear Information System (INIS)

    Pereira, W.S.; Silva, A.X.; Lopes, J.M.; Carmo, A.S.; Fernandes, T.S.; Mello, C.R.; Kelecom, A.

    2017-01-01

    Optimization is one of the bases of radioprotection and aims to move doses away from the dose limit that is the borderline of acceptable radiological risk. This work aims to use the monitoring of surface contamination as a tool of the optimization process. 53 surface contamination points were analyzed at a nuclear fuel cycle facility. Three sampling points were identified with monthly mean values of contamination higher than 1 Bq ∙ cm -2 , points 28, 42 and 47. These points were indicated for the beginning of the optimization process

  4. Cardiac nuclear medicine, part II: diagnosis of coronary artery diseas

    International Nuclear Information System (INIS)

    Polak, J.F.; Holman, B.L.

    1981-01-01

    Diagnosing coronary artery disease is difficult and requires careful consideration of the roles and limitations of the tests used. Standard ECG tests are not reliable indicators of the presence of disease in asymptomatic patients. Thallium stress testing to assess ischemia and exercise ventriculography to assess functional status of the heart are limited in sensitivity and specificity. This is the second of a three-part series on cardiac nuclear medicine. Part I (Med. Instrum., May-June, 1981) focused on the commonly used examinations in cardiac physiology and pathophysiology. Part III will focus on myocardial infarction and other cardiac diseases

  5. Reactor building design of nuclear power plant ATUCHA II, Argentina

    International Nuclear Information System (INIS)

    Rufino, R.E.; Hermann, E.R.; Richter, E.

    1984-01-01

    It is presented the civil engineering project carried out by the joint venture Hochtief - Techint-Bignoli (HTB) for the reactor building at the Atucha II power plant (PHWR of 745 MWe) in Buenos Aires. All the other civil projects at Atucha II are also being carried out by HTB. This building has the same general characteristics of the PWR plants developed by KWU in Germany, known for the spherical steel containment 56m in diameter. Nevertheless, it differs from those principally in the equipment lay-out and the remarkable foundation depth. From the basic engineering provided by ENACE, the joint venture has had to face the challenge of designing a tridimensional structure of large size. This has necessitated using simplified models which had to be superimposed, since the use of only one spatial mode would be highly inadequate, lacking the flexibility necessary to absorb the numerous modifications that this type of project undergoes during construction. In addition, this procedure has eliminated resorting to numerous and costly computer processings. (Author) [pt

  6. 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.

  7. Heater test planning for the Near Surface Test Facility at the Hanford reservation. Volume II. Appendix

    International Nuclear Information System (INIS)

    DuBois, A.; Binnall, E.; Chan, T.; McEvoy, M.; Nelson, P.; Remer, J.

    1979-04-01

    Volume II contains the following information: theoretical support for radioactive waste storage projects - development of data analysis methods and numerical models; injectivity temperature profiling as a means of permeability characterization; geophysical holes at the Near Surface Test Facility (NSTF), Hanford; proposed geophysical and hydrological measurements at NSTF; suggestions for characterization of the discontinuity system at NSTF; monitoring rock property changes caused by radioactive waste storage using the electrical resistivity method; microseismic detection system for heated rock; Pasco Basin groundwater contamination study; a letter to Mark Board on Gable Mountain Faulting; report on hydrofracturing tests for in-situ stress measurement, NSTF, Hole DC-11, Hanford Reservation; and borehole instrumentation layout for Hanford Near Surface Test Facility

  8. Proposed Tenaska Washington II Generation Project : Final Environmental Impact Statement. Volume 2: Public Involvement.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1994-01-01

    In regard to the proposed Tenaska Washington II Generation Project, the goal of the Bonneville Power Administration`s (BPA) Environmental Impact Statement (EIS) public involvement process is to determine the issues to be examined and pertinent analyses to be conducted and to solicit comments on the content and quality of information presented in the Draft Environmental Impact Statement (DEIS). Comments and questions are solicited from the public and government agencies during the scoping process and during the comment period and public hearing on the DEIS, to find out what is of most concern to them. The end product of the public involvement process is the Comment Report which follows in part of this volume on Public Involvement.

  9. Journal of Sustainable Development of Energy, Water and Environment Systems - Volume II

    Directory of Open Access Journals (Sweden)

    Neven Duić

    2014-12-01

    Full Text Available The Journal of Sustainable Development of Energy, Water and Environment Systems – JSDEWES is an international journal dedicated to the improvement and dissemination of knowledge on methods, policies and technologies for increasing the sustainability of development by de-coupling growth from natural resources and replacing them with knowledge based economy, taking into account its economic, environmental and social pillars, as well as methods for assessing and measuring sustainability of development, regarding energy, transport, water, environment and food production systems and their many combinations. In total 32 manuscripts were published in Volume II, all of them reviewed by at least two reviewers. The Journal of Sustainable Development of Energy, Water and Environment Systems would like to thank reviewers for their contribution to the quality of the published manuscripts.

  10. Coal liquefaction: A research and development needs assessment: Final report, Volume II

    Energy Technology Data Exchange (ETDEWEB)

    Schindler, H.D.; Burke, F.P.; Chao, K.C.; Davis, B.H.; Gorbaty, M.L.; Klier, K.; Kruse, C.W.; Larsen, J.W.; Lumpkin, R.E.; McIlwain, M.E.; Wender, I.; Stewart, N.

    1989-03-01

    Volume II of this report on an assessment of research needs for coal liquefaction contains reviews of the five liquefaction technologies---direct, indirect, pyrolysis, coprocessing, and bioconversion. These reviews are not meant to be encyclopedic; several outstanding reviews of liquefaction have appeared in recent years and the reader is referred to these whenever applicable. Instead, these chapters contain reviews of selected topics that serve to support the panel's recommendations or to illustrate recent accomplishments, work in progress, or areas of major research interest. At the beginning of each of these chapters is a brief introduction and a summary of the most important research recommendations brought out during the panel discussions and supported by the material presented in the review. A review of liquefaction developments outside the US is included. 594 refs., 100 figs., 60 tabs.

  11. Methods of Celestial Mechanics Volume II: Application to Planetary System, Geodynamics and Satellite Geodesy

    CERN Document Server

    Beutler, Gerhard

    2005-01-01

    G. Beutler's Methods of Celestial Mechanics is a coherent textbook for students as well as an excellent reference for practitioners. Volume II is devoted to the applications and to the presentation of the program system CelestialMechanics. Three major areas of applications are covered: (1) Orbital and rotational motion of extended celestial bodies. The properties of the Earth-Moon system are developed from the simplest case (rigid bodies) to more general cases, including the rotation of an elastic Earth, the rotation of an Earth partly covered by oceans and surrounded by an atmosphere, and the rotation of an Earth composed of a liquid core and a rigid shell (Poincaré model). (2) Artificial Earth Satellites. The oblateness perturbation acting on a satellite and the exploitation of its properties in practice is discussed using simulation methods (CelestialMechanics) and (simplified) first order perturbation methods. The perturbations due to the higher-order terms of the Earth's gravitational potential and reso...

  12. The Argentine nuclear policy: evaluation and proposals of the National Atomic Energy Commission. Privatization of the nuclear power plants and the situation of Atucha II. Addendum 1

    International Nuclear Information System (INIS)

    2001-01-01

    An analysis is made of the possible privatization of the nuclear power plants in Argentina. The urgent definition of a nuclear policy for the short, medium and long term is strongly recommended to the Government together with the conclusion of the construction of the Atucha II nuclear power plant

  13. Comparative assessment of TRU waste forms and processes. Volume II. Waste form data, process descriptions, and costs

    International Nuclear Information System (INIS)

    Ross, W.A.; Lokken, R.O.; May, R.P.; Roberts, F.P.; Thornhill, R.E.; Timmerman, C.L.; Treat, R.L.; Westsik, J.H. Jr.

    1982-09-01

    This volume contains supporting information for the comparative assessment of the transuranic waste forms and processes summarized in Volume I. Detailed data on the characterization of the waste forms selected for the assessment, process descriptions, and cost information are provided. The purpose of this volume is to provide additional information that may be useful when using the data in Volume I and to provide greater detail on particular waste forms and processes. Volume II is divided into two sections and two appendixes. The first section provides information on the preparation of the waste form specimens used in this study and additional characterization data in support of that in Volume I. The second section includes detailed process descriptions for the eight processes evaluated. Appendix A lists the results of MCC-1 leach test and Appendix B lists additional cost data. 56 figures, 12 tables

  14. Titanium-II: an evaluated nuclear data file

    International Nuclear Information System (INIS)

    Philis, C.; Howerton, R.; Smith, A.B.

    1977-06-01

    A comprehensive evaluated nuclear data file for elemental titanium is outlined including definition of the data base, the evaluation procedures and judgments, and the final evaluated results. The file describes all significant neutron-induced reactions with elemental titanium and the associated photon-production processes to incident neutron energies of 20.0 MeV. In addition, isotopic-reaction files, consistent with the elemental file, are separately defined for those processes which are important to applied considerations of material-damage and neutron-dosimetry. The file is formulated in the ENDF format. This report formally documents the evaluation and, together with the numerical file, is submitted for consideration as a part of the ENDF/B-V evaluated file system. 20 figures, 9 tables

  15. The nuclear data collecting system designed with ARM and μC/OS-II

    International Nuclear Information System (INIS)

    Wang Chunsheng; Ma Yingjie; Han Feng

    2008-01-01

    Introduce a kind of nuclear data collecting system regarding ARM-μC/OS-II as the platform, gathering the GPS receiver in it. It was detailed to expatiated the key techniques of the multi-channel pulse amplitude analyzer, the interface design of LPC2148, a controller in ARM, and how to expand the RTOS and design applications on μC/OS-II. This system can communicate with the GPS-OEM module by the UART interface, collecting the GPS information synchronously as well as nuclear data. And then save and display them or pass them to the host computer by the USB interface. The embedded and Real-Time system, μC/OS-II build up the real-time and stability of the system and advance the integration. (authors)

  16. Infinite dilution partial molar volumes of platinum(II) 2,4-pentanedionate in supercritical carbon dioxide.

    Science.gov (United States)

    Kong, Chang Yi; Siratori, Tomoya; Funazukuri, Toshitaka; Wang, Guosheng

    2014-10-03

    The effects of temperature and density on retention of platinum(II) 2,4-pentanedionate in supercritical fluid chromatography were investigated at temperatures of 308.15-343.15K and pressure range from 8 to 40MPa by the chromatographic impulse response method with curve fitting. The retention factors were utilized to derive the infinite dilution partial molar volumes of platinum(II) 2,4-pentanedionate in supercritical carbon dioxide. The determined partial molar volumes were small and positive at high pressures but exhibited very large and negative values in the highly compressible near critical region of carbon dioxide. Copyright © 2014 Elsevier B.V. All rights reserved.

  17. Final report on Phase II remedial action at the former Middlesex Sampling Plant and associated properties. Volume 2

    International Nuclear Information System (INIS)

    1985-04-01

    Volume 2 presents the radiological measurement data taken after remedial action on properties surrounding the former Middlesex Sampling Plant during Phase II of the DOE Middlesex Remedial Action Program. Also included are analyses of the confirmatory radiological survey data for each parcel with respect to the remedial action criteria established by DOE for the Phase II cleanup and a discussion of the final status of each property. Engineering details of this project and a description of the associated health physics and environmental monitoring activities are presented in Volume 1

  18. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 3

    International Nuclear Information System (INIS)

    Johansen, K.; Donnelly, K.J.; Gee, J.H.; Green, B.J.; Nathwani, J.S.; Quinn, A.M.; Rogers, B.G.; Stevenson, M.A.; Dunford, W.E.; Tamm, J.A.

    1985-12-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second such assessment was completed in 1984 and is documented in the Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1-4. This, the third volume of the report, summarizes the pre-closure environmental and safety assessments completed by Ontario Hydro for Atomic Energy of Canada Limited. The preliminary results and their sigificance are discussed. 85 refs

  19. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 4

    International Nuclear Information System (INIS)

    Wuschke, D.M.; Gillespie, P.A.; Mehta, K.K.; Henrich, W.F.; LeNeveu, D.M.; Guvanasen, V.M.; Sherman, G.R.; Donahue, D.C.; Goodwin, B.W.; Andres, T.H.

    1985-12-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second such assessment was performed in 1984 and is documented in the Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1-4. This volume, entitled Post-Closure Assessment, describes the methods, models and data used to perform the second post-closure assessment. The results are presented and their significance is discussed. Conclusions and planned improvements are listed. 72 refs

  20. Nuclear reactions with radioactive and stable beams (Part II)

    International Nuclear Information System (INIS)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A.; Lizcano, D.

    2005-12-01

    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: 6 He + 209 Bi, 8 Li + 208 Pb, 10 Be + 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 12 C + 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 18 O + 4 He, 12 C + 12 C, 12 C + 16 O, 16 O + 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 8 B dispersed in an enriched target of 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 7 Be and 6 Li dispersed in this same target. In this same one our stay group participates in other three experiments proposed by collaborators of other institutions (University of Notre Dame, University of Sao Paulo), where the products of the

  1. 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.

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

    International Nuclear Information System (INIS)

    1980-06-01

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

  3. 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

  4. Seismic fragility of nuclear power plant components (Phase II)

    International Nuclear Information System (INIS)

    Bandyopadhyay, K.K.; Hofmayer, C.H.; Kassir, M.K.; Pepper, S.E.

    1990-02-01

    As part of the Component Fragility Program which was initiated in FY 1985, three additional equipment classes have been evaluated. This report contains the fragility results and discussions on these equipment classes which are switchgear, I and C panels and relays. Both low and medium voltage switchgear assemblies have been considered and a separate fragility estimate for each type is provided. Test data on cabinets from the nuclear instrumentation/neutron monitoring system, plant/process protection system, solid state protective system and engineered safeguards test system comprise the BNL data base for I and C panels (NSSS). Fragility levels have been determined for various failure modes of switchgear and I ampersand C panels, and the deterministic results are presented in terms of test response spectra. In addition, the test data have been evaluated for estimating the respective probabilistic fragility levels which are expressed in terms of a median value, an uncertainty coefficient, a randomness coefficient and an HCLPF value. Due to a wide variation of relay design and the fragility level, a generic fragility level cannot be established for relays. 7 refs., 13 figs., 12 tabs

  5. The modernization of the nuclear power plants of Asco and Vandellos II; Modernizacion de las centrales nucleares de Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Martinez Anton, L.

    2011-07-01

    Since the beginning of their commercial operation, the nuclear power plants of Asco and Vandellos have made design modifications aimed at improving the safety, reliability and operation of the plants. From the moment the management of the three plants was brought together within the Association Nuclear Asco-Vandellos II, and within the assets management process, joint strategic modernisation and improvement plans have been developed on the basis of the status of equipment, the evaluation of their ageing, obsolesce, degradations, manufacturers recommendations and/or the application of new regulations. The article lists the mos important actions already carried out or in the project phase for the 3 plants in the primary and secondary system, electrical and instrumentation systems and auxiliary systems, highlighting the problems and the solutions adopted in the most relevant modifications. (Author)

  6. Quality assurance program manual for nuclear power plants. Volume I. Policies

    International Nuclear Information System (INIS)

    1976-01-01

    The Consumers Power Company Quality Assurance Program Manual for Nuclear Power Plants consists of policies and procedures which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumer Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary. CP Co 1--Consumers Power Company QA Program Topical Report is Volume I of this manual and contains Quality Assurance Program Policies applicable during all phases of nuclear power plant design, construction and operation

  7. Research program for seismic qualification of nuclear plant electrical and mechanical equipment. Task 4. Use of fragility in seismic design of nuclear plant equipment. Volume 4

    International Nuclear Information System (INIS)

    Kana, D.D.; Pomerening, D.J.

