Effluent treatment options for nuclear thermal propulsion system ground tests

International Nuclear Information System (INIS)

Shipers, L.R.; Brockmann, J.E.

1992-01-01

A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the strengths and weaknesses of different methods to handle effluent from nuclear thermal propulsion system ground tests

Ground-water protection activities of the US Nuclear Regulatory Commission

International Nuclear Information System (INIS)

1987-02-01

This report evaluates the internal consistency of NRC's ground-water protection programs. These programs have evolved consistently with growing public concerns about the significance of ground-water contamination and environmental impacts. Early NRC programs provided for protection of the public health and safety by minimizing releases of radionuclides. More recent programs have included provisions for minimizing releases of nonradiological constituents, mitigating environmental impacts, and correcting ground-water contamination. NRC's ground-water protection programs are categorized according to program areas, including nuclear materials and waste management (NMSS), nuclear reactor operation (NRR), confirmatory research and standards development (RES), inspection and enforcement (IE), and agreement state programs (SP). Based on analysis of existing ground-water protection programs within NRC, the interoffice Ground-water Protection Group has identified several inconsistencies between and within program areas. These inconsistencies include: (1) different definitions of the term ''ground-water,'' (2) variable regulation of nonradiological constituents in ground water, (3) different design periods for ground-water protection, and (4) different scopes and rigor of ground-water assessments. The second inconsistency stems from differences in statutory authority granted to the NRC. The third inconsistency is rationalized by recognizing differences in perceived risks associated with nuclear facilities. The Ground-water Protection Group will document its analysis of the remaining inconsistencies and make recommendations to reconcile or eliminate them in a subsequent report

Conceptual Design of On-line Based Licensing Review and Assesment System of Nuclear Installations and Nuclear Materials ('PRIBEN')

International Nuclear Information System (INIS)

Melani, Ai; Chang, Soon Heung

2008-01-01

At the present Indonesia has no nuclear power plant in operation yet, although it is expected that the first nuclear power plant will be operated and commercially available in around the year of 2016 to 2017 in Muria Peninsula. There are only three research reactors, one nuclear fuel fabrication plant for research reactors, and one experimental fuel fabrication plant for nuclear power, one isotope production facility and some other research facilities. All the facility is under Nuclear Energy Regulatory Agency (BAPETEN) controlling through regulation, licensing and inspection. The organizations operation submits licensing application to BAPETEN before utilizing the facility. According to the regulation before BAPETEN give license they perform review and assessment for the utility application. Based on the review and assessment result, BAPETEN may stipulate, reject, delay or terminate the license. In anticipation of expansion of the nuclear program in Indonesia, BAPETEN should have an integrated and updated system for review and asses the licensing application. For this reason, an expert system for the review and asses the licensing application, so-called PRIBEN (Perizinan Reaktor, Instalasi dan Bahan Nuklir/Licensing of Reactor, Nuclear Installations and Nuclear Materials), is developed which runs on the online-based reality environment

Ground assessment methods for nuclear power plant

International Nuclear Information System (INIS)

1985-01-01

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

Nuclear ground state

International Nuclear Information System (INIS)

Negele, J.W.

1975-01-01

The nuclear ground state is surveyed theoretically, and specific suggestions are given on how to critically test the theory experimentally. Detailed results on 208 Pb are discussed, isolating several features of the charge density distributions. Analyses of 208 Pb electron scattering and muonic data are also considered. 14 figures

Lightning discrimination by a ground-based nuclear burst detection system

International Nuclear Information System (INIS)

Thornbrough, A.D.

1978-04-01

Sandia Laboratories is developing for the U.S. Army a Ground-Based Nuclear Burst Detection System to provide pertinent information for its field commanders and higher authorities. The equipment must operate in all kinds of weather and produce very low false alarms under all types of conditions. With these requirements, a study of the effects during thunderstorms, which includes thousands of lightning flashes, was conducted. The results of these studies were that, with suitable discrimination, the system had no false alarms during a period of high thunderstorm activity in the Albuquerque area for the time from September 13 to October 3, 1977. Data and plots are included of those false alarms that were recorded before the final discriminants were implemented to provide an inventory of waveshapes for additional analysis

Lightning discrimination by a ground-based nuclear burst detection system

Energy Technology Data Exchange (ETDEWEB)

Thornbrough, A.D.

1978-04-01

Sandia Laboratories is developing for the U.S. Army a Ground-Based Nuclear Burst Detection System to provide pertinent information for its field commanders and higher authorities. The equipment must operate in all kinds of weather and produce very low false alarms under all types of conditions. With these requirements, a study of the effects during thunderstorms, which includes thousands of lightning flashes, was conducted. The results of these studies were that, with suitable discrimination, the system had no false alarms during a period of high thunderstorm activity in the Albuquerque area for the time from September 13 to October 3, 1977. Data and plots are included of those false alarms that were recorded before the final discriminants were implemented to provide an inventory of waveshapes for additional analysis.

Ground motion prediction needs for nuclear engineering design

International Nuclear Information System (INIS)

Hadjian, A.H.

1985-01-01

The basic design philosophy of nuclear power plants stipulates that the risk to the public be as low as reasonably achievable. As a result of this philosophy, the seismic design of nuclear power plants has tended, over time, to diverge from that of other engineered structures. The emphasis at the present time is to specify ground motion at a nuclear facility site as realistically as possible and to design all safety-related structures to respond to the specified ground motion in the elastic range. The characteristics of this realistic design ground motion are discussed and present prediction needs identified

Seismic hazard analysis. Review panel, ground motion panel, and feedback results

International Nuclear Information System (INIS)

Bernreuter, D.L.

1981-10-01

The Site Specific Spectra Project (SSSP) was a multi-year study funded by the U.S. Nuclear Regulatory Commission to provide estimates of the seismic hazards at a number of nuclear power plant sites in the Eastern U.S. A key element of our approach was the Peer Review Panel, which we formed in order to ensure that our use of expert opinion was reasonable. We discuss the Peer Review Panel results and provide the complete text of each member's report. In order to improve the ground motion model, an Eastern U.S. Ground Motion Model Panel was formed. In Section 4 we tabulate the responses from the panel members to our feedback questionnaire and discuss the implications of changes introduced by them. We conclude that the net difference in seismic hazard values from those presented in Volume 4 is small and does not warrant a reanalysis. (author)

Ground state energy fluctuations in the nuclear shell model

International Nuclear Information System (INIS)

Velazquez, Victor; Hirsch, Jorge G.; Frank, Alejandro; Barea, Jose; Zuker, Andres P.

2005-01-01

Statistical fluctuations of the nuclear ground state energies are estimated using shell model calculations in which particles in the valence shells interact through well-defined forces, and are coupled to an upper shell governed by random 2-body interactions. Induced ground-state energy fluctuations are found to be one order of magnitude smaller than those previously associated with chaotic components, in close agreement with independent perturbative estimates based on the spreading widths of excited states

Identifying Barriers in Implementing Outcomes-Based Assessment Program Review: A Grounded Theory Analysis

Science.gov (United States)

Bresciani, Marilee J.

2011-01-01

The purpose of this grounded theory study was to identify the typical barriers encountered by faculty and administrators when implementing outcomes-based assessment program review. An analysis of interviews with faculty and administrators at nine institutions revealed a theory that faculty and administrators' promotion, tenure (if applicable),…

A review of nuclear geophysics

International Nuclear Information System (INIS)

Clayton, C.G.; Schweitzer, J.S.