    1984-08-01

    The Research Program for Seismic Qualification of Nuclear Plant Electrical and Mechanical Equipment has spanned a period of three years and resulted in seven technical summary reports, each of which have covered in detail the findings of different tasks and subtasks, and have been combined into five NUREG/CR volumes. Volume 4 presents study of the use of fragility concepts in the design of nuclear plant equipment and compares the results of state-of-the-art proof testing with fragility testing

  8. Nuclear assay of coal. Volume 7. Coal rheology and its impact on nuclear assay. Final report

    International Nuclear Information System (INIS)

    Hogg, R.; Luckie, P.; Gozani, T.

    1979-01-01

    A number of possible techniques for introducing coal to a continuous on-line nuclear analysis of coal (CONAC) system have been evaluated, including flow methods and nonflow methods. A modified flat-belt feeder system was recommended. The success of such a coal-presentation technique would rely on proper entry to the feed hopper, shape of the withdrawal opening from the feed hopper, and a slow belt speed to minimize demixing

  9. World Energy Data System (WENDS). Volume VII. Nuclear facility profiles, AG--CH. [Brief tabulated information

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile.

  10. World Energy Data System (WENDS). Volume VIII. Nuclear facility profiles, CO--HU. [Brief tabulated information

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile.

  11. World Energy Data System (WENDS). Volume IX. Nuclear facility profiles, IN--PL. [Brief tabulated information

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile.

  12. World Energy Data System (WENDS). Volume VIII. Nuclear facility profiles, CO--HU

    International Nuclear Information System (INIS)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile

  13. World Energy Data System (WENDS). Volume IX. Nuclear facility profiles, IN--PL

    International Nuclear Information System (INIS)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile

  14. World Energy Data System (WENDS). Volume VII. Nuclear facility profiles, AG--CH

    International Nuclear Information System (INIS)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile

  15. World Energy Data System (WENDS). Volume X. Nuclear facility profiles, PO--ZA

    International Nuclear Information System (INIS)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile

  16. World Energy Data System (WENDS). Volume X. Nuclear facility profiles, PO--ZA. [Brief tabulated information

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    In this compendium each profile of a nuclear facility is a capsule summary of pertinent facts regarding that particular installation. The facilities described include the entire fuel cycle in the broadest sense, encompassing resource recovery through waste management. Power plants and all US facilities have been excluded. To facilitate comparison the profiles have been recorded in a standard format. Because of the breadth of the undertaking some data fields do not apply to the establishment under discussion and accordingly are blank. The set of nuclear facility profiles occupies four volumes; the profiles are ordered by country name, and then by facility code. Each nuclear facility profile volume contains two complete indexes to the information. The first index aggregates the facilities alphabetically by country. It is further organized by category of facility, and then by the four-character facility code. It provides a quick summary of the nuclear energy capability or interest in each country and also an identifier, the facility code, which can be used to access the information contained in the profile.

  17. Volume reduction technology development for solid wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Oh, Won Zin; Lee, Kune Woo; Song, Kee Chan; Choi, Wang Kyu; Kim, Young Min

    1998-07-01

    A great deal of solid wastes, which have various physical, chemical, and radiological characteristics, are generated from the nuclear fuel cycle facility as well as radioactive gaseous and liquid wastes. The treatment of the large quantity of solid wastes from the nuclear fuel cycle have great technical, economical and social effects on the domestic policy decision on the nuclear fuel cycle, such as operation and maintenance of the facility, waste disposal, etc. Cement immobilization, super compaction, and electrochemical dissolution were selected as the volume reduction technologies for solid wastes, which will generated from the domestic nuclear fuel cycle facility in the future. And the assessment of annual arisings and the preliminary conceptual design of volume reduction processes were followed. Electrochemical decontamination of α-radionuclides from the spent fuel hulls were experimentally investigated, and showed the successful results. However, β/γ radioactivity did not reduce to the level below which hulls can be classified as the low-level radioactive waste and sent to the disposal site for the shallow land burial. The effects of the various process variables in the electrochemical decontamination were experimentally analysed on the process. (author). 32 refs., 32 tabs., 52 figs

  18. Data base on dose reduction research projects for nuclear power plants: Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    Khan, T.A.; Baum, J.W.

    1989-05-01

    This is the third volume in a series of reports that provide information on dose-reduction research and health physics technology for nuclear power plants. The information is taken from data base maintained by Brookhaven National Laboratory's ALARA Center for the Nuclear Regulatory Commission. This report presents information on 80 new projects, covering a wide area of activities. Projects on steam generator degradation, decontamination, robotics, improvement in reactor materials, and inspection techniques, among others, are described in the research section. The section on health physics technology includes some simple and very cost-effective projects to reduce radiation exposures. Collective dose data from the United States and other countries are also presented. In the conclusion, we suggest that although new advanced reactor design technology will eventually reduce radiation exposures at nuclear power plants to levels below serious concern, in the interim an aggressive approach to dose reduction remains necessary. 20 refs.

  19. Using electrochemical separation to reduce the volume of high-level nuclear waste

    International Nuclear Information System (INIS)

    Slater, S.A.; Gay, E.C.

    1998-01-01

    Argonne National Laboratory (ANL) has developed an electrochemical separation technique called electrorefining that will treat a variety of metallic spent nuclear fuel and reduce the volume of high-level nuclear waste that requires disposal. As part of that effort, ANL has developed a high throughput electrorefiner (HTER) that has a transport rate approximately three times faster than electrorefiners previously developed at ANL. This higher rate is due to the higher electrode surface area, a shorter transport path, and more efficient mixing, which leads to smaller boundary layers about the electrodes. This higher throughput makes electrorefining an attractive option in treating Department of Energy spent nuclear fuels. Experiments have been done to characterize the HTER, and a simulant metallic fuel has been successfully treated. The HTER design and experimental results is discussed

  20. Historical sketches of Sandia National Laboratories nuclear field testing. Volume 1: Full discussion except for sensitive references

    International Nuclear Information System (INIS)

    Banister, J.R.

    1994-10-01

    This report contains historical sketches that cover the major activities of Sandia nuclear field testing, from early atmospheric shots until 1990. It includes a chronological overview followed by more complete discussions of atmospheric, high-altitude, underwater, cratering, and underground nuclear testing. Other activities related to nuclear testing and high-explosive tests are also described. A large number of references are cited for readers who wish to learn more about technical details. Appendices, written by several authors, provide more insight for a variety of special aspects of nuclear testing and related work. Two versions of this history were published: volume 1 has an unlimited distribution, and volume 2 has a limited distribution

  1. Independent Safety Assessment of the TOPAZ-II space nuclear reactor power system (Revised)

    International Nuclear Information System (INIS)

    1993-09-01

    The Independent Safety Assessment described in this study report was performed to assess the safety of the design and launch plans anticipated by the U.S. Department of Defense (DOD) in 1993 for a Russian-built, U.S.-modified, TOPAZ-II space nuclear reactor power system. Its conclusions, and the bases for them, were intended to provide guidance for the U.S. Department of Energy (DOE) management in the event that the DOD requested authorization under section 91b. of the Atomic Energy Act of 1954, as amended, for possession and use (including ground testing and launch) of a nuclear-fueled, modified TOPAZ-II. The scientists and engineers who were engaged to perform this assessment are nationally-known nuclear safety experts in various disciplines. They met with participants in the TOPAZ-II program during the spring and summer of 1993 and produced a report based on their analysis of the proposed TOPAZ-II mission. Their conclusions were confined to the potential impact on public safety and did not include budgetary, reliability, or risk-benefit analyses

  2. WSPEEDI-II system user's manual for a nuclear or radiological emergency

    International Nuclear Information System (INIS)

    Nakanishi, Chika; Sato, Sohei; Muto, Shigeo; Furuno, Akiko; Terada, Hiroaki; Nagai, Haruyasu

    2011-03-01

    Nuclear Emergency Assistance and Training Center (NEAT) has developed the response system to evaluate the radiological consequences of an accident on a nuclear power plant or nuclear weapons testing around Japan and to support prediction of radioactive material distributions by using an atmospheric dispersion model on the framework of the Response Assistance Network (RANET) which is established by the International Atomic Energy Agency (IAEA). For the enhancement of assistance capability to external organizations at a nuclear or radiological emergency, NEAT will introduce a computer-based emergency response system, 'Worldwide version of System for Prediction of Environmental Emergency Dose Information: WSPEEDI 2nd version (WSPEEDI-II)' developed by Division of Environmental and Radiation Sciences. This manual covers the overview of the system and configuration parameters as the basic knowledge needed for operating the systems. (author)

  3. Stereological estimation of nuclear volume in benign and malignant melanocytic lesions of the skin. Inter- and intraobserver variability of malignancy grading

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Ottosen, P D

    1991-01-01

    The volume-weighted, mean nuclear volume (nuclear vv) may be estimated without any assumptions regarding nuclear shape using modern stereological techniques. As a part of an investigation concerning the prospects of nuclear vv for classification and malignancy grading of cutaneous melanocytic tum...

  4. 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

  5. Prototypical spent nuclear nuclear fuel rod consolidation equipment, Phase 2: Final design report: Volume 2, Appendices: Part 1

    International Nuclear Information System (INIS)

    Ciez, A.P.

    1987-01-01

    The purpose of this specification is to establish functional and design requirements for the Prototypical Spent Nuclear Fuel Rod Consolidation System. The Department of Energy-Idaho Operations Office (DOE-ID) is responsible for the implementation of the Prototypic Dry Rod Consolidation Demonstration Project. This program is to develop and demonstrate a fully qualified, licensable, cost-effective, dry spent fuel rod consolidation system by July 1989. The work is divided into four phases as follows: Phase I--Preliminary Design, Phase II--Final Design Option, Phase III--Fabrication and System Checkout Option, and Phase IV--Installation and Hot Demonstration Option. This specification is part of the Phase II effort. The objectives of this specification are to provide functional and design requirements for the Prototypical Spent Nuclear Fuel Rod Consolidation equipment; establish specific tool and subsystem requirements such that the integrated and overall system requirements are satisfied; and establish positioning, envelope and size interface control requirements for each tool or subsystem such that the individual components will interface properly with the overall system design

  6. Nuclear desalination in the Arab world - Part II: Advanced inherent and passive safe nuclear reactors

    International Nuclear Information System (INIS)

    Karameldin, A.; Samer S. Mekhemar

    2004-01-01

    Rapid increases in population levels have led to greater demands for fresh water and electricity in the Arab World. Different types of energies are needed to contribute to bridging the gap between increased demand and production. Increased levels of safeguards in nuclear power plants have became reliable due to their large operational experience, which now exceeds 11,000 years of operation. Thus, the nuclear power industry should be attracting greater attention. World electricity production from nuclear power has risen from 1.7% in 1970 to 17%-20% today. This ratio had increased in June 2002 to reach more than 30%, 33% and 42% in Europe, Japan, and South Korea respectively. In the Arab World, both the public acceptance and economic viability of nuclear power as a major source of energy are greatly dependent on the achievement of a high level of safety and environmental protection. An assessment of the recent generation of advanced reactor safety criteria requirements has been carried out. The promising reactor designs adapted for the Arab world and other similar developing countries are those that profit from the enhanced and passive safety features of the new generation of reactors, with a stronger focus on the effective use of intrinsic characteristics, simplified plant design, and easy construction, operation and maintenance. In addition, selected advanced reactors with a full spectrum from small to large capacities, and from evolutionary to radical types, which have inherent and passive safety features, are discussed. The relevant economic assessment of these reactors adapted for water/electricity cogeneration have been carried out and compared with non-nuclear desalination methods. This assessment indicates that, water/electricity cogeneration by the nuclear method with advanced inherent and passive safe nuclear power plants, is viable and competitive. (author)

  7. Field Operations and Enforcement Manual for Air Pollution Control. Volume II: Control Technology and General Source Inspection.

    Science.gov (United States)

    Weisburd, Melvin I.

    The Field Operations and Enforcement Manual for Air Pollution Control, Volume II, explains in detail the following: technology of source control, modification of operations, particulate control equipment, sulfur dioxide removal systems for power plants, and control equipment for gases and vapors; inspection procedures for general sources, fuel…

  8. IGF-II transgenic mice display increased aberrant colon crypt multiplicity and tumor volume after 1,2-dimethylhydrazine treatment

    Directory of Open Access Journals (Sweden)

    Oesterle Doris

    2006-01-01

    Full Text Available Abstract In colorectal cancer insulin-like growth factor II (IGF-II is frequently overexpressed. To evaluate, whether IGF-II affects different stages of tumorigenesis, we induced neoplastic alterations in the colon of wild-type and IGF-II transgenic mice using 1,2-dimethylhydrazine (DMH. Aberrant crypt foci (ACF served as markers of early lesions in the colonic mucosa, whereas adenomas and carcinomas characterized the endpoints of tumor development. DMH-treatment led initially to significantly more ACF in IGF-II transgenic than in wild-type mice. This increase in ACF was especially prominent for those consisting of ≥three aberrant crypts (AC. Nevertheless, adenomas and adenocarcinomas of the colon, present after 34 weeks in both genetic groups, were not found at different frequency. Tumor volumes, however, were significantly higher in IGF-II transgenic mice and correlated with serum IGF-II levels. Immunohistochemical staining for markers of proliferation and apoptosis revealed increased cell proliferation rates in tumors of IGF-II transgenic mice without significant affection of apoptosis. Increased proliferation was accompanied by elevated localization of β-catenin in the cytosol and cell nuclei and reduced appearance at the inner plasma membrane. In conclusion, we provide evidence that IGF-II, via activation of the β-catenin signaling cascade, promotes growth of ACF and tumors without affecting tumor numbers.

  9. Human Reliability analysis for digitized nuclear power plants: Case study on the LingAo II nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Zou, Yan Hua; Zhang, Li [Institute of Human Factors Engineering AND Safety Management, Hunan Institute of Technology, Hengyang (China); Dai, Cao; Li, Peng Cheng; Qing, Tao [Human Factors Institute, University of South China, Hengyang (China)

    2017-03-15

    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.

  10. 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.

  11. Persistent type II endoleak after EVAR: the predictive value of the AAA thrombus volume.

    Science.gov (United States)

    Gallitto, Enrico; Gargiulo, Mauro; Mascoli, Chiara; Freyrie, Antonio; DE Matteis, Massimo; Serra, Carla; Bianchini Massoni, Claudio; Faggioli, Gianluca; Stella, Andrea

    2018-02-01

    Persistent type II endoleaks (ELIIp, ≥6 months) after an endovascular aneurysm repair (EVAR) can be associated with adverse outcomes. The aims of this study are the evaluation of the incidence of ELIIp, their preoperative morphological predictive features (PMF) and the post-EVAR abdominal aortic aneurysm (AAA) evolution in the presence of ELIIp. Patients underwent EVAR between 2008 and 2010 were prospectively collected. Cases with ELIIp (group A: AG) were identified. A control group without ELIIp (group B: BG), homogeneous for clinical characteristics, follow-up timing and methods (CTA and/or CEUS at 6.12 months and yearly thereafter) was retrospectively selected. The PMF evaluated by computed-tomography-angiography (CTA) were: AAA-diameter, number and diameter of AAA efferent patent vessels (EPV), AAA-total volume (TV), AAA-thrombus volume (THV) and TV/THV rate (%VR). Volumes were calculated by the dedicated vessels analysis software. AG and BG were compared. The primary endpoint was to evaluate the incidence of ELIIp. Secondary endpoints were to analyze the relation between PMF and ELIIp and to assess the post-EVAR AAA-evolution in the presence of ELIIp. Between 2008 and 2010, 200 patients underwent EVAR to treat AAA electively. An ELIIp was detected in 35cases (17.5%) (AG). Twenty-seven patients (13.5%) were included in BG. An overall of 62 patients (GA+GB) were analyzed. The mean pre-operative AAA diameter and EPV were 58±11.6 mm and 5.5±1.8 mm, respectively. The mean TV and THV were 187±111.5 cc and 82±75 cc, respectively. The median %VR was 42.3%. ELIIp was correlated to EPV≥6 (χ2, p=.015) and %VR AAA growth post-EVAR. ELIIp is a not rare complication and it could require re-interventions. Our data suggest that VEP≥6 or %VT<40% are risk factors for ELIIp. No PMF was able to predict the ELIIp evolution. The relative high rate of re-interventions, could suggest the need of adjunctive/preventing primary procedures in patients at high-risk for ELIIp.