1992-01-01

This paper summarizes the development of nuclear geophysics in scientific and technological content and in range from its beginnings early in this century to the present day. We note that the early work in nuclear geophysics was originally referred to under the umbrella of open-quotes isotope applicationsclose quotes and the origin of the term open-quotes nuclear geophysicsclose quotes (which is seen to clarify and to focus work in this area) is exposed in this paper. The current expansion of nuclear geophysics front its original concern with oil well logging is an important trend because much of the underlying science, technology, and instrumentation is common ground. A review of nuclear geophysics would be a barren document without reference to long-term and, in some cases, short-term commercial and economic as well as to technological considerations, since these factors are the principal motivation for further development

A review on the status of development in thorium-based nuclear fuels

International Nuclear Information System (INIS)

Lee, Young Woo; Na, S. H.; Lee, Y. W.; Kim, H. S.; Kim, S. H.; Joung, C.Y.

2000-02-01

Thorium as an alternative nuclear energy source had been widely investigated in the 1950s-1960s because it is more abundant than uranium, but the studies of thorium nuclear fuel cycle were discontinued by political and economic reasons in the 1970s. Recently, however, renewed interest was vested in thorium-based nuclear fuel cycle because it may generate less long-lived minor actinides and has a lower radiotoxicity of high level wastes after reprocessing compared with the thorium fuel cycle. In this state-of the art report, thorium-based nuclear cycle. In this state-of the art report, thorium-based nuclear fuel cycle and fuel fabrication processes developed so far with different reactor types are reviewed and analyzed to establish basic technologies of thorium fuel fabrication which could meet our situation. (author)

Nuclear review: the real thing?

International Nuclear Information System (INIS)

Barker, F.

1993-01-01

The Consortium of Opposing Local Authorities (Cola) will present objections to new nuclear power stations to the Government review of nuclear power which will start soon (late 1993/1994). Cola's case consists of four main arguments. First, financial, with expectations of construction cost increases, poor performance, costs of retrofitting as tighter safety standards are introduced and decommissioning costs. Second, market protection beyond 1998 cannot be justified on security of supply or environmental grounds. Thirdly, estimates of further PWR generating costs cannot be considered competitive with fossil-fuel alternatives. Fourthly, the disadvantages outweigh the advantages so the creation or maintenance of the market conditions which can overcome the risk aversion of private capital cannot be justified. (author)

Review of commonly used remote sensing and ground-based ...

African Journals Online (AJOL)

This review provides an overview of the use of remote sensing data, the development of spectral reflectance indices for detecting plant water stress, and the usefulness of field measurements for ground-truthing purposes. Reliable measurements of plant water stress over large areas are often required for management ...

Power quality considerations for nuclear spectroscopy applications: Grounding

Science.gov (United States)

García-Hernández, J. M.; Ramírez-Jiménez, F. J.; Mondragón-Contreras, L.; López-Callejas, R.; Torres-Bribiesca, M. A.; Peña-Eguiluz, R.

2013-11-01

Traditionally the electrical installations are designed for supplying power and to assure the personnel safety. In nuclear analysis laboratories, additional issues about grounding also must be considered for proper operation of high resolution nuclear spectroscopy systems. This paper shows the traditional ways of grounding nuclear spectroscopy systems and through different scenarios, it shows the effects on the more sensitive parameter of these systems: the energy resolution, it also proposes the constant monitoring of a power quality parameter as a way to preserve or to improve the resolution of the systems, avoiding the influence of excessive extrinsic noise.

Ground acceleration in a nuclear power plant

International Nuclear Information System (INIS)

Pena G, P.; Balcazar, M.; Vega R, E.

2015-09-01

A methodology that adopts the recommendations of international organizations for determining the ground acceleration at a nuclear power plant is outlined. Systematic presented here emphasizes the type of geological, geophysical and geotechnical studies in different areas of influence, culminating in assessments of Design Basis earthquake and the earthquake Operating Base. The methodology indicates that in regional areas where the site of the nuclear power plant is located, failures are identified in geological structures, and seismic histories of the region are documented. In the area of detail geophysical tools to generate effects to determine subsurface propagation velocities and spectra of the induced seismic waves are used. The mechanical analysis of drill cores allows estimating the efforts that generate and earthquake postulate. Studies show that the magnitude of the Fukushima earthquake, did not affect the integrity of nuclear power plants due to the rocky settlement found. (Author)

Review of nuclear techniques in South African agricultural research: 1963-1984

International Nuclear Information System (INIS)

Marais, P.G.; Kotze, W.A.G.; Joubert, M.E.; Huismans, H.; Brodrick, H.T.

1985-01-01

The use of nuclear techniques in agriculture research in the RSA was reviewed at a National Conference on Nuclear Energy in 1963. Since then, 573 publications on the use of nuclear techniques in agriculture have appeared, which can be classified as follows: zoology; botany; food irradiation; soil and plant relations; soil moisture and ground water studies; and other radiation and tracer applications. A survey of literature on the use of radioactive isotopes in agriculture published between 1973 and 1980, including South African publications, was compiled by the Atomic Energy Board in 1980 but did not include any review of the scientific material

Application of Low Voltage High Resistance Grounding in Nuclear Power Plants

Directory of Open Access Journals (Sweden)

Choong-Koo Chang

2016-02-01

Full Text Available Most nuclear power plants now utilize solid grounded low voltage systems. For safety and reliability reasons, the low voltage (LV high resistance grounding (HRG system is also increasingly used in the pulp and paper, petroleum and chemical, and semiconductor industries. Fault detection is easiest and fastest with a solidly grounded system. However, a solidly grounded system has many limitations such as severe fault damage, poor reliability on essential circuits, and electrical noise caused by the high magnitude of ground fault currents. This paper will briefly address the strengths and weaknesses of LV grounding systems. An example of a low voltage HRG system in the LV system of a nuclear power plant will be presented. The HRG system is highly recommended for LV systems of nuclear power plants if sufficient considerations are provided to prevent nuisance tripping of ground fault relays and to avoid the deterioration of system reliability.

Goals, Objectives, and Requirements (GOR) of the Ground-based Nuclear Detonation Detection (GNDD) Team for the Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D)

International Nuclear Information System (INIS)

Casey, Leslie A.

2014-01-01

The goal, objectives, and requirements (GOR) presented in this document define a framework for describing research directed specifically by the Ground-based Nuclear Detonation Detection (GNDD) Team of the National Nuclear Security Administration (NNSA). The intent of this document is to provide a communication tool for the GNDD Team with NNSA management and with its stakeholder community. It describes the GNDD expectation that much of the improvement in the proficiency of nuclear explosion monitoring will come from better understanding of the science behind the generation, propagation, recording, and interpretation of seismic, infrasound, hydroacoustic, and radionuclide signals and development of 'game-changer' advances in science and technology.

Goals, Objectives, and Requirements (GOR) of the Ground-based Nuclear Detonation Detection (GNDD) Team for the Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D)

Energy Technology Data Exchange (ETDEWEB)

Casey, Leslie A.

2014-01-13

The goal, objectives, and requirements (GOR) presented in this document define a framework for describing research directed specifically by the Ground-based Nuclear Detonation Detection (GNDD) Team of the National Nuclear Security Administration (NNSA). The intent of this document is to provide a communication tool for the GNDD Team with NNSA management and with its stakeholder community. It describes the GNDD expectation that much of the improvement in the proficiency of nuclear explosion monitoring will come from better understanding of the science behind the generation, propagation, recording, and interpretation of seismic, infrasound, hydroacoustic, and radionuclide signals and development of "game-changer" advances in science and technology.

An assessment of testing requirement impacts on nuclear thermal propulsion ground test facility design

International Nuclear Information System (INIS)

Shipers, L.R.; Ottinger, C.A.; Sanchez, L.C.