  12. The history of the IEA volume II: major policies and actions

    International Nuclear Information System (INIS)

    Scott, R.

    1995-01-01

    Volume II of the History of the International Energy Agency (IEA) continues the story which began with the Origins and Structure of the Agency in Volume I. After examining the industrial countries'energy policies leading up to the 1973-1974 crisis, the current Volume focuses on the new policies adopted in the IEA during its first twenty years.The first part of this book deals with a section on 'Energy Policy Origins of the 1973-1974 Oil Supply Vulnerability : The Optimistic-Passive Approach to Oil Policy'. The main events and developments leading up to the crisis are briefly outlined together with a short presentation of the policy views and critical conclusions that were made on that situation by some of the most knowledgeable oil specialists of the period. The second part surveys IEA oil security, beginning with the oil Emergency Sharing System. The IAE's long-term policies for reducing its Members'dependence on imported oil are the subject of the third part. In this part is described the development of some of the leading IEA work in the field of energy and the environment, the Agency's far-reaching reviews of Members'policies in this sector and a discussion of the 'free markets' policy and of the IEA Shared Goals of 1993. The fourth part deals with the still longer-term Energy Research and Development in the IEA and is a review of the internal organization of IEA work in the R and D field. The fifth part follows with a discussion of the Oil Market policies and practices of the Agency, where the main and durable goals are 'transparency and information dissemination'. The last part addresses the Agency's policies and actions with respect to Co-operation with Non-Member Countries. Then, it takes up Members'policies and activities in connection with the oil producer and consumer country dialogue of 1976-1977 and outlines its disappointing outcome. (O.L.). 2 figs., 13 tabs

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

    International Nuclear Information System (INIS)

    1980-06-01

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

  14. Lists I and II, nuclear medical diagnostics. As of January 18, 1983

    International Nuclear Information System (INIS)

    1983-01-01

    The information booklet presents the guidelines of the Federal Association of Panel Doctors, concerning the minimum equipment required for nuclear medical diagnostics practices (nuclear medical equipment guidelines), in the amended version of May 18, 1981; it also contains the list I (modern commercially available equipment) and the list II (older types of equipment). The devices specified in these lists are products of firms that are members of the ZVEI, and are in compliance with the guidelines of the Panel Doctors' Association. Combinations of older computer equipment/cameras with up-to-date equipment, also come up to the standards given in the guidelines if specifically mentioned therein. The list of manufacturers gives addresses of the manufacturers of the equipment stated in list I and II. An appendix up-dates the information to the date of October 1, 1986. (orig./HP) [de

  15. 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).

  16. II. congress of Czechoslovak Society of Nuclear Medicine and Radiation Hygiene

    International Nuclear Information System (INIS)

    1986-01-01

    The proceedings contain 165 abstracts of papers covering all areas of the application of nuclear medicine, such as osteology, cardiology, immunology, neurology, oncology, etc. The topics include the examination of the skeleton with radioisotopes, various immunology methods, scintiscanning of body organs, tumor monitoring, radiopharmacology aspects, biological radiation effects, cytogenetic changes following irradiation, and studies of radiation effects on DNA repair. Separate volumes are devoted to education of technicians, processing of radioisotope examination data, radiation protection and decontamination. (M.D.)

  17. Temperature variation on the Mediterranean Sea by the exploitation of the Vandellos II Nuclear Power Plant

    International Nuclear Information System (INIS)

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

    2010-01-01

    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.

  18. Nuclear piping criteria for Advanced Light-Water Reactors, Volume 1--Failure mechanisms and corrective actions

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    This WRC Bulletin concentrates on the major failure mechanisms observed in nuclear power plant piping during the past three decades and on corrective actions taken to minimize or eliminate such failures. These corrective actions are applicable to both replacement piping and the next generation of light-water reactors. This WRC Bulletin was written with the objective of meeting a need for piping criteria in Advanced Light-Water Reactors, but there is application well beyond the LWR industry. This Volume, in particular, is equally applicable to current nuclear power plants, fossil-fueled power plants, and chemical plants including petrochemical. Implementation of the recommendations for mitigation of specific problems should minimize severe failures or cracking and provide substantial economic benefit. This volume uses a case history approach to high-light various failure mechanisms and the corrective actions used to resolve such failures. Particular attention is given to those mechanisms leading to severe piping failures, where severe denotes complete severance, large ''fishmouth'' failures, or long throughwall cracks releasing a minimum of 50 gpm. The major failure mechanisms causing severe failure are erosion-corrosion and vibrational fatigue. Stress corrosion cracking also has been a common problem in nuclear piping systems. In addition thermal fatigue due to mixing-tee and to thermal stratification also is discussed as is microbiologically-induced corrosion. Finally, water hammer, which represents the ultimate in internally-generated dynamic high-energy loads, is discussed

  19. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 2

    International Nuclear Information System (INIS)

    Gillespie, P.A.; Wuschke, D.M.; Guvanasen, V.M.; Mehta, K.K.; McConnell, D.B.; Tamm, J.A.; Lyon, R.B.

    1985-12-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the burial of corrosion-resistant containers of waste in a vault located deep in plutonic rock in the Canadian Shield. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluatin of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have if the concept were implemented. The second assessment was performed in 1984 and is documented in Second Interim Assessment of the Canadian Concept for Nuclear Fuel Waste Disposal - Volumes 1 to 4. This volume, entitled Background, discusses Canadian nuclear fuel wastes and the desirable features of a waste disposal method. It outlines several disposal options being considered by a number of countries, including the option chosen for development and assessment in Canada. The reference disposal systems assumed for the second assessment are described, and the approach used for concept assessment is discussed briefly. 79 refs

  20. Development of methods for measuring materials nuclear characteristics, Phases, I, II, II and IV; Razvijanje metoda merenja nuklearnih karakteristika materijala, I, II, II i VI faza

    Energy Technology Data Exchange (ETDEWEB)

    Maglic, R [Boris Kidric Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)

    1963-04-15

    This report contains the following phases of the project 'measurement of nuclear characteristics of reactor materials': nuclear performances of the neutron chopper; method for measuring total effective cross sections by transmission method on the chopper; review of methods for measuring activation cross sections; measurement of neutron spectra of the RA reactor and measurement of total effective cross section of gold by using the chopper.

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

    International Nuclear Information System (INIS)

    1979-12-01

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

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

    International Nuclear Information System (INIS)

    1979-12-01

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

  3. International Best Practice Basis for Assessing Recovery Operations. Annex II of Technical Volume 5

    International Nuclear Information System (INIS)

    2015-01-01

    This volume seeks to identify lessons learned related to post-accident recovery that may further improve preparedness worldwide. This objective assessment of the recovery programme is made according to international best practice. In the practice and assessment of radiation and nuclear safety, international best practice is a process or technique that is likely to consistently produce superior results. An important principle is that a ‘best’ practice can evolve to become better as improvements are discovered and lessons are learned from past experience. The lessons to be learned from the recovery programme as it unfolds in Japan will feed back into improving international best practice in post-accident recovery worldwide. Best practice is used to maintain quality and is a component of quality management systems and standards, such as ISO 9000. It is generally regarded as being the most efficient and effective way to accomplish desired outcomes. The body of best practice is used as a benchmark and for self assessment

  4. Site characterization report for the basalt waste isolation project. Volume II

    International Nuclear Information System (INIS)

    1982-11-01

    The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 2 contains chapters 6 through 12: geochemistry; surface hydrology; climatology, meteorology, and air quality; environmental, land-use, and socioeconomic characteristics; repository design; waste package; and performance assessment

  5. Site characterization report for the basalt waste isolation project. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-11-01

    The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 2 contains chapters 6 through 12: geochemistry; surface hydrology; climatology, meteorology, and air quality; environmental, land-use, and socioeconomic characteristics; repository design; waste package; and performance assessment.

  6. A Report to Congress on Long-Term Stewardship. Volume II, Site Summaries

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2001-01-01

    During World War II and the Cold War, the Federal government developed and operated a vast network of industrial facilities for the research, production, and testing of nuclear weapons, as well as for other scientific and engineering research. These processes left a legacy of radioactive and chemical waste, environmental contamination, and hazardous facilities and materials at well over a 100 sites in 30 States and one U.S. Territory. Hundreds of thousand of acres of residually contaminated soils, contaminated groundwater, surface water and sediment contamination, and contaminated buildings are present at many sites across the country. These sites range in size from less than one acre, containing only a single facility, to large sites spanning over 100,000 acres with huge uranium enrichment plants and plutonium processing canyons. Since 1989, the U.S. Department of Energy’s (DOE) Environmental Management (EM) program has made significant progress in addressing this environmental legacy. Millions of cubic meters of waste have been removed, stabilized, or disposed of, resulting in significant risk and cost reduction. In addition, DOE began disposing of transuranic (i.e., plutonium-contaminated) waste in the nation’s first deep geologic repository – the Waste Isolation Pilot Plant in New Mexico. DOE is now carrying out its long-term stewardship obligations at dozens of sites, including smaller sites where DOE has completed cleanup work for the entire site and many larger sites where DOE has remediated portions of the site.

  7. Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.10--nuclear technology economy and management modernization sub-volume

    International Nuclear Information System (INIS)

    2014-05-01

    Progress report on nuclear science and technology in China (Vol. 3) includes 18 articles which are communicated on the third national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the tenth one, the content is about nuclear technology economy and management modernization sub-volume

  8. Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.7--nuclear fusion and plasma physics sub-volume

    International Nuclear Information System (INIS)

    2014-05-01

    Progress report on nuclear science and technology in China (Vol. 3) includes 22 articles which are communicated on the third national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the seventh one, the content is about nuclear fusion and plasma physics sub-volume

  9. Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.10--Nuclear Information sub-volume

    International Nuclear Information System (INIS)

    2014-05-01

    Progress report on nuclear science and technology in China (Vol. 3) includes 28 articles which are communicated on the third national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the tenth one, the content is about Nuclear Information sub-volume

  10. Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.9--nuclear technology applied in industry sub-volume

    International Nuclear Information System (INIS)

    2014-05-01

    Progress report on nuclear science and technology in China (Vol. 3) includes 35 articles which are communicated on the third national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the ninth one, the content is about nuclear technology applied in industry sub-volume

  11. Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.8--nuclear agriculture sub-volume

    International Nuclear Information System (INIS)

    2014-05-01

    Progress report on nuclear science and technology in China (Vol. 3) includes 10 articles which are communicated on the third national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the eighth one, the content is about nuclear agriculture sub-volume

  12. Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.3--nuclear power sub-volume (Pt.2)

    International Nuclear Information System (INIS)

    2014-05-01

    Progress report on nuclear science and technology in China (Vol. 3) includes 86 articles which are communicated on the third national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the third one, the content is about nuclear power sub-volume (Pt.2)

  13. Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.4--Nuclear chemistry and radiation chemistry sub-volume

    International Nuclear Information System (INIS)

    2014-05-01

    Progress report on nuclear science and technology in China (Vol. 3) includes 24 articles which are communicated on the third national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the fourth one, the content is about Nuclear chemistry and radiation chemistry sub-volume

  14. The legal regime governing the peaceful uses of nuclear energy. II. International Regulations. Pt.1. Regulations on peaceful uses

    International Nuclear Information System (INIS)

    1979-12-01

    The first volume on atomic energy law published by CNEN reproduced national laws and regulations in that field. This book constitutes part one of the second volume and deals with international nuclear conventions and cooperation as at 30 June 1978. It reproduces the instruments and conventions which set up the international nuclear agencies, recommendations in the field of radiation protection and nuclear safety, the nuclear third party liability conventions, the international instruments concerning technical and scientific cooperation and finally, the bilateral cooperation agreements between Italy and other nations and its agreements with international organizations (NEA) [fr

  15. 14N nuclear quadrupole interaction in Cu(II) doped L-alanine

    International Nuclear Information System (INIS)

    Murgich, J.; Calvo, R.; Oseroff, S.B.; Instituto Venezolano de Investigaciones Cientificas, Caracas. Dept. de Quimica)

    1980-01-01

    The 14 N nuclear quadrupole interaction tensor Psub(N) measured by ENDOR in Cu(II) doped L-alanine is analyzed in terms of the Townes and Daily theory assuming a tetra-hedrally bonded N atom. The results of this analysis are compared with those for the 14 N in pure L-alanine and it is found that the principal directions of the Psub(N) tensor are drastically changed upon metal complexation as a consequence of the higher electron affinity of Cu(II) with respect to C and H. Comparison of the corresponding bond populations in pure and Cu(II) doped L-alanine indicates that the Cu draws 0.11 more electron from the N than the substituted H atom. (orig.)

  16. Complex-wide review of DOE's Low-Level Waste Management ES ampersand H vulnerabilities. Volume II. Final report

    International Nuclear Information System (INIS)

    1996-05-01

    Volume I of this report presents a summary of DOE's complex-wide review of its low-level waste management system, including the assessment scope and methodology, site-specific and complex-wide vulnerabilities, and DOE's conclusions and recommendations. Volume II presents a more detailed discussion of the assessment methodology and evaluation instruments developed by the Assessment Working Group for identifying site-specific vulnerabilities, categorizing and classifying vulnerabilities, and identifying and analyzing complex-wide vulnerabilities. Attachments A and B of this volume contain, respectively, the Site Evaluation Survey and the Vulnerability Assessment Form used in those processes. Volume III contains the site-specific assessment reports for the 36 sites (38 facilities) assessed in the complex-wide review from which the complex-wide vulnerabilities were drawn

  17. Incineration as a radioactive waste volume reduction process for CEA nuclear centers

    International Nuclear Information System (INIS)

    Atabek, R.; Chaudon, L.

    1994-01-01

    Incineration processes represent a promising solution for waste volume reduction, and will be increasingly used in the future. The features and performance specifications of low-level waste incinerators with capacities ranging from 10 to 20 kg - h -1 at the Fontenay-aux-Roses, Grenoble and Cadarache nuclear centers in France are briefly reviewed. More extensive knowledge of low-level wastes produced in facilities operated by the Commissariat a l'Energie Atomique (CEA) has allowed us to assess the volume reduction obtained by processing combustible waste in existing incinerators. Research and development work is in progress to improve management procedures for higher-level waste and to build facilities capable of incinerating α - contaminated waste. (authors). 6 refs., 5 figs., 1 tab

  18. International Nuclear Model. Volume 3. Program description. Appendix A-H (Part 1)

    International Nuclear Information System (INIS)

    Andress, D.

    1985-01-01

    The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decisions for reactor deployment and fuel management decisions based on an input set of technical, economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. This volume contains appendices A through H including a description of subroutines and the Fortran listing of the program

  19. The NJOY Nuclear Data Processing System: Volume 3, The GROUPR, GAMINR, and MODER modules

    International Nuclear Information System (INIS)

    MacFarlane, R.E.; Muir, D.W.

    1987-10-01

    The NJOY Nuclear Data Processing System is a comprehensive computer code package for producing pointwise and multigroup cross sections and related quantities from ENDF/B-IV, V, or VI evaluated nuclear data. A concise description of the code system and references to the ancestors of NJOY are given in Vol. 1 of this report. This volume describes the GROUPR module, which produces multigroup neutron interaction cross sections and group-to-group production cross sections for neutrons and photons; the GAMINR module, which produces multigroup photon-interaction cross sections and group-to-group matrices; and the MODER module, which converts ENDF/B and NJOY interface files back and forth between formatted (i.e., BCD, ASCII) and binary modes and performs several associated editing functions. 34 refs., 13 figs

  20. Sandia National Laboratories/New Mexico Facilities and Safety Information Document [NOTE: Volume II, Chapter 12

    International Nuclear Information System (INIS)

    March, F.; Guerrero, J.V.; Johns, W.H.; Schetnan, R.; Bayliss, L.S.; Kuzio, K.A.