1993-01-01

Programs to develop solid core nuclear thermal propulsion (NTP) systems have been under way at the Department of Defense (DoD), the National Aeronautics and Space Administration (NASA), and the Department of Energy (DOE). These programs have recognized the need for a new ground test facility to support development of NTP systems. However, the different military and civilian applications have led to different ground test facility requirements. The Department of Energy (DOE) in its role as landlord and operator of the proposed research reactor test facilities has initiated an effort to explore opportunities for a common ground test facility to meet both DoD and NASA needs. The baseline design and operating limits of the proposed DoD NTP ground test facility are described. The NASA ground test facility requirements are reviewed and their potential impact on the DoD facility baseline is discussed

Nuclear fuel waste management and disposal concept: Report. Federal environmental assessment review process

International Nuclear Information System (INIS)

1998-01-01

The Canadian concept for disposing CANDU reactor waste or high-level nuclear wastes from reprocessing involves underground disposal in sealed containers emplaced in buffer-filled and sealed vaults 500--1,000 meters below ground, in plutonic rock of the Canadian Shield. This document presents the report of a panel whose mandate was to review this concept (rather than a specific disposal project at a specific site) along with a broad range of related policy issues, and to conduct that review in five provinces (including reviews with First Nations groups). It first outlines the review process and then describes the nature of the problem of nuclear waste management. It then presents an overview of the concept being reviewed, its implementation stages, performance assessment analyses performed on the concept, and implications of a facility based on that concept (health, environmental, social, transportation, economic). The fourth section examines the criteria by which the safety and acceptability of the concept should be evaluated. This is followed by a safety and acceptability evaluation from both technical and social perspectives. Section six proposes future steps for building and determining acceptability of the concept, including an Aboriginal participation process, creation of a Nuclear Fuel Waste Management Agency, and a public participation process. The final section discusses some issues outside the panel's mandate, such as energy policy and renewable energy sources. Appendices include a chronology of panel activities, a review of radiation hazards, comparison between nuclear waste management and the management of other wastes, a review of other countries' approaches to long-term management of nuclear fuel wastes, and details of a siting process proposed by the panel

Nuclear safety review for 1984

International Nuclear Information System (INIS)

1985-08-01

This publication is based on the fourth Nuclear Safety Review prepared by the IAEA Secretariat for presentation to the Board of Governors. It discusses relevant international activities in 1984 and the current status of nuclear safety and radiation protection, and looks ahead to anticipated developments

Nuclear Posture Review

Science.gov (United States)

2018-02-01

REVIEW margin for further delay in recapitalizing the physical infrastructure needed to produce strategic materials and components for U.S. nuclear... REVIEW 2018 This page left intentionally blank REVIEW NUCLEAR POSTURE REVIEW FEBRUARY 2018...OFFICE OF THE SECRETARY OF DEFENSE This page left intentionally blank REVIEW CONTENTS SECRETARY’S PREFACE

Proceedings of the 24th Seismic Research Review: Nuclear Explosion Monitoring: Innovation and Integration

International Nuclear Information System (INIS)

Warren, N. Jill

2002-01-01

These proceedings contain papers prepared for the 24th Seismic Research Review: Nuclear Explosion Monitoring: Innovation and Integration, held 17-19 September, 2002 in Ponte Vedra Beach, Florida. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Proceedings of the 24th Seismic Research Review: Nuclear Explosion Monitoring: Innovation and Integration

Energy Technology Data Exchange (ETDEWEB)

Warren, N. Jill [Editor

2002-09-17

These proceedings contain papers prepared for the 24th Seismic Research Review: Nuclear Explosion Monitoring: Innovation and Integration, held 17-19 September, 2002 in Ponte Vedra Beach, Florida. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Review and Application of Ship Collision and Grounding Analysis Procedures

DEFF Research Database (Denmark)

Pedersen, Preben Terndrup

2010-01-01

It is the purpose of the paper to present a review of prediction and analysis tools for collision and grounding analyses and to outline a probabilistic procedure for which these tools can be used by the maritime industry to develop performance based rules to reduce the risk associated with human,......, environmental and economic costs of collision and grounding events. The main goal of collision and grounding research should be to identify the most economic risk control options associated with prevention and mitigation of collision and grounding events....

Proceedings of the 26th Seismic Research Review: Trends in Nuclear Explosion Monitoring

International Nuclear Information System (INIS)

Chavez, Francesca C.; Benson, Jody; Hanson, Stephanie; Mark, Carol; Wetovsky, Marvin A.

2004-01-01

These proceedings contain papers prepared for the 26th Seismic Research Review: Trends in Nuclear Explosion Monitoring, held 21-23 September, 2004 in Orlando, Florida. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Proceedings of the 26th Seismic Research Review: Trends in Nuclear Explosion Monitoring

Energy Technology Data Exchange (ETDEWEB)

Chavez, Francesca C [Editor; Benson, Jody [Editor; Hanson, Stephanie [Editor; Mark, Carol [Editor; Wetovsky, Marvin A [Editor

2004-09-21

These proceedings contain papers prepared for the 26th Seismic Research Review: Trends in Nuclear Explosion Monitoring, held 21-23 September, 2004 in Orlando, Florida. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Ground test facilities for evaluating nuclear thermal propulsion engines and fuel elements

International Nuclear Information System (INIS)

Allen, G.C.; Beck, D.F.; Harmon, C.D.; Shipers, L.R.

1992-01-01

Interagency panels evaluating nuclear thermal propulsion development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and design issues of a proposed ground test complex for evaluating nuclear thermal propulsion engines and fuel elements being developed for the Space Nuclear Thermal Propulsion (SNTP) program. 2 refs

Ground acceleration in a nuclear power plant; Aceleracion del suelo en una central nuclear

Energy Technology Data Exchange (ETDEWEB)

Pena G, P.; Balcazar, M.; Vega R, E., E-mail: pablo.pena@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2015-09-15

A methodology that adopts the recommendations of international organizations for determining the ground acceleration at a nuclear power plant is outlined. Systematic presented here emphasizes the type of geological, geophysical and geotechnical studies in different areas of influence, culminating in assessments of Design Basis earthquake and the earthquake Operating Base. The methodology indicates that in regional areas where the site of the nuclear power plant is located, failures are identified in geological structures, and seismic histories of the region are documented. In the area of detail geophysical tools to generate effects to determine subsurface propagation velocities and spectra of the induced seismic waves are used. The mechanical analysis of drill cores allows estimating the efforts that generate and earthquake postulate. Studies show that the magnitude of the Fukushima earthquake, did not affect the integrity of nuclear power plants due to the rocky settlement found. (Author)

Quaternary ground siting technology of nuclear power plants

International Nuclear Information System (INIS)

Nishi, K.; Kokusho, T.; Iwatate, Y.; Ishida, K.; Honsho, S.; Okamoto, T.; Tohma, J.; Tanaka, Y.; Kanatani, M.