    1999-01-01

    Operations in Tech Area IV commenced in 1980 with the construction of Buildings 980 and 981 and the Electron Beam Fusion Accelerator, which at the time was a major facility in SNL's Inertial Confinement Fusion Program. The Electron Beam Fusion Accelerator was a third-generation fusion accelerator that followed Proto I and Proto II, which were operated in Tech Area V. Another accelerator, the Particle Beam Fusion Accelerator I, was constructed in Tech Area IV because there was not enough room in Tech Area V, a highly restricted area that contains SNL's reactor facilities. In the early 1980s, more fusion-related facilities were constructed in Tech Area IV. Building 983 was built to house a fourth-generation fusion accelerator, the Particle Beam Fusion Accelerator II, now called Z Machine, and Buildings 960 and 961 were built to house office space, electrical and mechanical laboratories, and highbay space for pulsed power research and development. In the mid 1980s, Building 970 was constructed to house the Simulation Technology Laboratory. The main facility in the Simulation Technology Laboratory is the High-Energy Radiation Megavolt Electron Source (HERMES) III, a third-generation gamma ray accelerator that is used primarily for the simulation of gamma rays produced by nuclear weapons. The previous generations, HERMES I and HERMES II, had been located in Tech Area V. In the late 1980s, Proto II was moved from Tech Area V to the Simulation Technology Laboratory and modified to function as an x-ray simulation accelerator, and construction of Buildings 962 and 963 began. These buildings comprised the Strategic Defense Facility, which was initially intended to support the nation's Strategic Defense Initiative or ''Star Wars'' program. It was to house a variety of pulsed power-related facilities to conduct research in such areas as directed-energy weapons (electron beams, lasers, and microwaves) and an earth-to-orbit launcher. With the reduction of the Strategic Defense

  1. Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety.

  2. Data base on dose reduction research projects for nuclear power plants. Volume 5

    Energy Technology Data Exchange (ETDEWEB)

    Khan, T.A.; Yu, C.K.; Roecklein, A.K. [Brookhaven National Lab., Upton, NY (United States)

    1994-05-01

    This is the fifth volume in a series of reports that provide information on dose reduction research and health physics technology or nuclear power plants. The information is taken from two of several databases maintained by Brookhaven National Laboratory`s ALARA Center for the Nuclear Regulatory Commission. The research section of the report covers dose reduction projects that are in the experimental or developmental phase. It includes topics such as steam generator degradation, decontamination, robotics, improvements in reactor materials, and inspection techniques. The section on health physics technology discusses dose reduction efforts that are in place or in the process of being implemented at nuclear power plants. A total of 105 new or updated projects are described. All project abstracts from this report are available to nuclear industry professionals with access to a fax machine through the ACEFAX system or a computer with a modem and the proper communications software through the ACE system. Detailed descriptions of how to access all the databases electronically are in the appendices of the report.

  3. Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

  4. Review of Department of Defense Education Activity (DODEA) Schools. Volume II: Quantitative Analysis of Educational Quality

    National Research Council Canada - National Science Library

    Anderson, Lowell

    2000-01-01

    This volume compiles, and presents in integrated form, IDA's quantitative analysis of educational quality provided by DoD's dependent schools, It covers the quantitative aspects of volume I in greater...

  5. Optimisation of the link volume for weakest link failure prediction in NBG-18 nuclear graphite

    International Nuclear Information System (INIS)

    Hindley, Michael P.; Groenwold, Albert A.; Blaine, Deborah C.; Becker, Thorsten H.

    2014-01-01

    This paper describes the process for approximating the optimal size of a link volume required for weakest link failure calculation in nuclear graphite, with NBG-18 used as an example. As part of the failure methodology, the link volume is defined in terms of two grouping criteria. The first criterion is a factor of the maximum grain size and the second criterion is a function of an equivalent stress limit. A methodology for approximating these grouping criteria is presented. The failure methodology employs finite element analysis (FEA) in order to predict the failure load, at 50% probability of failure. The average experimental failure load, as determined for 26 test geometries, is used to evaluate the accuracy of the weakest link failure calculations. The influence of the two grouping criteria on the failure load prediction is evaluated by defining an error in prediction across all test cases. Mathematical optimisation is used to find the minimum error across a range of test case failure predictions. This minimum error is shown to deliver the most accurate failure prediction across a whole range of components, although some test cases in the range predict conservative failure load. The mathematical optimisation objective function is penalised to account for non-conservative prediction of the failure load for any test case. The optimisation is repeated and a link volume found for conservative failure prediction. The failure prediction for each test case is evaluated, in detail, for the proposed link volumes. Based on the analysis, link design volumes for NBG-18 are recommended for either accurate or conservative failure prediction

  6. Stereological estimates of nuclear volume in normal germ cells and carcinoma in situ of the human testis

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Müller, J

    1990-01-01

    Carcinoma in situ of the testis may appear many years prior to the development of an invasive tumour. Using point-sampled intercepts, base-line data concerning unbiased stereological estimates of the volume-weighted mean nuclear volume (nuclear vV) were obtained in 50 retrospective serial...... testicular biopsies from 10 patients with carcinoma in situ. All but two patients eventually developed an invasive growth. Testicular biopsies from 10 normal adult individuals and five prepubertal boys were included as controls. Nuclear vV in testicular carcinoma in situ was significantly larger than...... that of morphologically normal spermatogonia (2P = 1.0 x 10(-19)), with only minor overlap. Normal spermatogonia from controls had, on average, smaller nuclear vV than morphologically normal spermatogonia in biopsies with ipsi- or contra-lateral carcinoma in situ (2P = 5.2 x 10(-3)). No difference in nuclear vV was found...

  7. Nuclear waste calorimeter for very large drums with 385 litres sample volume

    Energy Technology Data Exchange (ETDEWEB)

    Jossens, G.; Mathonat, C. [SETARAM Instrumentation, Caluire (France); Bachelet, F. [CEA Valduc, Is sur Tille (France)

    2015-03-15

    Calorimetry is a very precise and well adapted tool for the classification of drums containing nuclear waste material depending on their level of activities (low, medium, high). A new calorimeter has been developed by SETARAM Instrumentation and the CEA Valduc in France. This new calorimeter is designed for drums having a volume bigger than 100 liters. It guarantees high operator safety by optimizing drum handling and air circulation for cooling, and optimized software for direct measurement of the quantity of nuclear material. The LVC1380 calorimeter makes it possible to work over the range 10 to 3000 mW, which corresponds to approximately 0.03 to 10 g of tritium or 3 to 955 g of {sup 241}Pu in a volume up to 385 liters. This calorimeter is based on the heat flow measurement using Peltier elements which surround the drum in the 3 dimensions and therefore measure all the heat coming from the radioactive stuff whatever its position inside the drum. Calorimeter's insulating layers constitute a thermal barrier designed to filter disturbances until they represent less than 0.001 Celsius degrees and to eliminate long term disturbances associated, for example, with laboratory temperature variations between day and night. A calibration device based on Joule effect has also been designed. Measurement time has been optimized but remains long compared with other methods of measurement such as gamma spectrometry but its main asset is to have a good accuracy for low level activities.

  8. Geoscience data base handbook for modeling a nuclear waste repository. Volume 1

    International Nuclear Information System (INIS)

    Isherwood, D.

    1979-12-01

    This handbook contains reference information on parameters that should be considered in analyzing or modeling a proposed nuclear waste repository site. Only those parameters and values that best represent the natural environment are included. Rare extremes are avoided. Where laboratory and field data are inadequate, theoretical treatments and informed engineering judgements are presented. Volume 1 contains a data base on salt as a repository medium. Chapters on the geology of bedded and dome salt, the geomechanics of salt, hydrology, geochemistry, natural and man-made features, and seismology provide compiled data and related information useful for studying a proposed repository in salt. These and other data will be needed to derive generic deep geologic modeling parameters and will also serve as background for the verification of source data that may be presented in licensing applications for nuclear waste repositories. Volume 2 is the result of a scoping study for a data base on the geology, geomechanics, and hydrology of shale, granite, and basalt as alternative repository media. Except for the geomechanics of shale, most of the sections contain relatively complete compilations of the available data, as well as discussions of the properties that are unique to each rock type

  9. Methods for volume reduction and recycling of LLW arising from decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Krause, G.; Bergstroem, L.

    2003-01-01

    Radioactive contaminated waste is a great cost factor for nuclear power plants and other nuclear industry. On the deregulated electricity market the price of produced kWh is an important competition tool. Therefore many power producers in the process to achieve savings and hence low production costs have given waste minimization and volume reduction highest priority. Studsvik RadWaste AB in Nykoeping, Sweden, is successfully providing incineration and scrap metal treatment services for customers from Europe, Japan and the USA. Since 1987 thousands of tonnes of metal have been released for unrestricted re-use and recycling in commercial steel industry. The incineration service, provided since 1976, results in 97% volume reduction and generates biologically inert ash suitable for disposal in a final radioactive waste repository. Both processes, which are quality and environmentally certified, reduce the cost of interim storage and disposal. In addition, the companies within the Studsvik Group offer a wide range of services such as transportation, measurement and safeguard, site assistance, industrial cleaning and decontamination in connection with demolition on site. (authors)

  10. Data base on dose reduction research projects for nuclear power plants. Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    Khan, T.A.; Vulin, D.S.; Liang, H.; Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

    1992-08-01

    This is the fourth volume in a series of reports that provide information on dose reduction research and health physics technology for nuclear power plants. The information is taken from a data base maintained by Brookhaven National Laboratory`s ALARA Center for the Nuclear Regulatory Commission. This report presents information on 118 new or updated projects, covering a wide range of activities. Projects including steam generator degradation, decontamination, robotics, improvement in reactor materials, and inspection techniques, among others, are described in the research section of the report. The section on health physics technology includes some simple and very cost-effective projects to reduce radiation exposures. Included in this volume is a detailed description of how to access the BNL data bases which store this information. All project abstracts from this report, as well as many other useful documents, can be accessed, with permission, through our on-line system, ACE. A computer equipped with a modem, or a fax machine is all that is required to connect to ACE. Many features of ACE, including software, hardware, and communications specifics, are explained in this report.

  11. Base excision repair efficiency and mechanism in nuclear extracts are influenced by the ratio between volume of nuclear extraction buffer and nuclei—Implications for comparative studies

    International Nuclear Information System (INIS)

    Akbari, Mansour; Krokan, Hans E.

    2012-01-01

    Highlights: • We examine effect of volume of extraction buffer relative to volume of isolated nuclei on repair activity of nuclear extract. • Base excision repair activity of nuclear extracts prepared from the same batch and number of nuclei varies inversely with the volume of nuclear extraction buffer. • Effect of the volume of extraction buffer on BER activity of nuclear extracts can only be partially reversed after concentration of the more diluted extract by ultrafiltration. - Abstract: The base excision repair (BER) pathway corrects many different DNA base lesions and is important for genomic stability. The mechanism of BER cannot easily be investigated in intact cells and therefore in vitro methods that reflect the in vivo processes are in high demand. Reconstitution of BER using purified proteins essentially mirror properties of the proteins used, and does not necessarily reflect the mechanism as it occurs in the cell. Nuclear extracts from cultured cells have the capacity to carry out complete BER and can give important information on the mechanism. Furthermore, candidate proteins in extracts can be inhibited or depleted in a controlled way, making defined extracts an important source for mechanistic studies. The major drawback is that there is no standardized method of preparing nuclear extract for BER studies, and it does not appear to be a topic given much attention. Here we have examined BER activity of nuclear cell extracts from HeLa cells, using as substrate a circular DNA molecule with either uracil or an AP-site in a defined position. We show that BER activity of nuclear extracts from the same batch of cells varies inversely with the volume of nuclear extraction buffer relative to nuclei volume, in spite of identical protein concentrations in the BER assay mixture. Surprisingly, the uracil–DNA glycosylase activity (mainly UNG2), but not amount of UNG2, also correlated negatively with the volume of extraction buffer. These studies demonstrate

  12. COMURHEX II, a 610 million euro investment to meet tomorrow's nuclear power needs

    International Nuclear Information System (INIS)

    2007-01-01

    The worldwide development of nuclear power will lead to increasing demands for uranium. To meet its customers' growing requirements, AREVA has chosen to invest in COMURHEX II to renew and modernize its industrial conversion tool. An entirely new plant is to be built on the Tricastin site to the north of the existing COMURHEX plant. The plant, together with other large-scale investment projects such as the future Georges Besse II enrichment plant - also located on the Tricastin site - and the modernization of the FBFC fuel fabrication facilities in the south of France, will enable AREVA to strengthen its position as a long-standing and fully integrated player at the Front End of the nuclear fuel cycle. These major investments confirm the group's strong commitment to the global development of nuclear power. Converting uranium ore into uranium hexafluoride (UF 6 ) is a key stage before the enrichment and fabrication of nuclear fuel. AREVA is gearing up for market changes, increasing its uranium production from 15,000 tons per year to 21,000 tons per year to match market needs. Today the conversion units of the different industrial operators are showing their age. They will need replacing in the medium term to increase production capacity and keep abreast of the economic, regulatory and environmental conditions of tomorrow's market. Its euros 610 million investment in the Narbonne and Pierrelatte sites in southern France will make AREVA the first uranium converter to overhaul its industrial tool. Thus indicating the group's intention of remaining world leader in UF 6 conversion. The COMURHEX II project will involve the modernization and upgrading of our installations on the basis of tried-and-tested processes and techniques, while incorporating technological innovations that will improve the production performance, reinforce nuclear safety in the facilities, while further reducing the environmental impact of their activities. The first industrial production on the

  13. Survey II of public and leadership attitudes toward nuclear power development in the United States

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    In August 1975, Ebasco Services Incorporated released results of a survey conducted by Louis Harris and Associates, Inc. to determine attitudes of the American public and its leaders toward nuclear power development in the U.S. Results showed, among other things, that the public favored building nuclear power plants; that they believed we have an energy shortage that will not go away soon; that they were not willing to make environmental sacrifices; and that, while favoring nuclear power development, they also had concerns about some aspects of nuclear power. Except for the environmental group, the leadership group felt the same way the public does. A follow-up survey was made in July 1976 to measure any shifts in attitudes. Survey II showed that one of the real worries that remains with the American public is the shortage of energy; additionally, the public and the leaders are concerned about the U.S. dependence on imported oil. With exception of the environmentalists, the public and its leaders support a host of measures to build energy sources, including: solar and oil shale development; speeding up the Alaskan pipeline; speeding up off-shore drilling; and building nuclear power plants. The public continues to be unwilling to sacrifice the environment. There is less conviction on the part of the public that electric power will be in short supply over the next decade. The public believes the days of heavy dependence on oil or hydroelectric power are coming to an end. By a margin of 3 to 1, the public favors building more nuclear power plants in the U.S., but some concerns about the risks have not dissipated. Even though the public is worried about radioactivity escaping into the atmosphere, they consider nuclear power generation more safe than unsafe

  14. The research on corrosion condition and anticorrosion methods of SEP system pipelines in Qinshan Nuclear Power Plant Phase II

    International Nuclear Information System (INIS)

    Zhang Wei; Cao Feng; Wang Jianjun

    2010-01-01

    SEP system in Qinshan nuclear power plant phase II provides drinking water and firefight water for nuclear island, conventional island, inner and outer of BOP structures. Many corrosion perforations in the SEP pipeline were found during operation. This article analysis the corrosion reasons and presents some reasonable treatment and surveillance methods. (authors)

  15. Improving motor reliability in nuclear power plants: Volume 1, Performance evaluation and maintenance practices

    International Nuclear Information System (INIS)

    Subudhi, M.; Gunther, W.E.; Taylor, J.H.; Sugarman, A.C.; Sheets, M.W.