1992-01-01

A seismic stability evaluation method for a nuclear power plant to be located on Quaternary sandy/gravelly ground is discussed herein in terms of a geological and geotechnical survey, a design earthquake motion evaluation and geotechnical seismic stability analyses. The geological and geotechnical exploration tunnel in the rock foundation siting will be difficult in the Quaternary ground siting. Boring, geophysical surveys and soil sampling will play a major role in this case. A design earthquake input spectrum for this siting is proposed to take in account the significant effect of longer period motion on ground stability. Equivalent and non-linear analyses demonstrate the seismic stability of the foundation ground so long as the soil density is high. (author)

Procedures for evaluation of vibratory ground motions of soil deposits at nuclear power plant sites

International Nuclear Information System (INIS)

1975-06-01

According to USNRC requirements set forth in Appendix A, 10 CFR, Part 100, vibratory ground motion criteria for a nuclear plant must be based on local soil conditions, as well as on the seismicity, geology, and tectonics of the region. This report describes how such criteria can be developed by applying the latest technology associated with analytical predictions of site-dependent ground motions and with the use of composite spectra obtained from the current library of strong motion records. Recommended procedures for defining vibratory ground motion criteria contain the following steps: (1) geologic and seismologic studies; (2) site soils investigations; (3) site response sensitivity studies; (4) evaluation of local site response characteristics; (5) selection of site-matched records; and (6) appraisal and selection of seismic input criteria. An in-depth discussion of the engineering characteristics of earthquake ground motions including parameters used to characterize earthquakes and strong motion records, geologic factors that influence ground shaking, the current strong motion data base, and case histories of the effects of past earthquake events is presented. Next, geotechnical investigations of the seismologic, geologic, and site soil conditions required to develop vibratory motion criteria are briefly summarized. The current technology for establishing vibratory ground motion criteria at nuclear plant sites, including site-independent and site-dependent procedures that use data from strong motion records and from soil response analyses is described. (auth)

Proprietary, standard, and government-supported nuclear data bases

International Nuclear Information System (INIS)

Poncelet, C.G.; Ozer, O.; Harris, D.R.

1975-07-01

This study presents an assessment of the complex situation surrounding nuclear data bases for nuclear power technology. Requirements for nuclear data bases are identified as regards engineering functions and system applications for the many and various user groups that rely on nuclear data bases. Current practices in the development and generation of nuclear data sets are described, and the competitive aspect of design nuclear data set development is noted. The past and current role of the federal government in nuclear data base development is reviewed, and the relative merits of continued government involvement are explored. National policies of the United States and other industrial countries regarding the availability of nationally supported nuclear data information are reviewed. Current proprietary policies of reactor vendors regarding design library data sets are discussed along with the basis for such proprietary policies. The legal aspects of protective policies are explored as are their impacts on the nuclear power industry as a whole. The effect of the regulatory process on the availability and documentation of nuclear data bases is examined. Current nuclear data standard developments are reviewed, including a discussion of the standard preparation process. Standards currently proposed or in preparation that directly relate to nuclear data bases are discussed in some detail. (auth)

Variational Monte Carlo calculations of nuclear ground states

International Nuclear Information System (INIS)

Wiringa, R.B.

1990-01-01

A major goal in nuclear physics is to understand how nuclear structure comes about from the underlying interactions between nucleons. This requires modelling nuclei as collections of strongly interacting nucleons. We start with realistic nucleon-nucleon potentials, supplemented with consistent three-nucleon potentials and two-body electroweak current operators, and try to predict nuclear ground properties, such as the binding energy, density and momentum distributions, and electromagnetic form factors. We also seek to predict other properties of nuclei such as excited states and low-energy reactions. 21 refs., 14 figs., 5 tabs

The Nuclear Review: the Institution of Nuclear Engineers' response to the Review of Nuclear Power

International Nuclear Information System (INIS)

Anon.

1994-01-01

The United Kingdom Government's Nuclear Review currently underway, addresses whether and in what form nuclear power should continue to be part of the country's power generation capability. This article sets out the response of the Institution of Nuclear Engineers to the Nuclear Review. This pro-nuclear group emphasises the benefits to be gained from diversity of generation in the energy supply industry. The environmentally benign nature of nuclear power is emphasised, in terms of gaseous emissions. The industry's excellent safety record also argues in favour of nuclear power. Finally, as power demand increases globally, a health U.K. nuclear industry could generate British wealth through power exports and via the construction industry. The Institution's view on radioactive waste management is also set out. (UK)

Stability evaluation of ground considering dynamic vertical ground motion. Pt. 3. Effect of dynamic vertical motions on sliding safety factor of foundation ground and surrounding slope in nuclear power plant

International Nuclear Information System (INIS)

Ishikawa, Hiroyuki; Sato, Hiroaki; Kawai, Tadashi; Kanatani, Mamoru

2003-01-01

In this report, time differences of the peak accelerations between horizontal and vertical motions were investigated based on the earthquake records on the rock sites and analytical studies were carried out in order to investigate the effect of them to the fluctuations of the minimum sliding safety factors of the foundation ground and surrounding slope of nuclear power plants. Summaries of this report were as follows; (1) Maximum time difference of the peak accelerations between horizontal and vertical motions on the rock sites was approximately 10 seconds in the earthquakes within the epicenter distance of 100 km. (2) Analytical studies that employed the equivalent linear analysis with horizontal and vertical input motions were carried out against the representative models and ground properties of the foundation grounds and surrounding slopes in nuclear power plants. The combinations of the horizontal and vertical motions were determined from the above-mentioned investigation results based on the actual earthquake records. It was revealed that the fluctuations of the minimum sliding safety factors were not seriously affected by the time difference of the peak accelerations between horizontal and vertical motions. (author)

Grounded theory research: literature reviewing and reflexivity.

Science.gov (United States)

McGhee, Gerry; Marland, Glenn R; Atkinson, Jacqueline

2007-11-01

This paper is a report of a discussion of the arguments surrounding the role of the initial literature review in grounded theory. Researchers new to grounded theory may find themselves confused about the literature review, something we ourselves experienced, pointing to the need for clarity about use of the literature in grounded theory to help guide others about to embark on similar research journeys. The arguments for and against the use of a substantial topic-related initial literature review in a grounded theory study are discussed, giving examples from our own studies. The use of theoretically sampled literature and the necessity for reflexivity are also discussed. Reflexivity is viewed as the explicit quest to limit researcher effects on the data by awareness of self, something seen as integral both to the process of data collection and the constant comparison method essential to grounded theory. A researcher who is close to the field may already be theoretically sensitized and familiar with the literature on the study topic. Use of literature or any other preknowledge should not prevent a grounded theory arising from the inductive-deductive interplay which is at the heart of this method. Reflexivity is needed to prevent prior knowledge distorting the researcher's perceptions of the data.

Reviewing nuclear power

International Nuclear Information System (INIS)

Robinson, Colin

1990-01-01

The UK government has proposed a review of the prospects for nuclear power as the Sizewell B pressurized water reactor project nears completion in 1994. However, a delay in the completion of Sizewell B or a change of government could put off the review for some years beyond the mid 1990s. Anticipating, though, that such a review will eventually take place, issues which it should consider are addressed. Three broad categories of possible benefit claimed for nuclear power are examined. These are that nuclear power contributes to the security of energy supply, that it provides protection against long run fossil fuel price increases and that it is a means of mitigating the greenhouse effect. Arguments are presented which cost doubt over the reality of these benefits. Even if these benefits could be demonstrated, they would have to be set against the financial, health and accident costs attendant on nuclear power. It is concluded that the case may be made that nuclear power imposes net costs on society that are not justified by the net benefits conferred. Some comments are made on how a government review, if and when it takes place, should be conducted. (UK)

The nuclear review

International Nuclear Information System (INIS)

Jeffrey, R.

1995-01-01

The prospects for nuclear power in the United Kingdom are considered from the point of view of Scottish Nuclear and in the context of the government's Nuclear Review and forthcoming proposals for the future of nuclear generation. Scottish Nuclear has been successful in transforming a loss making public sector company into one which is profitable. If proper account is taken of the risks of higher gas prices, environmental costs and the vulnerability to which the UK energy supply industry might be exposed by over dependence on gas, nuclear power is seen to be attractive. Outcome from the Review which Scottish Nuclear would like to see includes: a separation of their successful ongoing AGR programme from the historical magnox liabilities; a segregated fund to deal with long term AGR decommissioning and waste liabilities; greater commercial freedom and a move towards privatisation. (UK)

Ground Testing a Nuclear Thermal Rocket: Design of a sub-scale demonstration experiment

Energy Technology Data Exchange (ETDEWEB)

David Bedsun; Debra Lee; Margaret Townsend; Clay A. Cooper; Jennifer Chapman; Ronald Samborsky; Mel Bulman; Daniel Brasuell; Stanley K. Borowski

2012-07-01

In 2008, the NASA Mars Architecture Team found that the Nuclear Thermal Rocket (NTR) was the preferred propulsion system out of all the combinations of chemical propulsion, solar electric, nuclear electric, aerobrake, and NTR studied. Recently, the National Research Council committee reviewing the NASA Technology Roadmaps recommended the NTR as one of the top 16 technologies that should be pursued by NASA. One of the main issues with developing a NTR for future missions is the ability to economically test the full system on the ground. In the late 1990s, the Sub-surface Active Filtering of Exhaust (SAFE) concept was first proposed by Howe as a method to test NTRs at full power and full duration. The concept relied on firing the NTR into one of the test holes at the Nevada Test Site which had been constructed to test nuclear weapons. In 2011, the cost of testing a NTR and the cost of performing a proof of concept experiment were evaluated.

Nuclear program review

International Nuclear Information System (INIS)

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

1985-01-01

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

A simple dynamic rising nuclear cloud based model of ground radioactive fallout for atmospheric nuclear explosion

International Nuclear Information System (INIS)

Zheng Yi

2008-01-01

A simple dynamic rising nuclear cloud based model for atmospheric nuclear explosion radioactive prediction was presented. The deposition of particles and initial cloud radius changing with time before the cloud stabilization was considered. Large-scale relative diffusion theory was used after cloud stabilization. The model was considered reasonable and dependable in comparison with four U.S. nuclear test cases and DELFIC model results. (authors)

Nuclear heating - a review of projects in several countries

International Nuclear Information System (INIS)

Vymetal, L.

1980-01-01

A review is presented of projects and studies of nuclear heat generation and district heating in the USSR, France, Sweden, Finland, USA, FRG, and CSSR. Attention is primarily paid to the nuclear sources, i.e., nuclear power and heating plants and special reactors for nuclear heating plants. The questions of heat transmission and costs are also dealt with. The review is based on the literature published between 1976 and 1979. An important source were materials from the conference on the use of low-potential heat from nuclear reactors held in Otaniemi (Finland) in 1977. (author)

α-decay half-lives of some nuclei from ground state to ground state using different nuclear potential

Directory of Open Access Journals (Sweden)

Akrawy Dashty T.

2018-01-01

Full Text Available Theoretical α-decay half-lives of some nuclei from ground state to ground state are calculated using different nuclear potential model including Coulomb proximity potential (CPPM, Royer proximity potential and Broglia and Winther 1991. The calculated values comparing with experimental data, it is observed that the CPPM model is in good agreement with the experimental data.

The ground based plan

International Nuclear Information System (INIS)

1989-01-01

The paper presents a report of ''The Ground Based Plan'' of the United Kingdom Science and Engineering Research Council. The ground based plan is a plan for research in astronomy and planetary science by ground based techniques. The contents of the report contains a description of:- the scientific objectives and technical requirements (the basis for the Plan), the present organisation and funding for the ground based programme, the Plan, the main scientific features and the further objectives of the Plan. (U.K.)

Concept of ground facilities and the analyses of the factors for cost estimation

Energy Technology Data Exchange (ETDEWEB)

Lee, J. Y.; Choi, H. J.; Choi, J. W.; Kim, S. K.; Cho, D. K

2007-09-15

The geologic disposal of spent fuels generated from the nuclear power plants is the only way to protect the human beings and the surrounding environments present and future. The direct disposal of the spent fuels from the nuclear power plants is considered, and a Korean Reference HLW disposal System(KRS) suitable for our representative geological conditions have been developed. In this study, the concept of the spent fuel encapsulation process as a key of the above ground facilities for deep geological disposal was established. To do this, the design requirements, such as the functions and the spent fuel accumulations, were reviewed. Also, the design principles and the bases were established. Based on the requirements and the bases, the encapsulation process of the spent fuel from receiving spent fuel of nuclear power plants to transferring canister into the underground repository was established. Simulation for the above-ground facility in graphic circumstances through KRS design concept and disposal scenarios for spent nuclear fuel showed that an appropriate process was performed based on facility design concept and required for more improvement on construction facility by actual demonstration test. And, based on the concept of the above ground facilities for the Korean Reference HLW disposal System, the analyses of the factors for the cost estimation was carried out.

Nuclear Safety Review 2013

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-15

The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis.

Nuclear Safety Review 2013

International Nuclear Information System (INIS)

2013-07-01

The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis

Silicon carbide optics for space and ground based astronomical telescopes

Science.gov (United States)

Robichaud, Joseph; Sampath, Deepak; Wainer, Chris; Schwartz, Jay; Peton, Craig; Mix, Steve; Heller, Court

2012-09-01

Silicon Carbide (SiC) optical materials are being applied widely for both space based and ground based optical telescopes. The material provides a superior weight to stiffness ratio, which is an important metric for the design and fabrication of lightweight space telescopes. The material also has superior thermal properties with a low coefficient of thermal expansion, and a high thermal conductivity. The thermal properties advantages are important for both space based and ground based systems, which typically need to operate under stressing thermal conditions. The paper will review L-3 Integrated Optical Systems - SSG’s (L-3 SSG) work in developing SiC optics and SiC optical systems for astronomical observing systems. L-3 SSG has been fielding SiC optical components and systems for over 25 years. Space systems described will emphasize the recently launched Long Range Reconnaissance Imager (LORRI) developed for JHU-APL and NASA-GSFC. Review of ground based applications of SiC will include supporting L-3 IOS-Brashear’s current contract to provide the 0.65 meter diameter, aspheric SiC secondary mirror for the Advanced Technology Solar Telescope (ATST).

International Nuclear Officials Discuss IAEA Peer Reviews of Nuclear Safety Regulations

International Nuclear Information System (INIS)

2011-01-01

Full text: Senior nuclear regulators today concluded a Workshop on the Lessons Learned from the IAEA Integrated Regulatory Review Service (IRRS) Missions. The U.S. Nuclear Regulatory Commission (NRC) hosted the workshop, in cooperation with the International Atomic Energy Agency, in Washington, DC, from 26 to 28 October 2011. About 60 senior regulators from 22 IAEA Member States took part in this workshop. The IRRS programme is an international peer review service offered by the IAEA to its Member States to provide an objective evaluation of their nuclear safety regulatory framework. The review is based on the internationally recognized IAEA Safety Standards. ''The United States Nuclear Regulatory Commission was pleased to host the IAEA's IRRS meeting this week. The discussions over the past three days have provided an important opportunity for regulators from many countries to come together to strengthen the international peer review process,'' said U.S. NRC Chairman Gregory B. Jaczko. ''Especially after the Fukushima Daiichi accident, the global community recognizes that IRRS missions fill a vital role in strengthening nuclear safety and security programs around the world, and we are proud to be a part of this important effort.'' The IAEA Action Plan on Nuclear Safety includes actions focused towards strengthening the existing IAEA peer reviews, incorporating lessons learned and improving their effectiveness. The workshop provided a platform for the exchange of information, experience and lessons learned from the IRRS missions, as well as expectations for the IRRS programme for the near future. Further improvements in the planning and implementation of the IRRS missions in the longer term were discussed. A strong commitment of all relevant national authorities to the IRRS programme was identified as a key element of an effective regulatory framework. The conclusions of the workshop will be issued in November 2011 and the main results will be reported to the IAEA

Relativistic analysis of nuclear ground state densities at 135 to 200 ...