    1987-11-01

    This report constitutes the first of the three volumes under this NUREG. The report presents recommendations for developing a cost-effective program for performance evaluation and maintenance of electric motors in nuclear power plants. These recommendations are based on current industry practices, available techniques for monitoring degradation in motor components, manufacturer's recommendations, operating experience, and results from two laboratory tests on aged motors. Two laboratory test reports on a small and a large motor are presented in separate volumes of this NUREG. These provide the basis for the various functional indicators recommended for maintenance programs in this report. The overall preventive maintenance program is separated into two broad areas of activity aimed at mitigating the potential effects of equipment aging: Performance Evaluation and Equipment Maintenance. The latter involves actually maintaining the condition of the equipment while the former involves those activities undertaken to monitor degradation due to aging. These monitoring methods are further categorized into periodic testing, surveillance testing, continuous monitoring and inspections. This study focuses on the methods and procedures for performing the above activities to maintain the motors operationally ready in a nuclear facility. This includes an assessment of various functional indicators to determine their suitability for trending to monitor motor component condition. The intrusiveness of test methods and the present state-of-the-art for using the test equipment in a plant environment are discussed. In conclusion, implementation of the information provided in this report, will improve motor reliability in nuclear power plants. The study indicates the kinds of tests to conduct, how and when to conduct them, and to which motors the tests should be applied. 44 refs., 12 figs., 13 tabs

  16. Nitric oxide, prostaglandins and angiotensin II in the regulation of renal medullary blood flow during volume expansion.

    Science.gov (United States)

    Moreno, Carol; Llinás, María T; Rodriguez, Francisca; Moreno, Juan M; Salazar, F Javier

    2016-03-01

    Regulation of medullary blood flow (MBF) is essential in maintaining renal function and blood pressure. However, it is unknown whether outer MBF (OMBF) and papillary blood flow (PBF) are regulated independently when extracellular volume (ECV) is enhanced. The aim of this study was to determine whether OMBF and PBF are differently regulated and whether there is an interaction between nitric oxide (NO), prostaglandins (PGs) and angiotensin II (Ang II) in regulating OMBF and PBF when ECV is enhanced. To achieve these goals, OMBF and PBF were measured by laser-Doppler in volume-expanded rats treated with a cyclooxygenase inhibitor (meclofenamate, 3 mg/kg) and/or a NO synthesis inhibitor (L-nitro-arginine methyl ester (L-NAME), 3 μg/kg/min) and/or Ang II (10 ng/kg/min). OMBF was unchanged by NO or PGs synthesis inhibition but decreased by 36 % (P blood flows to the outer medulla and renal papilla are differently regulated and showing that there is a complex interaction between NO, PGs and Ang II in regulating OMBF and PBF when ECV is enhanced.

  17. Best-practices guidelines for L2PSA development and applications. Volume 2 - Best practices for the Gen II PWR, Gen II BWR L2PSAs. Extension to Gen III reactors

    International Nuclear Information System (INIS)

    Raimond, E.; Durin, T.; Rahni, N.; Meignen, R.; Cranga, M.; Pichereau, F.; Bentaib, A.; Guigueno, Y.; Loeffler, H.; Mildenberger, O.; Lajtha, G.; Santamaria, C.S.; Dienstbier, J.; Rydl, A.; Holmberg, J.E.; Lindholm, I.; Maennistoe, I.; Pauli, E.M.; Dirksen, G.; Grindon, L.; Peers, K.; Hulqvist, G.; Parozzi, F.; Polidoro, F.; Cazzoli, E.; Vitazkova, J.; Burgazzi, L.; Oury, L.; Ngatchou, C.; Siltanen, S.; Niemela, I.; Routamo, T.; Helstroem, P.; Bassi, C.; Brinkman, H.; Seidel, A.; Schubert, B.; Wohlstein, R.; Guentay, S.; Vincon, L.

    2010-01-01

    The objective of this coordinated action was to develop best practice guidelines for the performance of Level 2 PSA methodologies with a view of harmonisation at EU level and to allow meaningful and practical uncertainty evaluations in a Level 2 PSA. Specific relationships with community in charge of nuclear reactor safety (utilities, safety authorities, vendors, and research or services companies) have been established in order to define the current needs in terms of guidelines for level 2 PSA development and applications. An international workshop was organised in Hamburg, with the support of VATTENFALL, in November 2008. The level 2 PSA experts from the ASAMPSA2 project partners have proposed some guidelines for the development and application of L2PSA based on their experience and on information available from international cooperation (EC Severe Accident network of Excellence - SARNET, IAEA standards, OECD-NEA publications and workshop) or open literature. The number of technical issues addressed in the guideline is very large and all are not covered with the same relevancy in the first version of the guideline. This version is submitted for external review in November 2010 by severe accident experts and PSA, especially, from SARNET and OECD-NEA members. The feedback of the external review will be dis cussed during an international open works hop planned in March 2011 and all outcomes will be taken into consideration in the final version of this guideline (June 2011). The guideline includes 3 volumes: - Volume 1 - General considerations on L2PSA. - Volume 2 - Technical recommendations for Gen II and III reactors. - Volume 3 - Specific considerations for future reactor (Gen IV). The recommendations formulated in the guideline should not be considered as 'mandatory' but should help the L2PSA developers to achieve high quality studies with limited time and resources. It may also help the L2PSA reviewers by positioning one specific study in comparison with some

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

    International Nuclear Information System (INIS)

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

    1966-03-01

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

  19. Potential safety enhancements to nuclear plant control: proof testing at EBR-II

    International Nuclear Information System (INIS)

    Lindsay, R.W.; Chisholm, G.H.

    1984-01-01

    Future changes in nuclear plant control and protective systems will reflect an evolutionary improvement through increased use of computers coupled with a better integration of man and machine. Before improvements can be accepted into the licensed commercial plant environment, significant testing must be accomplished to answer safety questions and to prove the worth of new ideas. The Experimental Breeder Reactor-II (EBR-II) is being used as a test-bed for both in-house development and testing for others in a DOE sponsored Man-Machine Integration program. The ultimate result of the development and testing would be a control system for which safety credit could be taken in the licensing process

  20. 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 ...

  1. The modernization of the nuclear power plants of Asco and Vandellos II

    International Nuclear Information System (INIS)

    Martinez Anton, L.

    2011-01-01

    Since the beginning of their commercial operation, the nuclear power plants of Asco and Vandellos have made design modifications aimed at improving the safety, reliability and operation of the plants. From the moment the management of the three plants was brought together within the Association Nuclear Asco-Vandellos II, and within the assets management process, joint strategic modernisation and improvement plans have been developed on the basis of the status of equipment, the evaluation of their ageing, obsolesce, degradations, manufacturers recommendations and/or the application of new regulations. The article lists the mos important actions already carried out or in the project phase for the 3 plants in the primary and secondary system, electrical and instrumentation systems and auxiliary systems, highlighting the problems and the solutions adopted in the most relevant modifications. (Author)

  2. Study and application of ANISN and DOT-II nuclear cores in reactor physics problems

    International Nuclear Information System (INIS)

    Dias, Artur Flavio

    1980-01-01

    To solve time-independent neutrons and/or gamma rays transport problems in nuclear reactors, two codes available at IPEN were studied and applied to solve benchmark problems. The ANISN code solves the one-dimensional Boltzmann transport equation for neutrons or gamma rays, in plane, spherical, or cylindrical geometries. The DOT-II code solves the same equation in two-dimensional space for plane, cylindrical and circular geometries. General anisotropic scattering allowed in both codes. Moreover, pointwise convergence criteria, and alternate step function difference equations are also used in order to remove the oscillating flux distributions, sometimes found in discrete ordinates solutions. Basic theories and numerical techniques used in these codes are studied and summarized. Benchmark problems have been solved using these codes. Comparisons of the results show that both codes can be used with confidence in the analysis of nuclear problems. (author)

  3. Concept and structure of instrumentation and control of the Atucha II nuclear power plant

    International Nuclear Information System (INIS)

    Garzon, D.; Roca, J.L.

    1987-01-01

    The general structure of instrumentation and control of Atucha II nuclear power plant as well as the technologies used, are described: concepts of functional decentralization and physical centralization; concept of functional group and functional complex; description of the technologies used (physical support) in the project of plant instrumentation and control; description of the different automation levels on the basis of concepts of control interface, automatism, regulation, group and subgroup controls; principles of signal conditioning; concept of announcement of alarms and state: supervisory computer, description of HAS (Hard wired Alarm System) and CAS (Computer Alarm System); application of the above mentioned structure to the project of another type of plants. (Author)

  4. Volume fraction prediction in biphasic flow using nuclear technique and artificial neural network

    Energy Technology Data Exchange (ETDEWEB)

    Salgado, Cesar M.; Brandao, Luis E.B., E-mail: otero@ien.gov.br, E-mail: brandao@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    The volume fraction is one of the most important parameters used to characterize air-liquid two-phase flows. It is a physical value to determine other parameters, such as the phase's densities and to determine the flow rate of each phase. These parameters are important to predict the flow pattern and to determine a mathematical model for the system. To study, for example, heat transfer and pressure drop. This work presents a methodology for volume fractions prediction in water-gas stratified flow regime using the nuclear technique and artificial intelligence. The volume fractions calculate in biphasic flow systems is complex and the analysis by means of analytical equations becomes very difficult. The approach is based on gamma-ray pulse height distributions pattern recognition by means of the artificial neural network. The detection system uses appropriate broad beam geometry, comprised of a ({sup 137}Cs) energy gamma-ray source and a NaI(Tl) scintillation detector in order measure transmitted beam whose the counts rates are influenced by the phases composition. These distributions are directly used by the network without any parameterization of the measured signal. The ideal and static theoretical models for stratified regime have been developed using MCNP-X code, which was used to provide training, test and validation data for the network. The detector also was modeled with this code and the results were compared to experimental photopeak efficiency measurements of radiation sources. The proposed network could obtain with satisfactory prediction of the volume fraction in water-gas system, demonstrating to be a promising approach for this purpose. (author)

  5. Volume fraction prediction in biphasic flow using nuclear technique and artificial neural network

    International Nuclear Information System (INIS)

    Salgado, Cesar M.; Brandao, Luis E.B.

    2015-01-01

    The volume fraction is one of the most important parameters used to characterize air-liquid two-phase flows. It is a physical value to determine other parameters, such as the phase's densities and to determine the flow rate of each phase. These parameters are important to predict the flow pattern and to determine a mathematical model for the system. To study, for example, heat transfer and pressure drop. This work presents a methodology for volume fractions prediction in water-gas stratified flow regime using the nuclear technique and artificial intelligence. The volume fractions calculate in biphasic flow systems is complex and the analysis by means of analytical equations becomes very difficult. The approach is based on gamma-ray pulse height distributions pattern recognition by means of the artificial neural network. The detection system uses appropriate broad beam geometry, comprised of a ( 137 Cs) energy gamma-ray source and a NaI(Tl) scintillation detector in order measure transmitted beam whose the counts rates are influenced by the phases composition. These distributions are directly used by the network without any parameterization of the measured signal. The ideal and static theoretical models for stratified regime have been developed using MCNP-X code, which was used to provide training, test and validation data for the network. The detector also was modeled with this code and the results were compared to experimental photopeak efficiency measurements of radiation sources. The proposed network could obtain with satisfactory prediction of the volume fraction in water-gas system, demonstrating to be a promising approach for this purpose. (author)

  6. Long-term consequences of and prospects for recovery from nuclear war: Two views. View II

    International Nuclear Information System (INIS)

    Anspaugh, L.R.

    1986-01-01

    The author comments on the information presented in this volume and speculates on the long-term consequences of nuclear war and the prospects for recovery. In order to do that, it might be useful to define long term. To him this means time frames of years to perhaps even hundreds of years in terms of the ultimate response and recovery of large-scale ecosystems. Such long time frames may seem excessive, but if some of the speculated efforts of nuclear war are actually realized, it may indeed take centuries before native ecosystems restabilize. Also, when referring to long-term effects of the magnitude required to have a major impact on entire ecosystems, it is clear that the driving force would not be the direct effects of nuclear war. Of potentially greater significance would be the secondary effects mediated by the intermediate-term impacts on global climate. Specifically, he refers to the speculative impacts of major decreases in the heat and light fluxes reaching the Earth's surface. Such changes are commonly referred to as ''nuclear winter.''

  7. Shock Isolation Elements Testing for High Input Loadings. Volume II. Foam Shock Isolation Elements.

    Science.gov (United States)

    SHOCK ABSORBERS ), (*GUIDED MISSILE SILOS, SHOCK ABSORBERS ), (*EXPANDED PLASTICS, (*SHOCK(MECHANICS), REDUCTION), TEST METHODS, SHOCK WAVES, STRAIN(MECHANICS), LOADS(FORCES), MATHEMATICAL MODELS, NUCLEAR EXPLOSIONS, HARDENING.

  8. Feedback to Managers, Volume II: A Review and Comparison of Sixteen Multi-Rater Feedback Instruments.

    Science.gov (United States)

    Van Velsor, Ellen; Leslie, Jean Brittain

    "Feedback to Managers" is a two-volume report. Volume 2 compares 16 of the better feedback instruments available. The following are the instruments: (1) ACUMEN Group Feedback; (2) BENCHMARKS; (3) the Campbell Leadership Index; (4) COMPASS: the Managerial Practices Survey; (5) the Executive Success Profile; (6) Leader Behavior Analysis…

  9. Pressure fluctuation analysis for charging pump of chemical and volume control system of nuclear power plant

    Directory of Open Access Journals (Sweden)

    Chen Qiang

    2016-01-01

    Full Text Available Equipment Failure Root Cause Analysis (ERCA methodology is employed in this paper to investigate the root cause for charging pump’s pressure fluctuation of chemical and volume control system (RCV in pressurized water reactor (PWR nuclear power plant. RCA project task group has been set up at the beginning of the analysis process. The possible failure modes are listed according to the characteristics of charging pump’s actual pressure fluctuation and maintenance experience during the analysis process. And the failure modes are analysed in proper sequence by the evidence-collecting. It suggests that the gradually untightened and loosed shaft nut in service should be the root cause. And corresponding corrective actions are put forward in details.

  10. Partial volume effect correction in nuclear medicine: assessment with a mathematical phantom

    International Nuclear Information System (INIS)

    Silva, Murilo Collete da; Pozzo, Lorena

    2009-01-01

    Objective: assessment of Van Cittert partial volume effect correction method in nuclear medicine images, with a mathematical phantom. Material and method: we simulated an image of four circular sources of different diameters and intensity of 255 per pixel. The iterative algorithm was applied with 20 iterations and α = 1. We obtained the maximum and average counts on the entire image and in regions of interest placed on each of the sources. We also extracted count profiles plotted along the diameter of each of the sources. Results: the local convergence depends on the size of the source studied: the smaller the source, the greater the number of iterations required. It also depends on the information extracted: the use of average counts provides more homogeneous results than the maximum count. There is a significant improvement in image contrast. Conclusion: this study showed the possibility of qualitative and quantitative improvement in applying the bidimensional iterative Van Cittert method to images of simple geometry. (author)

  11. Exxon nuclear power distribution control for pressurized water reactors: Phase II

    International Nuclear Information System (INIS)

    Holm, J.S.; Burnside, R.J.