Indian Academy of Sciences (India)

fitting of differential cross-section and analyzing power, and the appearance of wine-bottle- ... So, the effect of different nuclear density distributions is quite conspicuous in the relativistic ap- proach. Hence, we have analyzed five different nuclear ground state .... The NEG and FNEG densities have been used to see the effect.

Nuclear instrumentation and measurement: a review based on the ANIMMA conferences

Science.gov (United States)

Giot, Michel; Vermeeren, Ludo; Lyoussi, Abdallah; Reynard-Carette, Christelle; Lhuillier, Christian; Mégret, Patrice; Deconinck, Frank; Gonçalves, Bruno Soares

2017-12-01

The ANIMMA conferences offer a unique opportunity to discover research carried out in all fields of nuclear measurements and instrumentation with applications extending from fundamental physics to fission and fusion reactors, medical imaging, environmental protection and homeland security. After four successful editions of the Conference, it was decided to prepare a review based to a large extent but not exclusively on the papers presented during the first four editions of the conference. This review is organized according to the measurement methodologies: neutronic, photonic, thermal, acoustic and optical measurements, as well as medical imaging and specific challenges linked to data acquisition and electronic hardening. The paper describes the main challenges justifying research in these different areas, and summarizes the recent progress reported. It offers researchers and engineers a way to quickly and efficiently access knowledge in highly specialized areas.

Ground test facility for nuclear testing of space reactor subsystems

International Nuclear Information System (INIS)

Quapp, W.J.; Watts, K.D.

1985-01-01

Two major reactor facilities at the INEL have been identified as easily adaptable for supporting the nuclear testing of the SP-100 reactor subsystem. They are the Engineering Test Reactor (ETR) and the Loss of Fluid Test Reactor (LOFT). In addition, there are machine shops, analytical laboratories, hot cells, and the supporting services (fire protection, safety, security, medical, waste management, etc.) necessary to conducting a nuclear test program. This paper presents the conceptual approach for modifying these reactor facilities for the ground engineering test facility for the SP-100 nuclear subsystem. 4 figs

Nuclear Test Personnel Review

Science.gov (United States)

FOIA Electronic Reading Room Privacy Impact Assessment DTRA No Fear Act Reporting Nuclear Test Personnel Review NTPR Fact Sheets NTPR Radiation Dose Assessment Documents US Atmospheric Nuclear Test History Documents US Underground Nuclear Test History Reports NTPR Radiation Exposure Reports Enewetak

Study on Quaternary ground siting of nuclear power plant, (1)

International Nuclear Information System (INIS)

Kokusho, Takaji; Nishi, Koichi; Honsho, Shizumitsu

1991-01-01

A seismic stability evaluation method for a nuclear power plant to be located on a Quaternary sandy/gravelly ground is discussed herein in terms of the geological and geotechnical survey, design earthquake motion evaluation and geotechnical seismic stability analyses. The geological and geotechnical exploration tunnel in the rock-foundation siting will be difficult in the Quaternary ground siting. Boring, geophysical surveys and soil samplings will play a major role in this case. The design earthquake input spectrum for this siting is proposed so as to take account the significant effect of longer period motion on the ground stability. Equivalent and non-linear analyses demonstrate the seismic stability of the foundation ground so long as the soil density is high. (author)

Calculated concentrations of any radionuclide deposited on the ground by release from underground nuclear detonations, tests of nuclear rockets, and tests of nuclear ramjet engines

International Nuclear Information System (INIS)

Hicks, H.G.

1981-11-01

This report presents calculated gamma radiation exposure rates and ground deposition of related radionuclides resulting from three types of event that deposited detectable radioactivity outside the Nevada Test Site complex, namely, underground nuclear detonations, tests of nuclear rocket engines and tests of nuclear ramjet engines

Nuclear technology review 2002

International Nuclear Information System (INIS)

2002-08-01

The unifying theme of the Nuclear Technology Review 2002 (NTR-2002) is the importance of innovation. Innovation makes it possible to step beyond incremental evolutionary improvements constrained by diminishing returns. For crop production and public health, for example, the sterile insect technique created a whole new path for future improvements, distinctly different from applying ever larger amounts of pesticides. Nuclear techniques offer a new and safer approach to removing the world's estimated 60,000,000 abandoned land mines. New precision techniques create the potential for ever less intrusive and more effective radiation treatments for cancer. For nuclear power continuing innovation will be a key factor in closing the projection gap between long term global energy scenarios in which nuclear power expands substantially and near term scenarios with only modest expansion or even decline. While the NTR-2002 presents a worldwide review of the state-of-the-art of nuclear science and technology, and not an annual report on IAEA activities, it notes areas where the Agency has a particularly important role to play. Part I of the NTR-2002 'Fundamentals of Nuclear Development', reviews developments in the field of nuclear, atomic and molecular data. Research reactors remain essential to progress in nuclear science and technology. Part I reviews advances in radioisotope production, the use of accelerators and neutron activation analysis relevant to applications ranging from medicine particularly the light against cancer to industry. Part I also reviews developments in nuclear instrumentation and nuclear fusion, particularly in connection with the International Thermonuclear Experimental Reactor. Part II begins with a summary of nuclear power production in 2001. At the end of 2001 there were 438 nuclear power plants (NPPs) in operation, corresponding to a total capacity of 353 GW(e), more than 10000 reactor-years of cumulative operating experience and about 16% of global

Space nuclear power plant technology development philosophy for a ground engineering phase

International Nuclear Information System (INIS)

Buden, D.; Trapp, T.J.; Los Alamos National Lab., NM)

1985-01-01

The development of a space qualified nuclear power plant is proceeding from the technical assessment and advancement phase to the ground engineering phase. In this new phase, the selected concept will be matured by the completion of activities needed before protoflight units can be assembled and qualified for first flight applications. This paper addresses a possible philosophy to arrive at the activities to be performed during the ground engineering phase. The philosophy is derived from what we believe a potential user of nuclear power would like to see completed before commitment to a flight development phase. 5 references

Space nuclear power plant technology development philosophy for a ground engineering phase

International Nuclear Information System (INIS)

Buden, D.; Trapp, T.J.

1985-01-01

The development of a space qualified nuclear power plant is proceeding from the Technical Assessment and Advancement Phase to the Ground Engineering Phase. In this new phase, the selected concept will be matured by the completion of activities needed before protoflight units can be assembled and qualified for first flight applications. This paper addresses a possible philosophy to arrive at the activities to be performed during the Ground Engineering Phase. The philosophy is derived from what we believe a potential user of nuclear power would like to see completed before commitment to a flight development phase

Atomic mass and characteristic constant of nuclear ground state (CENPL.MCC). Pt. 1

International Nuclear Information System (INIS)

Su Zongdi; Ma Lizhen; Zhou Chunmei; Ge Zhigang

1994-01-01

Atomic mass and characteristic constants for nuclear ground states are basic data for nuclear physics, and necessary ones for basic researches, theoretical calculations, as well as many applied researches. The atomic mass of exotic nuclei quite far from the valley stability are also very important for astrophysics researches. The above-requirement is paid attention to in our setting up this file. The recent and as many as possible data (such as the half-lives of the new nuclides 202 Pt, 208 Hg and 185 Hf and the mass excess of 199 Ir, which were produced and distinguished by Chinese scientists) have been collected, and put into the computer-based data file in brief table format. (1 fig.)

U.S. Forward Operating Base Applications of Nuclear Power

International Nuclear Information System (INIS)

Griffith, George W.

2015-01-01

This paper provides a high level overview of current nuclear power technology and the potential use of nuclear power at military bases. The size, power ranges, and applicability of nuclear power units for military base power are reviewed. Previous and current reactor projects are described to further define the potential for nuclear power for military power.

A comparison of the different regulatory requirements of NPP in vertical ground motion

International Nuclear Information System (INIS)

Hou Chunlin; Pan Rong; Yang Yu; Wang Shuguo; Li Xiaojun

2015-01-01

Based on the importance of vertical motion in the nuclear power plants (NPPs) and equipment identification of seismic test, we summarize the existing laws and regulations cited by China's NPPs in the vertical seismic ground motion of the regulations. Then, according to the interpretation of various laws and regulations content, we may identified four vertical earthquake response spectrums. Finally, combined with the seismic safety requirements of China NPPs evaluation and the vertical seismic design of M310, EPR, AP1000 and CAP1400 pressurized water reactor, we explain that the vertical seismic ground motion selection should distinguish the effects between near field and far field earthquake, the existing regulations and specifications that China used are still required to further improve on the selection of vertical ground motion. The results of this study can provide reference for seismic design of China's nuclear power plant and nuclear safety review. (authors)

Current status of ground motions evaluation in seismic design guide for nuclear power facilities. Investigation on IAEA and US.NRC

International Nuclear Information System (INIS)

Nakajima, Masato; Ito, Hiroshi; Hirata, Kazuta

2009-01-01

Recently, IAEA (International Atomic Energy Agency) and US.NRC (US. Nuclear Regulatory Commission) published several standards and technical reports on seismic design and safety evaluation for nuclear power facilities. This report summarizes the current status of the international guidelines on seismic design and safety evaluation for nuclear power facilities in order to explore the future research topics. The main results obtained are as follows: 1 IAEA: (1) In the safety standard series, two levels are defined as seismic design levels, and design earthquake ground motion is determined corresponding to each seismic design level. (2) A new framework on seismic design which consists of conventional deterministic method and risk-based method is discussed in the technical report although the framework is not adopted in the safety guidelines. 2 USA: (1) US.NRC discusses a performance-based seismic design framework which has been originally developed by the private organization (American Society of Civil Engineers). (2) Design earthquakes and earthquake ground motion are mainly evaluated and determined based on probabilistic seismic hazard evaluations. 3 Future works: It should be emphasized that IAEA and US.NRC have investigated the implementation of risk-based concept into seismic design. The implementation of risk-based concept into regulation and seismic design makes it possible to consider various uncertainties and to improve accountability. Therefore, we need to develop the methods for evaluating seismic risk of structures, and to correlate seismic margin and seismic risk quantitatively. Moreover, the probabilistic method of earthquake ground motions, that is required in the risk-based design, should be applied to sites in Japan. (author)

Vertical-borehole ground-coupled heat pumps: A review of models and systems

Energy Technology Data Exchange (ETDEWEB)

Yang, H.; Cui, P. [Renewable Energy Research Group, Department of Building Services Engineering, The Hong Kong Polytechnic University, Hong Kong (China); Fang, Z. [Ground Source Heat Pump Research Center, Shandong Jianzhu University, Jinan (China)

2010-01-15

A large number of ground-coupled heat pump (GCHP) systems have been used in residential and commercial buildings throughout the world due to the attractive advantages of high efficiency and environmental friendliness. This paper gives a detailed literature review of the research and developments of the vertical-borehole GCHP technology for applications in air-conditioning. A general introduction on the ground source heat pump system and its development is briefly presented first. Then, the most typical simulation models of the vertical ground heat exchangers currently available are summarized in detail including the heat transfer processes outside and inside the boreholes. The various design/simulation programs for vertical GCHP systems primarily based on the typical simulation models are also reviewed in this paper. Finally, the various hybrid GCHP systems for cooling or heating-dominated buildings are well described. It is found that the GCHP technology can be used both in cold and hot weather areas and the energy saving potential is significant. (author)

Nuclear quadrupole moment of the 99Tc ground state

International Nuclear Information System (INIS)

Errico, Leonardo; Darriba, German; Renteria, Mario; Tang Zhengning; Emmerich, Heike; Cottenier, Stefaan

2008-01-01

By combining first-principles calculations and existing nuclear magnetic resonance (NMR) experiments, we determine the quadrupole moment of the 9/2 + ground state of 99 Tc to be (-)0.14(3)b. This confirms the value of -0.129(20)b, which is currently believed to be the most reliable experimental determination, and disagrees with two earlier experimental values. We supply ab initio calculated electric-field gradients for Tc in YTc 2 and ZrTc 2 . If this calculated information would be combined with yet to be performed Tc-NMR experiments in these compounds, the error bar on the 99 Tc ground state quadrupole moment could be further reduced

Some predicted peak ground motions for nuclear cratering explosions along the Qattara alignment in Egypt

International Nuclear Information System (INIS)

Bryan, J.B.

1980-01-01

Some predicted peak free-field ground motions at shot depth for the nuclear explosive excavation of a canal in Egypt are summarized. Peak values of displacement, velocity, acceleration, and radial stress are presented as a function of slant range from the working point. Results from two-dimensional TENSOR cratering calculations are included. Fits to ground motion measurements in other media are also shown. This summary is intended to help specify engineering design requirements for detonating nuclear explosive salvos which are required to efficiently excavate the canal. It also should be useful in guiding estimates for gage response ranges in ground motion measurements

Nuclear emergency planning in Spain. The PLABEN review project

International Nuclear Information System (INIS)

Lentijo Lentijo, J. C.; Vila Pena, M.

2002-01-01

The international rules and recommendations for nuclear emergency planning and the Spanish experience gained in the management of event with radiological risk have noticed that is necessary to review the planning radiological bases for emergencies in nuclear power plants and to define the planning radiological bases for radiological emergencies that could happen in radioactive facilities or in activities out of the regulatory framework. The paper focuses on CSN actions concerning the Plaben review project related to define the new radiological principles taking into account the current international recommendations for interventions, make a proposal about the organisation and operation of the provincial radiological action group and the national support level for radiological emergency response. (Author) 7 refs

Ground-based photo monitoring

Science.gov (United States)

Frederick C. Hall

2000-01-01

Ground-based photo monitoring is repeat photography using ground-based cameras to document change in vegetation or soil. Assume those installing the photo location will not be the ones re-photographing it. This requires a protocol that includes: (1) a map to locate the monitoring area, (2) another map diagramming the photographic layout, (3) type and make of film such...