    1978-01-01

    The power distribution control procedure, denoted PDC-II, described in this report enables nuclear plants to manage core power distributions such that Technical Specification Limits on F/sub Q//sup T/ are not violated during normal operation and limits on MDNBR are not violated during steady-state, load-follow, and anticipated transients. The PDC-II data base described provides the means for predicting the maximum F/sub Q//sup T/(z) distribution anticipated during operation under the PDC-II procedure taking into account the incore measured equilibrium power distribution data for the reactor in question. A comparison of this distribution with the Technical Specification limit curve determines whether the Technical Specification limit can be protected by PDC-II procedure. If such protection can be confirmed for a given operating cycle interval, APDMS monitoring is not necessary over this interval and the excore monitored constant axial offset limits will protect the Technical Specification F/sub Q//sup T/ limits. This document describes the maximum possible variation in F/sub Q//sup T/(z) which can occur during operation when following the PDC-II procedures. This bounding variation in F/sub Q//sup T/(z) is referred to as V(z). This V(z) distribution represents the maximun variation in F/sub Q//sup T/(z) when the axial offset is maintained within the range defined in this report [+- 5% at full power condition

  12. Compact sodium cooled nuclear power plant with fast core (KNK II- Karlsruhe), Safety Report

    International Nuclear Information System (INIS)

    1977-09-01

    After the operation of the KNK plant with a thermal core (KNK I), the installation of a fast core (KNK II) had been realized. The planning of the core and the necessary reconstruction work was done by INTERATOM. Owner and customer was the Nuclear Research Center Karlsruhe (KfK), while the operating company was the Kernkraftwerk-Betriebsgesellschaft mbH (KBG) Karlsruhe. The main goals of the KNK II project and its special experimental test program were to gather experience for the construction, the licensing and operation of future larger plants, to develop and to test fuel and absorber assemblies and to further develop the sodium technology and the associated components. The present safety report consists of three parts. Part 1 contains the description of the nuclear plant. Hereby, the reactor and its components, the handling facilities, the instrumentation with the plant protection, the design of the plant including the reactor core and the nominal operation processes are described. Part 2 contains the safety related investigation and measures. This concerns the reactivity accidents, local cooling perturbations, radiological consequences with the surveillance measures and the justification of the choice of structural materials. Part three finally is the appendix with the figures, showing the different buildings, the reactor and its components, the heat transfer systems and the different auxiliary facilities [de

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

    Science.gov (United States)

    Fallows, Scott M.

    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. These results, like any others, are subject to a variety of systematic effects that may alter their final interpretations. A primary focus of this dissertation will be difficulties in precisely calibrating the energy scale for nuclear recoil events like those from WIMPs. Nuclear recoils have suppressed ionization signals relative to electron recoils of the same recoil energy, so the response of the detectors is calibrated differently for each recoil type. The overall normalization and linearity of the energy scale for electron recoils in CDMS~II detectors is clearly established by peaks of known gamma energy in the ionization spectrum of calibration data from a 133Ba source. This electron-equivalent keVee) energy scale enables calibration of the total phonon signal (keVt) by enforcing unity

  14. High Power Compact Single-Frequency Volume Bragg Er-Doped Fiber Laser, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — This proposal is based on successful results of Phase I project where it was shown that the use of volume Bragg gratings in PTR glass as selectors of transverse and...

  15. Proceedings of the 1984 workshop on high-energy excitations in condensed matter. Volume II

    International Nuclear Information System (INIS)

    Silver, R.N.

    1984-12-01

    This volume covers electronic excitations, momentum distributions, high energy photons, and a wrap-up session. Abstracts of individual items from the conference were prepared separately for the data base

  16. Elmo Bumpy Torus proof of principle, Phase II: Title 1 report. Volume VII. Cryogenic system

    International Nuclear Information System (INIS)

    Poteat, T.J.

    1982-01-01

    This document, Volume VII EBT-P Cryogenic System Title I Design Report, describes the system that resulted from the Title I Preliminary Design effort. It is a self-contained document that can be read apart from the other Volumes comprising the EBT-P Title I Report. This document is a contract deliverable item and provides the detail necessary to support the Cryogenic System design contained in the EBT-P Baseline Design Data Book

  17. CNS proceedings of the 16. annual conference, volume I and II

    International Nuclear Information System (INIS)

    Wight, A.L.; Loewer, R.

    1995-01-01

    The proceedings of the 16. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 82 papers are arranged in 16 sessions dealing with the following subjects: thermalhydraulics, containment, control and instrumentation, reactor physics, fuel channels, engineering and maintenance, safety and licensing, severe accidents and probabilistic safety assessment, new reactors and applications, radiation, fuel, computers. The individual papers have been abstracted separately

  18. CNS proceedings of the 16. annual conference, volume I and II

    Energy Technology Data Exchange (ETDEWEB)

    Wight, A L; Loewer, R [eds.

    1996-12-31

    The proceedings of the 16. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 82 papers are arranged in 16 sessions dealing with the following subjects: thermalhydraulics, containment, control and instrumentation, reactor physics, fuel channels, engineering and maintenance, safety and licensing, severe accidents and probabilistic safety assessment, new reactors and applications, radiation, fuel, computers. The individual papers have been abstracted separately.

  19. Reports distributed in 1976 under the NRC Light-Water Reactor Safety Technical Exchange. Volume II

    International Nuclear Information System (INIS)

    Sharp, D.S.; Cottrell, W.B.

    1977-01-01

    Lists of documents exchanged in 1976 under agreement between the U.S. Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the governments of France, Federal Republic of Germany, and Japan are presented. In 1976 the NRC received 25 reports from France, 74 from F.R. Germany, and 39 from Japan, and in return sent 119 U.S. reports to France, 154 to F.R. Germany, and 155 to Japan

  20. Stereological estimation of nuclear volume and other quantitative histopathological parameters in the prognostic evaluation of supraglottic laryngeal squamous cell carcinoma

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Bennedbaek, O; Pilgaard, J

    1989-01-01

    The aim of this study was to investigate various approaches to the grading of malignancy in pre-treatment biopsies from patients with supraglottic laryngeal squamous cell carcinoma. The prospects of objective malignancy grading based on stereological estimation of the volume-weighted mean nuclear...... observers of the latter was poor in the material which consisted of 35 biopsy specimens. Unbiased estimates of nuclear Vv were on the average 385 microns3 (CV = 0.44), with more than 90% of the associated variance attributable to differences in nuclear Vv among individual lesions. Nuclear Vv was positively....... None of the investigated categorical and quantitative parameters (cutoff points = means) reached the level of significance with respect to prognostic value. However, nuclear Vv showed the best information concerning survival (2p = 0.08), and this estimator offers optimal features for objective...

  1. GENII (Generation II): The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

    Energy Technology Data Exchange (ETDEWEB)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-09-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs.

  2. GENII [Generation II]: The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

    International Nuclear Information System (INIS)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-09-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs

  3. Radiological aspects of nuclear accident scenarios. Volume 1 real-time emergency response systems post-Chernobyl action

    International Nuclear Information System (INIS)

    Sinnaeve, J.

    1991-01-01

    In the event of a nuclear accident, there is a need for a rapid assessment of the resulting levels of environmental contamination in order to facilitate decisions on possible countermeasures. Volume 1 of this report covers the development of numerical models, in the form of software packages, to simulate atmospheric transport and deposition over various distances, and techniques for estimation of the resulting doses

  4. System of large transport containers for waste from dismantling light water and gas-cooled nuclear reactors. Volume 1

    International Nuclear Information System (INIS)

    Price, M.S.T.; Lafontaine, I.

    1985-01-01

    The purpose of this volume is to introduce the main types of nuclear reactor in the European Community (EC), select reference plants for further study, estimate the waste streams from the reference reactors, survey the transport regulations and assess existing containers

  5. An ancillary method in urine cytology: Nucleolar/nuclear volume ratio for discrimination between benign and malignant urothelial cells.

    Science.gov (United States)

    Tone, Kiyoshi; Kojima, Keiko; Hoshiai, Keita; Kumagai, Naoya; Kijima, Hiroshi; Kurose, Akira

    2016-06-01

    The essential of urine cytology for the diagnosis and the follow-up of urothelial neoplasia has been widely recognized. However, there are some cases in which a definitive diagnosis cannot be made due to difficulty in discriminating between benign and malignant. This study evaluated the practicality of nucleolar/nuclear volume ratio (%) for the discrimination. Using Papanicolaou-stained slides, 253 benign urothelial cells and 282 malignant urothelial cells were selected and divided into a benign urothelial cell and an urothelial carcinoma (UC) cell groups. Three suspicious cases and four cases in which discrimination between benign and malignant was difficult were prepared for verification test. Subject cells were decolorized and stained with 4',6-diamidino-2-phenylindole for detection of the nuclei and the nucleoli. Z-stack method was performed to analyze. When the cutoff point of 1.514% discriminating benign urothelial cells and UC cells from nucleolar/nuclear volume ratio (%) was utilized, the sensitivity was 56.0%, the specificity was 88.5%, the positive predictive value was 84.5%, and the negative predictive value was 64.4%. Nuclear and nucleolar volume, number of the nucleoli, and nucleolar/nuclear volume ratio (%) were significantly higher in the UC cell group than in the benign urothelial cell group (P benign and malignant urothelial cells, providing possible additional information in urine cytology. Diagn. Cytopathol. 2016;44:483-491. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

  6. ICPP calcined solids storage facility closure study. Volume II: Cost estimates, planning schedules, yearly cost flowcharts, and life-cycle cost estimates

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-01

    This document contains Volume II of the Closure Study for the Idaho Chemical Processing Plant Calcined Solids Storage Facility. This volume contains draft information on cost estimates, planning schedules, yearly cost flowcharts, and life-cycle costs for the four options described in Volume I: (1) Risk-Based Clean Closure; NRC Class C fill, (2) Risk-Based Clean Closure; Clean fill, (3) Closure to landfill Standards; NRC Class C fill, and (4) Closure to Landfill Standards; Clean fill.

  7. ICPP calcined solids storage facility closure study. Volume II: Cost estimates, planning schedules, yearly cost flowcharts, and life-cycle cost estimates

    International Nuclear Information System (INIS)

    1998-02-01

    This document contains Volume II of the Closure Study for the Idaho Chemical Processing Plant Calcined Solids Storage Facility. This volume contains draft information on cost estimates, planning schedules, yearly cost flowcharts, and life-cycle costs for the four options described in Volume I: (1) Risk-Based Clean Closure; NRC Class C fill, (2) Risk-Based Clean Closure; Clean fill, (3) Closure to landfill Standards; NRC Class C fill, and (4) Closure to Landfill Standards; Clean fill

  8. SLIM-MAUD: an approach to assessing human error probabilities using structured expert judgment. Volume II. Detailed analysis of the technical issues

    International Nuclear Information System (INIS)

    Embrey, D.E.; Humphreys, P.; Rosa, E.A.; Kirwan, B.; Rea, K.

    1984-07-01

    This two-volume report presents the procedures and analyses performed in developing an approach for structuring expert judgments to estimate human error probabilities. Volume I presents an overview of work performed in developing the approach: SLIM-MAUD (Success Likelihood Index Methodology, implemented through the use of an interactive computer program called MAUD-Multi-Attribute Utility Decomposition). Volume II provides a more detailed analysis of the technical issues underlying the approach

  9. Volume reduction of dry active waste by use of a waste sorting table at the Brunswick nuclear power plant

    International Nuclear Information System (INIS)

    Snead, P.B.

    1988-01-01

    Carolina Power and Light Company's Brunswick nuclear power plant has been using a National Nuclear Corporation Model WST-18 Waste Sorting Table to monitor and sort dry active waste for segregating uncontaminated material as a means of low-level waste volume reduction. The WST-18 features 18 large-area, solid scintillation detectors arranged in a 3 x 6 array underneath a sorting/monitoring surface that is shielded from background radiation. An 11-week study at Brunswick showed that the use of the waste sorting table resulted in dramatic improvements in both productivity (man-hours expended per cubic foot of waste processed) and monitoring quality over the previous hand-probe frisking method. Use of the sorting table since the study has confirmed its effectiveness in volume reduction. The waste sorting table paid for its operation in volume reduction savings alone, without accounting for the additional savings from recovering reusable items

  10. Design data and safety features of commercial nuclear power plants including cumulative index for Volumes I--VI

    International Nuclear Information System (INIS)

    Heddleson, F.A.

    1977-01-01

    Design data, safety features, and site characteristics are summarized for 12 nuclear power units in 6 power stations in the United States. Six pages of data are presented for each station, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. In addition, an aerial perspective is presented for each plant. This volume covers plants with docket numbers 50-553 through 50-569 (Phipps Bend, Black Fox, Yellow Creek, and NEP) and two earlier plants not previously reported--Hope Creek (50-354, 50-355) and WPPSS 1 and 4 (50-460, 50-513). Indexes for this volume and the five earlier volumes are presented in three forms--by docket number, by plant name, and by participating utility

  11. Generation IV nuclear energy systems: road map and concepts. 2. Generation II Measurement Systems for Generation IV Nuclear Power Plants

    International Nuclear Information System (INIS)

    Miller, Don W.

    2001-01-01

    need for substantial research. As we consider I and C systems in Generation IV reactors, we have the opportunity to take a much less 'timid' design philosophy than was taken in the design of I and C systems in the ALWRs. We need to make use of advanced technology to design an I and C system for the Generation IV multi-unit plant designs currently being considered. Such a design should accomplish the following: 1. provides for multi-unit control; 2. contributes to a plant design objective of a very low core damage frequency; 3. maximizes plant thermal efficiency (>50%); 4. maximizes plant capacity factor (>90%); 5. optimizes operability; 6. maximizes maintainability; 7. provides for on-line monitoring, calibration, and diagnostics; 8. provides optimum response to disturbances; 9. provides excellent load-following capability. When we consider the current situation in operating Generation I and II nuclear power plants and even Generation III ALWR design, we conclude that Generation IV reactors should employ at least Generation II measurement systems. Let us first consider data transmission, which is a form of communication, and ask the question: Do new communication-transferring methods by electrons flow in copper wires? The obvious answer is no. Virtually all new communication systems are using some electromagnetic method, such as light, microwaves, HF or VHF radio signals, and virtually no copper wires. When we envision Generation IV nuclear power plants, we should minimize the use of copper wires for data transmission. We should transmit data primarily by fiber optics and various wireless methods, some of which can penetrate thick barriers. Now let us consider sensors. If we use light for data transmission, then we should also use optical-based sensors. We should also take advantage of microprocessors, which provide opportunities to embed 'intelligence' in the sensor that can be used to increase accuracy, stability, and tolerance to external stressors (i.e., radiation

  12. Molecular characterization of a nuclear topoisomerase II from Nicotiana tabacum that functionally complements a temperature-sensitive topoisomerase II yeast mutant.

    Science.gov (United States)

    Singh, B N; Mudgil, Yashwanti; Sopory, S K; Reddy, M K

    2003-07-01

    We have successfully expressed enzymatically active plant topoisomerase II in Escherichia coli for the first time, which has enabled its biochemical characterization. Using a PCR-based strategy, we obtained a full-length cDNA and the corresponding genomic clone of tobacco topoisomerase II. The genomic clone has 18 exons interrupted by 17 introns. Most of the 5' and 3' splice junctions follow the typical canonical consensus dinucleotide sequence GU-AG present in other plant introns. The position of introns and phasing with respect to primary amino acid sequence in tobacco TopII and Arabidopsis TopII are highly conserved, suggesting that the two genes are evolved from the common ancestral type II topoisomerase gene. The cDNA encodes a polypeptide of 1482 amino acids. The primary amino acid sequence shows a striking sequence similarity, preserving all the structural domains that are conserved among eukaryotic type II topoisomerases in an identical spatial order. We have expressed the full-length polypeptide in E. coli and purified the recombinant protein to homogeneity. The full-length polypeptide relaxed supercoiled DNA and decatenated the catenated DNA in a Mg(2+)- and ATP-dependent manner, and this activity was inhibited by 4'-(9-acridinylamino)-3'-methoxymethanesulfonanilide (m-AMSA). The immunofluorescence and confocal microscopic studies, with antibodies developed against the N-terminal region of tobacco recombinant topoisomerase II, established the nuclear localization of topoisomerase II in tobacco BY2 cells. The regulated expression of tobacco topoisomerase II gene under the GAL1 promoter functionally complemented a temperature-sensitive TopII(ts) yeast mutant.

  13. Survey of fish impingement at power plants in the United States. Volume II. Inland waters

    International Nuclear Information System (INIS)

    Freeman, R.F. III; Sharma, R.K.

    1977-03-01

    Impingement of fish at cooling-water intakes of 33 power plants located on inland waters other than the Great Lakes has been surveyed and data are presented. Descriptions of site, plant, and intake design and operation are provided. Reports in this volume summarize impingement data for individual plants in tabular and histogram formats. Information was available from differing sources such as the utilities themselves, public documents, regulatory agencies, and others. Thus, the extent of detail in the reports varies greatly from plant to plant. Histogram preparation involved an extrapolation procedure that has inadequacies. The reader is cautioned in the use of information presented in this volume to determine intake-design acceptability or intensity of impacts on ecosystems. No conclusions are presented herein; data comparisons are made in Volume IV

  14. Stereological estimates of nuclear volume and other quantitative variables in supratentorial brain tumors. Practical technique and use in prognostic evaluation

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Braendgaard, H; Chistiansen, A O

    1991-01-01

    The use of morphometry and modern stereology in malignancy grading of brain tumors is only poorly investigated. The aim of this study was to present these quantitative methods. A retrospective feasibility study of 46 patients with supratentorial brain tumors was carried out to demonstrate...... the practical technique. The continuous variables were correlated with the subjective, qualitative WHO classification of brain tumors, and the prognostic value of the parameters was assessed. Well differentiated astrocytomas (n = 14) had smaller estimates of the volume-weighted mean nuclear volume and mean...... nuclear profile area, than those of anaplastic astrocytomas (n = 13) (2p = 3.1.10(-3) and 2p = 4.8.10(-3), respectively). No differences were seen between the latter type of tumor and glioblastomas (n = 19). The nuclear index was of the same magnitude in all three tumor types, whereas the mitotic index...

  15. Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository--Volume 2: Methodology and Results

    International Nuclear Information System (INIS)

    Taylor, L.L.; Wilson, J.R.; Sanchez, L.C.; Aguilar, R.; Trellue, H.R.; Cochrane, K.; Rath, J.S.

    1998-01-01

    The US Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3)

  16. Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository--Volume 2: Methodology and Results

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, L.L.; Wilson, J.R.; Sanchez, L.C.; Aguilar, R.; Trellue, H.R.; Cochrane, K.; Rath, J.S.

    1998-10-01

    The US Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3).

  17. Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository--Volume 1: Executive Summary

    International Nuclear Information System (INIS)

    Taylor, L.L.; Wilson, J.R.; Sanchez, L.Z.; Aguilar, R.; Trellue, H.R.; Cochrane, K.; Rath, J.S.

    1998-01-01

    The US Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3)

  18. Experience gathered from the transport of a fuel element prototype of the CNA-II (Atucha-II nuclear power plant) type

    International Nuclear Information System (INIS)

    Pastorini, A.; Belinco, C.G.; El Bis, E.D.; Sacchi, M.A.; Mayans, C.O.; Martin Ghiselli, A.; Marcora, G.R.

    1990-01-01

    This work describes the needs to materialize the transport of a fuel element prototype of the CNA-II (Atucha-II nuclear power plant) type, under special conditions, from the Fabrication Pilot Plant sited at the Constituyentes Atomic Center and the Ezeiza Atomic Center, for its subsequent analysis at the High Pressure Experimental Loop. The special conditions under which the transport has been made responded to the fact that the prototype presents a fragile adjustment between rods and separators, necessary to be preserved. (Author) [es

  19. Estudos sobre a regeneração do figado - variação do volume nuclear das celulas hepáticas em repouso divisional

    Directory of Open Access Journals (Sweden)

    Fernando Ubatuba

    1948-12-01

    Full Text Available Surgical removal of large amounts of hepatic tissue in male albino rats results in a rapid and conspicuous raise in cellular nuclear volumes. Measurements were made exclusively in resting nuclei. This volume variation is transitory. Nuclear volumes return to the normal value withins 6 days of restoration. The higher value are abserved 48 hours after the hepatic removal, indicating probably that this effect is due to hydration of the nucei, as occurs in the cytoplasm. This hydration could be correlated to the mitotic activity of the renmant tissue since a peak of mitoses parallels the changes in the nuclear volumes.

  20. Licensing assessment of the Candu Pressurized Heavy Water Reactor. Preliminary safety information document. Volume II

    International Nuclear Information System (INIS)

    1977-06-01

    ERDA has requested United Engineers and Constructors (UE and C) to evaluate the design of the Canadian natural uranium fueled, heavy water moderated (CANDU) nuclear reactor power plant to assess its conformance with the licensing criteria and guidelines of the U.S. Nuclear Regulatory Commission (USNRC) for light water reactors. This assessment was used to identify cost significant items of nonconformance and to provide a basis for developing a detailed cost estimate for a 1140 MWe, 3-loop Pressurized Heavy Water Reactor (PHWR) located at the Middletown, USA Site

  1. Occupational dose reduction at nuclear power plants: Annotated bibliography of selected readings in radiation protection and ALARA. Volume 8

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, S.G.; Khan, T.A.; Xie, J.W. [Brookhaven National Lab., Upton, NY (United States)

    1995-05-01

    The ALARA Center at Brookhaven National Laboratory publishes a series of bibliographies of selected readings in radiation protection and ALARA in a continuing effort to collect and disseminate information on radiation dose reduction at nuclear power plants. This volume 8 of the series. The abstracts in this bibliography were selected form proceedings of technical meetings and conference journals, research reports, and searches of the Energy Science and Technology database of the US Department of Energy. The subject material of these abstracts relates to the many aspects of radiation protection and dose reduction, and ranges form use of robotics, to operational health physics, to water chemistry. Material on the design, planning, and management of nuclear power stations is included, as well as information on decommissioning and safe storage efforts. Volume 8 contains 232 abstracts, an author index, and a subject index. The author index is specific for this volume. The subject index is cumulative and lists all abstract numbers from volumes 1 to 8. The numbers in boldface indicate the abstracts in this volume; the numbers not in boldface represent abstracts in previous volumes.

  2. Occupational dose reduction at nuclear power plants: Annotated bibliography of selected readings in radiation protection and ALARA. Volume 7

    Energy Technology Data Exchange (ETDEWEB)

    Kaurin, D.G.; Khan, T.A.; Sullivan, S.G.; Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

    1993-07-01

    The ALARA Center at Brookhaven National Laboratory publishes a series of bibliographies of selected readings in radiation protection and ALARA in the continuing effort to collect and disseminate information on radiation dose reduction at nuclear power plants. This is volume 7 of the series. The abstracts in this bibliography were selected from proceedings of technical meetings and conferences, journals, research reports, and searches of the Energy Science and Technology database of the US Department of Energy. The subject material of these abstracts relates to radiation protection and dose reduction, and ranges from use of robotics to operational health physics, to water chemistry. Material on the design, planning, and management of nuclear power stations is included, as well as information on decommissioning and safe storage efforts. Volume 7 contains 293 abstract, an author index, and a subject index. The author index is specific for this volume. The subject index is cumulative and lists all abstract numbers from volumes 1 to 7. The numbers in boldface indicate the abstracts in this volume; the numbers not in boldface represent abstracts in previous volumes.

  3. Occupational dose reduction at nuclear power plants: Annotated bibliography of selected readings in radiation protection and ALARA. Volume 8

    International Nuclear Information System (INIS)

    Sullivan, S.G.; Khan, T.A.; Xie, J.W.

    1995-05-01

    The ALARA Center at Brookhaven National Laboratory publishes a series of bibliographies of selected readings in radiation protection and ALARA in a continuing effort to collect and disseminate information on radiation dose reduction at nuclear power plants. This volume 8 of the series. The abstracts in this bibliography were selected form proceedings of technical meetings and conference journals, research reports, and searches of the Energy Science and Technology database of the US Department of Energy. The subject material of these abstracts relates to the many aspects of radiation protection and dose reduction, and ranges form use of robotics, to operational health physics, to water chemistry. Material on the design, planning, and management of nuclear power stations is included, as well as information on decommissioning and safe storage efforts. Volume 8 contains 232 abstracts, an author index, and a subject index. The author index is specific for this volume. The subject index is cumulative and lists all abstract numbers from volumes 1 to 8. The numbers in boldface indicate the abstracts in this volume; the numbers not in boldface represent abstracts in previous volumes

  4. Hyperfine structure in the Gd II spectrum and the nuclear electric quadrupole moment of 157Gd

    International Nuclear Information System (INIS)

    Clieves, H.P.; Steudel, A.

    1979-01-01

    The hyperfine structure of 157 Gd was investigated in 20 Gd II lines by means of a photoelectric recording Fabry-Perot interferometer with digital data processing. The hyperfine splitting factors, A and B, were obtained by computer fits to the observed line structures. Using a multiconfigurational set of wave functions in intermediate coupling derived by Wyart, mono-electronic parameters were deduced by a parametric treatment. The nuclear electric quadrupole moment of 157 Gd was evaluated from the quadrupole interaction of the 5d electron in 4f 7 5d6s, the 5d electron in 4f 7 5d6p, and the 6p electron in 4f 7 5d6p. The three values obtained for the quadrupole moment agree very well. The final result, corrected for Sternheimer shielding, is Q( 157 Gd) = 1.34(7) x 10 -24 cm 2 . (orig.) [de

  5. KNK II, Compact Sodium-Cooled Reactor in the Nuclear Research Center Karlsruhe

    International Nuclear Information System (INIS)

    1978-01-01

    The report gives an overview of the project of the sodium-cooled fast reactor KNK II in the nuclear research center KfK in Karlsruhe. This test reactor was the preparatory stage of the prototype plant SNR 300 and had several goals: to train operating personal, to practice the licensing procedures in Germany, to get experience with the sodium technology and to serve as a test bed for fast breeder core components. The report contains contributions of KfK as the owner and project managing organization, of INTERATOM as the design and construction company and of the KBG as the plant operating organization. Experience with and results of relevant aspects of the project are tackled: project management, reactor core and component design, safety questions and licensing, plant design and test programs [de

  6. Handbook of Game Theory and Industrial Organization, Volume II: Applications. An Introduction

    OpenAIRE

    Corchon, Luis; Marini, Marco A.

    2017-01-01

    We introduce here the second volume of the Handbook of Game Theory and Industrial Organization, by L. C. Corchón and M. A. Marini (ed.), Edward Elgar, Cheltenam, UK and Northampton, MA, describing its main aim and its basic structure.

  7. Developing maintainability for tokamak fusion power systems. Phase I report. Volume II. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Zahn, H.S.

    1977-10-01

    This volume contains the following appendices: (1) baseline large module time estimates, (2) baseline intermediate module time estimates, (3) baseline small module time estimates, (4) alternate concept estimates, (5) maintenance equipment concepts, (6) additional reactor design definition, and (7) TOCOMO supplements. (MOW)

  8. Influence of pressure on the properties of chromatographic columns. II. The column hold-up volume.

    Science.gov (United States)

    Gritti, Fabrice; Martin, Michel; Guiochon, Georges

    2005-04-08

    The effect of the local pressure and of the average column pressure on the hold-up column volume was investigated between 1 and 400 bar, from a theoretical and an experimental point of view. Calculations based upon the elasticity of the solids involved (column wall and packing material) and the compressibility of the liquid phase show that the increase of the column hold-up volume with increasing pressure that is observed is correlated with (in order of decreasing importance): (1) the compressibility of the mobile phase (+1 to 5%); (2) in RPLC, the compressibility of the C18-bonded layer on the surface of the silica (+0.5 to 1%); and (3) the expansion of the column tube (columns packed with the pure Resolve silica (0% carbon), the derivatized Resolve-C18 (10% carbon) and the Symmetry-C18 (20% carbon) adsorbents, using water, methanol, or n-pentane as the mobile phase. These solvents have different compressibilities. However, 1% of the relative increase of the column hold-up volume that was observed when the pressure was raised is not accounted for by the compressibilities of either the solvent or the C18-bonded phase. It is due to the influence of the pressure on the retention behavior of thiourea, the compound used as tracer to measure the hold-up volume.

  9. Ocean Thermal Energy Conversion (OTEC) platform configuration and integration. Volume II. Conceptual design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-06-01

    The purpose of this project is to evaluate six candidate hullforms as candidates for the OTEC commercial plant. This volume is a summary of the conceptual design including facility requirements, cost, schedule, and site sensitivity. Two OTEC commercial plant configurations are considered in this study: the ship and the semi-submersible. Engineering drawings are presented. (WHR)

  10. Technical Assistance in Evaluating Career Education Projects. Final Report. Volume II: Final Career Education Evaluation Report.

    Science.gov (United States)

    Stenner, A. Jackson; And Others

    This document contains the second of five volumes reporting the activities and results of a career education evaluation project conducted to accomplish the following two objectives: (1) to improve the quality of evaluations by career education projects funded by the United States Office of Career Education (OCE) through the provision of technical…

  11. Catalog of physical protection equipment. Book 1: Volume II. Intrusion detection components

    International Nuclear Information System (INIS)

    Haberman, W.

    1977-06-01

    This volume covers acoustic components, microwave/radar components, electro-optic barriers, electric field components, orientation components, ferrous metal detection components, proximity detection components, vibration detection components, seismic components, pressure-sensitive components, pressure mats, continuity components, electrical/magnetic switches, fire detection components, and mechanical contact switches

  12. Savannah River Plant - Project 8980 engineering and design history. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    1957-01-01

    This volume provides an engineering and design history of the 100 area of the Savannah River Plant. This site consisted of five separate production reactor sites, 100-R, P, L, K, and C. The document summarizes work on design of the reactors, support facilities, buildings, siting, etc. for these areas.

  13. Developing maintainability for tokamak fusion power systems. Phase II report. Volume III: appendices

    International Nuclear Information System (INIS)

    Fuller, G.M.; Zahn, H.S.; Mantz, H.C.; Kaletta, G.R.; Waganer, L.M.; Carosella, L.A.; Conlee, J.L.

    1978-11-01

    This volume contains time estimate summaries to the second level of detail for scheduled or unscheduled maintenance of the first wall/blanket, some selected subsystem components and maintenance equipment. Elaboration of selected maintenance equipment functions and performance as well as conceptual designs is also included

  14. Book Review: Sustainable Luxury and Social Entrepreneurship. Volume II: More Stories from the Pioneers

    DEFF Research Database (Denmark)

    Skjold, Else

    2017-01-01

    volume Sustainable Luxury and Social Entrepreneurship: Stories of the Pioneers, published in 2014. The book series, as well as the awards, seeks to investigate and promote the motives, context, and practical endeavours of sustainable entrepreneurs within the premium and luxury sector....

  15. Higher Education and Development in South-East Asia. Volume II, Country Profiles.

    Science.gov (United States)

    Hayden, Howard; And Others

    This document, the second of three volumes concerned with the role of institutions of higher education in the development of countries in South-East Asia, presents country profiles for Burma, Thailand, Laos, Cambodia, Viet-Nam, Malaysia, Singapore, Indonesia, and the Philippines. The profile emphasizes background, higher education, educational…

  16. Dancetime! 500 Years of Social Dance. Volume II: 20th Century. [Videotape].

    Science.gov (United States)

    Teten, Carol

    This 50-minute VHS videotape is the second in a 2-volume series that presents 500 years of social dance, music, and fashion. It features dance and music of the 20th century, including; 1910s: animal dances, castle walk, apache, and tango; 1920s: black bottom and charleston; 1930s: marathon, movie musicals, big apple, and jitterbug; 1940s: rumba;…

  17. SEL/Project Language. Level II, Kindergarten, Volume I (Lessons 1-16).

    Science.gov (United States)

    Valladares, Ann E.; And Others

    The document is an intervention curriculum guide designed to facilitate the initial adjustment of disadvantaged Southeastern children to kindergarten or first grade. The major emphasis is on the teaching of language skills in combination with subject matter learning using a language-experience approach. This volume contains Lessons 1-16 of a…

  18. Inductively coupled plasma emission spectroscopy. Part II: applications and fundamentals. Volume 2

    International Nuclear Information System (INIS)

    Boumans, P.W.J.M.

    1987-01-01

    This is the second part of the two-volume treatise by this well-known and respected author. This volume reviews applications of inductively coupled plasma atomic emission spectroscopy (ICP-AES), summarizes fundamental studies, and compares ICP-AES methods with other methods of analysis. The first six chapters are devoted to specific fields of application, including the following: metals and other industrial materials, geology, the environment, agriculture and food, biology and clinical analysis, and organic materials. The chapter on the analysis of organic materials also covers the special instrumental considerations required when organic solvents are introduced into an inductively coupled plasma. A chapter on the direct analysis of solids completes the first part of this volume. Each of the applications chapters begins with a summary of the types of samples that are encountered in that field, and the kinds of problems that an elemental analysis can help to solve. This is followed by a tutorial approach covering applicability, advantages, and limitations of the methods. The coverage is thorough, including sample handling, storage, and preparation, acid, and fusion dissolution, avoiding contamination, methods of preconcentration, the types of interferences that can be expected and ways to reduce them, and the types of ICP plasmas that are used. The second half of the volume covers fundamental studies of ICP-AES: basic processes of aerosol generation, plasma modeling and computer simulation, spectroscopic diagnostics, excitation mechanisms, and discharge characteristics. This section introduces the experimental and modeling methods that have been used to obtain fundamental information about ICPs

  19. Photo-Geomorphology of Coastal Landforms, Cat Island, Bahamas. Volume II,

    Science.gov (United States)

    The report provides the aerial imagery used in the analysis of the coastal landforms of Cat Island in the east-central Bahama Islands. Interpretive...published volume Coastal Landform of Cat Island, Bahamas: A Study of Holocene Accretionary Topography and Sea-Level Change but may also serve as an

  20. SOLVENT-BASED TO WATERBASED ADHESIVE-COATED SUBSTRATE RETROFIT - VOLUME II: PROCESS OVERVIEW

    Science.gov (United States)

    This volume presents initial results of a study to identify the issues and barriers associated with retrofitting existing solvent-based equipment to accept waterbased adhesives as part of an EPA effort to improve equipment cleaning in the coated and laminated substrate manufactur...

  1. Developing maintainability for tokamak fusion power systems. Phase I report. Volume II. Appendices

    International Nuclear Information System (INIS)

    Zahn, H.S.

    1977-10-01

    This volume contains the following appendices: (1) baseline large module time estimates, (2) baseline intermediate module time estimates, (3) baseline small module time estimates, (4) alternate concept estimates, (5) maintenance equipment concepts, (6) additional reactor design definition, and (7) TOCOMO supplements

  2. A DDC Bibliography on Computers in Information Sciences. Volume II. Information Sciences Series.

    Science.gov (United States)

    Defense Documentation Center, Alexandria, VA.

    The unclassified and unlimited bibliography compiles references dealing specifically with the role of computers in information sciences. The volume contains 239 annotated references grouped under three major headings: Artificial and Programming Languages, Computer Processing of Analog Data, and Computer Processing of Digital Data. The references…

  3. Engineering Drawing Practices - Volume I of II: Aerospace and Ground Support Equipment

    Science.gov (United States)

    Schwindt, Paul A.

    2015-01-01

    This manual establishes the essential requirements and reference documents for the preparation and revision of digital product definition data sets prepared for or by NASA at KSC. This volume is only applicable to KSC in-house programs/projects. These requirements do not apply to the preparation of illustrations, artwork, or figures in technical publications.

  4. Communications Strategies on Alcohol and Highway Safety. Volume II. High School Youth. Final Report.

    Science.gov (United States)

    Grey Advertising, Inc., New York, NY.

    The second part of a two-part, two volume study deals with high school youth and identifies target populations and communications strategies for encouraging personal action steps to prevent drunk driving. Data, collected from interviews and questionnaires, are summarized and presented in tabular form. One fourth of high schoolers in a…

  5. Technical Reports (Part II). End of Project Report, 1968-1971, Volume IV.

    Science.gov (United States)

    Western Nevada Regional Education Center, Lovelock.

    The pamphlets included in this volume are technical reports prepared as outgrowths of the Student Information System of the Western Nevada Regional Education Center funded by a Title III grant under the Elementary and Secondary Education Act of 1965. These reports demonstrate the use of the stored data; methods of interpreting the printouts from…

  6. Systems Book for a Student Information System. End of Project Report, 1968-1971, Volume II.

    Science.gov (United States)

    Western Nevada Regional Education Center, Lovelock.

    The necessary handbooks for use of the Student Information System (SIS), developed and tested by the Western Nevada Regional Education Center under a 1968-71 Title III (Elementary and Secondary Education Act) grant, are presented in this volume. As noted, the purpose of the SIS is to supply data and information to persons or organizations who make…

  7. Industrial Special Wastes Generated in Iowa and Manpower Characteristics of Employee Handlers, Volume II.

    Science.gov (United States)

    Pierce, David R.

    This document, Vol. II in a set, presents the results of the development and instruction of two pilot modules. The first module deals with pesticide container recycling. The second module deals with hazardous substances, especially paints and solvents. Each module contains background information, instructor narrative, student activities, and…

  8. Missouri Journal of Research in Music Education, Volume II, Number 5.

    Science.gov (United States)

    Hilton, Lewis B., Ed.

    1971-01-01

    The six articles presented in this journal are: I. Research in Action: The Transfer of Research in Music and Music Education into the Classroom by Jack R. Stephenson; II. Programmed Instruction and Music Education by Douglas L. Turpin; III. Music Education and the Blind by Joan Thief Gagnepain; IV. Improved Teaching Through the Use of the…

  9. TIBER II/ETR final design report: Volume 1, 1. 0 Introduction; 2. 0 plasma engineering

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J.D. (ed.)

    1987-09-01

    This paper discusses the design of the TIBER II tokamak test reactor. Specific topics discussed are the physics objectives for Tiber, magnetics, baseline operating point, pulsed inductive operation, edge physics and impurity control, fueling, disruption control, vertical stability and impurity flow reversal. (LSP)

  10. The Experience of Soviet Medicine in World War II 1941-1945. Volume I.

    Science.gov (United States)

    1982-02-25

    countries. The low percentage of neuropsychological patients in the Soviet Army is evidence of the achievements of pre- war years of the Soviet people...unsplinted 269 I I II I fracture did not bother them. To the question of the physician about =npn.aints, they most often pointed out hunger . As early

  11. Use of volume-rendered images in registration of nuclear medicine studies

    International Nuclear Information System (INIS)

    Wallis, J.W.; Miller, T.R.; Hsu, S.S.

    1995-01-01

    A simple operator-guided alignment technique based on volume-rendered images was developed to register tomographic nuclear medicine studies. For each of 2 three-dimensional data sets to be registered, volume-rendered images were generated in 3 orthogonal projections (x,y,z) using the method of maximum-activity projection. Registration was achieved as follows: (a) One of the rendering orientations (e.g. x) was chosen for manipulation; (b) The two dimensional rendering was translated and rotated under operator control to achieve the best alignment as determined by visual assessment; (c) This rotation and translation was then applied to the underlying three-dimensional data set, with updating of the rendered images in each of the orthogonal projections; (d) Another orientation was chosen, and the process repeated. Since manipulation was performed on the small two-dimensional rendered image, feedback was instantaneous. To aid in the visual alignment, difference images and flicker images (toggling between the two data sets) were displayed. Accuracy was assessed by analysis of separate clinical data sets acquired without patient movement. After arbitrary rotation and translation of one of the two data sets, the 2 data sets were registered. Mean registration error was 0.36 pixels, corresponding to a 2.44 mm registration error. Thus, accurate registration can be achieved in under 10 minutes using this simple technique. The accuracy of registration was assessed with use of duplicate SPECT studies originating from separate reconstructions of the data from each of the detectors of a triple-head gamma camera

  12. 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.

  13. Elements from chlorine to calcium nuclear reactions

    CERN Document Server

    Kunz, Wunibald

    1968-01-01

    Nuclear Tables: Part II Nuclear Reactions, Volume 3: The Elements from Chlorine to Calcium contains tabulations of the nuclear reaction values of elements chlorine, argon, potassium, and calcium. These tabulations provide the calculated Q-values of the elements and their isotopes. This book will be of value to general chemistry researchers.

  14. Demonstration, testing, & evaluation of in situ heating of soil. Draft final report, Volume II: Appendices A to E

    Energy Technology Data Exchange (ETDEWEB)

    Dev, H.; Enk, J.; Jones, D.; Saboto, W.

    1996-02-12

    This document is a draft final report for US DOE contract entitled, {open_quotes}Demonstration Testing and Evaluation of In Situ Soil Heating,{close_quotes} Contract No. DE-AC05-93OR22160, IITRI Project No. C06787. This report is presented in two volumes. Volume I contains the technical report This document is Volume II, containing appendices with background information and data. In this project approximately 300 cu. yd. of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. When scaled up, this process can be used for the environmental clean up and restoration of DOE sites contaminated with VOCs and other organic chemicals boiling up to 120{degrees}to 130{degrees}C in the vadose zone. Although it may applied to many types of soil formations, it is particularly attractive for low permeability clayey soil where conventional in situ venting techniques are limited by low air flow.

  15. Demonstration, testing, ampersand evaluation of in situ heating of soil. Draft final report, Volume II: Appendices A to E

    International Nuclear Information System (INIS)

    Dev, H.; Enk, J.; Jones, D.; Saboto, W.

    1996-01-01

    This document is a draft final report for US DOE contract entitled, open-quotes Demonstration Testing and Evaluation of In Situ Soil Heating,close quotes Contract No. DE-AC05-93OR22160, IITRI Project No. C06787. This report is presented in two volumes. Volume I contains the technical report This document is Volume II, containing appendices with background information and data. In this project approximately 300 cu. yd. of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. When scaled up, this process can be used for the environmental clean up and restoration of DOE sites contaminated with VOCs and other organic chemicals boiling up to 120 degrees to 130 degrees C in the vadose zone. Although it may applied to many types of soil formations, it is particularly attractive for low permeability clayey soil where conventional in situ venting techniques are limited by low air flow

  16. Mg II ABSORPTION CHARACTERISTICS OF A VOLUME-LIMITED SAMPLE OF GALAXIES AT z ∼ 0.1

    International Nuclear Information System (INIS)

    Barton, Elizabeth J.; Cooke, Jeff

    2009-01-01

    We present an initial survey of Mg II absorption characteristics in the halos of a carefully constructed, volume-limited subsample of galaxies embedded in the spectroscopic part of the Sloan Digital Sky Survey (SDSS). We observed quasars near sightlines to 20 low-redshift (z ∼ 0.1), luminous (M r + 5log h ≤-20.5) galaxies in SDSS DR4 and DR6 with the LRIS-B spectrograph on the Keck I telescope. The primary systematic criteria for the targeted galaxies are a redshift z ∼> 0.1 and the presence of an appropriate bright background quasar within a projected 75 h -1 kpc of its center, although we preferentially sample galaxies with lower impact parameters and slightly more star formation within this range. Of the observed systems, six exhibit strong (W eq (2796) ≥ 0.3 A) Mg II absorption at the galaxy's redshift, six systems have upper limits which preclude strong Mg II absorption, while the remaining observations rule out very strong (W eq (2796) ≥ 1-2 A) absorption. The absorbers fall at higher impact parameters than many non-absorber sightlines, indicating a covering fraction f c ∼ -1 kpc (f c ∼ 0.25). The data are consistent with a possible dependence of covering fraction and/or absorption halo size on the environment or star-forming properties of the central galaxy.

  17. Enlarged Halden programme group meeting on high burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research. Volume II

    International Nuclear Information System (INIS)

    1999-01-01

    Academy of Sciences, KFKI Atomic Energy Research Institute, the N.V. KEMA, the Netherlands, the Russian Research Centre 'Kurchatov Institute', the Slovakian VUJE - Nuclear Power Plant Research Institute, and from USA: the ABB Combustion Engineering Inc., the Electric Power Research Institute (EPRI), and the General Electric Co. The right to utilise information originating from the research work of the Halden Project is limited to persons and undertakings specifically given this right by one of these Project member organisations. The activities in the area of fuel and materials performance are based on extensive in-reactor measurements. The programmes are expanding in the areas of fuel performance at extended burn-ups, waterside corrosion and material testing in general. Development of in-core instruments is an important activity in support of the experimental programmes. The research programme at the Halden Project addresses the research needs of the nuclear industry in connection with introduction of digital I and C systems in NPPs. The programme provides information supporting design and licensing of upgraded, computer-based control room systems, and demonstrates the benefits of such systems through validation experiments in Halden's experimental research facility, HAMMLAB and pilot installations in NPPs. The Enlarged Halden Programme Group Meeting at Loen, Norway, was arranged to provide an opportunity to present results of work carried out at Halden and within participating organisations, and to encourage comments and impulses related to future Halden Project work. This HPR-351 relates to the fuel and materials part of the meeting and is divided in two volumes, HPR-351 Volume I and HPR-351 Volume II. The corresponding collection of papers in the man-machine area are given in one volume, HPR-352 Volume I. The overall programme of the Loen Enlarged Meeting covering the Fuel and Materials Research is given in the following pages. The papers with denomination HWR have

  18. COOMET.RI(II)-S1.Rn-222 (169/UA/98): Rn-222 volume activity comparison

    International Nuclear Information System (INIS)

    Skliarov, V.; Rottger, A.; Honig, A.; Korostin, S.; Kuznetsov, S.; Lapenas, A.; Milevsky, V.; Ivaniukovich, A.; Kharitonov, I.; Sepman, S.

    2009-01-01

    According to a first program, a supplementary comparison of Rn-222 volume activity was drawn up as a bilateral supplementary comparison between NSC 'Institute of Metrology', Ukraine, and VNIIFTRI, Russia. It took place in March 2005. In April 2005, at the 5. meeting of COOMET held in Braunschweig (Germany), representatives of these institutes exchanged data which showed the comparability of the national standards of Ukraine and Russia for the check points. During the discussion of the procedure some other institutes decided to join the comparison program, which was extended to BelGIM (Belarus), PTB (Germany), VNIIM (Russia) and RMTC (Latvia). The national standards of volume activity of radon-222 were thus calibrated using one standard radon radiometer as the transfer standard. Results are shown in the Final Report of the comparison. (authors)

  19. COOMET.RI(II)-S1.Rn-222 (169/UA/98): Rn-222 volume activity comparison

    Energy Technology Data Exchange (ETDEWEB)

    Skliarov, V. [National Scientific Centre, Institute of Metrology (NSC IM), Kharkiv (Ukraine); Rottger, A.; Honig, A. [Physikalisch-Technische Bundesanstalt (PTB), Braunschweig (Germany); Korostin, S.; Kuznetsov, S. [All-Russian Scientific Research Institute of Physical, Technical and Radio Measurements (VNIIFTRI), Moscow Region, Mendeleyevo (Russian Federation); Lapenas, A. [Latvian National Metrology Centre Ltd, Radiation Metrology and Testing Centre (RMTC), Salaspils (Latvia); Milevsky, V.; Ivaniukovich, A. [Belarussian State Institute of Metrology (BelGIM), Minsk (Belarus); Kharitonov, I.; Sepman, S. [D I Mendeleyev Institute of metrology (VNIIM), Saint Petersburg (Russian Federation)

    2009-06-15

    According to a first program, a supplementary comparison of Rn-222 volume activity was drawn up as a bilateral supplementary comparison between NSC 'Institute of Metrology', Ukraine, and VNIIFTRI, Russia. It took place in March 2005. In April 2005, at the 5. meeting of COOMET held in Braunschweig (Germany), representatives of these institutes exchanged data which showed the comparability of the national standards of Ukraine and Russia for the check points. During the discussion of the procedure some other institutes decided to join the comparison program, which was extended to BelGIM (Belarus), PTB (Germany), VNIIM (Russia) and RMTC (Latvia). The national standards of volume activity of radon-222 were thus calibrated using one standard radon radiometer as the transfer standard. Results are shown in the Final Report of the comparison. (authors)

  20. Barnwell Nuclear Fuels Plant applicability study. Volume II. BNFP: utilization alternatives, evaluations, and conclusions

    International Nuclear Information System (INIS)

    1978-04-01

    Descriptions and status of the Barnwell separations facility and related fuel cycle facilities are given. Alternative uses other than reprocessing, evaluation of uses for reprocessing alternatives, resource utilization and its relationship to U.S. security objectives, and evaluation of ownership-management options are discussed