The periodic safety review of nuclear power plants. Practices in OECD countries

International Nuclear Information System (INIS)

1992-01-01

This report gives an overview of the regulatory concepts and practices for the periodic safety review of nuclear power plants in OECD countries with nuclear power programmes. The statutory bases for such reviews, their objectives and the processes adopted are summarised against the background of each country's regulatory practices. Although periodic safety reviews are now, or will soon be, part of the regulatory process in the majority of countries, the national approaches to these reviews still differ considerably. This report includes numerous examples of the different concepts and practices in OECD countries, thereby illustrating the variety of ways adopted to reach the common goal of maintaining and improving nuclear safety

Effluent Containment System for space thermal nuclear propulsion ground test facilities

International Nuclear Information System (INIS)

1995-08-01

This report presents the research and development study work performed for the Space Reactor Power System Division of the U.S. Department of Energy on an innovative ECS that would be used during ground testing of a space nuclear thermal rocket engine. A significant portion of the ground test facilities for a space nuclear thermal propulsion engine are the effluent treatment and containment systems. The proposed ECS configuration developed recycles all engine coolant media and does not impact the environment by venting radioactive material. All coolant media, hydrogen and water, are collected, treated for removal of radioactive particulates, and recycled for use in subsequent tests until the end of the facility life. Radioactive materials removed by the treatment systems are recovered, stored for decay of short-lived isotopes, or packaged for disposal as waste. At the end of the useful life, the facility will be decontaminated and dismantled for disposal

Operational safety review programmes for nuclear power plants. Guidelines for assessment

International Nuclear Information System (INIS)

2002-01-01

The IAEA has been offering the Operational Safety Review Team (OSART) programme to provide advice and assistance to Member States in enhancing the operational safety of nuclear power plants (NPPs). Simultaneously, the IAEA has encouraged self-assessment and review by Member States of their own nuclear power plants to continuously improve nuclear safety. Currently, some utilities have been implementing safety review programmes to independently review their own plants. Corporate or national operational safety review programmes may be compliance or performance based. Successful utilities have found that both techniques are necessary to provide assurance that (i) as a minimum the NPP meets specific corporate and legal requirements and (ii) management at the NPP is encouraged to pursue continuous improvement principles. These programmes can bring nuclear safety benefits to the plants and utilities. The IAEA has conducted two pilot missions to assess the effectiveness of the operational review programme. Based on these missions and on the experience gained during OSART missions, this document has been developed to provide guidance on and broaden national/corporate safety review programmes in Member States, and to assist in maximizing their benefits. These guidelines are intended primarily for the IAEA team to conduct assessment of a national/corporate safety review programme. However, this report may also be used by a country or utility to establish its own national/corporate safety review programme. The guidelines may likewise be used for self-assessment or for establishing a baseline when benchmarking other safety review programmes. This report consists of four parts. Section 2 addresses the planning and preparation of an IAEA assessment mission and Sections 3 and 4 deal with specific guidelines for conducting the assessment mission itself

The management-retrieval code of the sub-library of atomic mass and characteristic constants for nuclear ground state

International Nuclear Information System (INIS)

Su Zongdi; Ma Lizhen

1994-01-01

The management code of the sub-library of atomic mass and characteristic constants for nuclear ground state (MCC) is used for displaying the basic information on the MCC sub-library on the screen, and retrieving the required data. The MCC data file contains the data of 4800 nuclides ranging from Z 0, A = 1 to Z = 122, A = 318. The MCC sub-library has been set up at Chinese Nuclear Data Center (CNDC), and has been used to provide the atomic masses and characteristic constants of nuclear ground states for the nuclear model calculation, nuclear data evaluations and other fields

Analytic model for surface ground motion with spall induced by underground nuclear tests

International Nuclear Information System (INIS)

MacQueen, D.H.

1982-04-01

This report provides a detailed presentation and critique of a model used to characterize the surface ground motion following a contained, spalling underground nuclear explosion intended for calculation of the resulting atmospheric acoustic pulse. Some examples of its use are included. Some discussion of the general approach of ground motion model parameter extraction, not dependent on the specific model, is also presented

Nuclear safety review for the year 2002

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-08-01

The Nuclear Safety Review reports on worldwide efforts to strengthen nuclear, radiation and transport safety and the safety of radioactive waste management. The final version of the Nuclear Safety Review for the Year 2002 was prepared in the light of the discussion by the Board of Governors in March 2002. This report presents an overview of the current issues and trends in nuclear, radiation, transport and radioactive waste safety at the end of 2002. This overview is supported by a more detailed factual account of safety-related events and issues worldwide during 2002. National authorities and the international community continued to reflect and act upon the implications of the events of II September 2001 for nuclear, radiation, transport and waste safety. In the light of this, the Agency has decided to transfer the organizational unit on nuclear security from the Department of Safeguards to the Department of Nuclear Safety (which thereby becomes the Department of Nuclear Safety and Security). By better exploiting the synergies between safety and security and promoting further cross-fertilization of approaches, the Agency is trying to help build up mutually reinforcing global regimes of safety and security. However, the Nuclear Safety Review for the Year 2002 addresses only those areas already in the safety programme. This short analytical overview is supported by a second part (corresponding to Part I of the Nuclear Safety Reviews of previous years), which describes significant safety-related events and issues worldwide during 2002. A Draft Nuclear Safety Review for the Year 2002 was submitted to the March 2003 session of the Board of Governors in document GOV/2003/6.

Nuclear safety review for the year 2002

International Nuclear Information System (INIS)

2003-08-01

The Nuclear Safety Review reports on worldwide efforts to strengthen nuclear, radiation and transport safety and the safety of radioactive waste management. The final version of the Nuclear Safety Review for the Year 2002 was prepared in the light of the discussion by the Board of Governors in March 2002. This report presents an overview of the current issues and trends in nuclear, radiation, transport and radioactive waste safety at the end of 2002. This overview is supported by a more detailed factual account of safety-related events and issues worldwide during 2002. National authorities and the international community continued to reflect and act upon the implications of the events of II September 2001 for nuclear, radiation, transport and waste safety. In the light of this, the Agency has decided to transfer the organizational unit on nuclear security from the Department of Safeguards to the Department of Nuclear Safety (which thereby becomes the Department of Nuclear Safety and Security). By better exploiting the synergies between safety and security and promoting further cross-fertilization of approaches, the Agency is trying to help build up mutually reinforcing global regimes of safety and security. However, the Nuclear Safety Review for the Year 2002 addresses only those areas already in the safety programme. This short analytical overview is supported by a second part (corresponding to Part I of the Nuclear Safety Reviews of previous years), which describes significant safety-related events and issues worldwide during 2002. A Draft Nuclear Safety Review for the Year 2002 was submitted to the March 2003 session of the Board of Governors in document GOV/2003/6

Human Factors Engineering Review Model for advanced nuclear power reactors

International Nuclear Information System (INIS)

O'Hara, J.; Higgins, J.; Goodman, C.; Galletti, G.: Eckenrode, R.

1993-01-01

One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model's rationale, scope, objectives, development, general characteristics. and application

Standard Review Plan for the review of safety analysis reports for nuclear power plants, updates. Irregular repts

International Nuclear Information System (INIS)

1980-01-01

The Standard Review Plan (SRP) is prepared for the guidance of staff reviewers in the Office of Nuclear Reactor Regulation in performing safety reviews of applications to construct or operate nuclear power plants. The principal purpose of the SRP is to assure the quality and uniformity of staff reviews, and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. It is also a purpose of the SRP to make information about regulatory matters widely available and to improve communication and understanding of the staff review process by interested members of the public and the nuclear power industry. The Standard Review Plan is written so as to cover a variety of site conditions and plant designs. Each section is written to provide the complete procedure and all acceptance criteria for all of the areas of review pertinent to that section. However, for any given application, the staff reviewers may select and emphasize particular aspects of each SRP section as is appropriate for the application

On development and improvement of evaluation techniques for seismic ground motion

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Issues regarding evaluation of active fault and ground motion for formulation of design basis ground motion (Ss) were prescribed in 'NSC seismic and tsunami safety reviewing manual' in 2012. Moreover, Nuclear Regulation Authority (NRA) is establishing the new seismic safety guideline. In this theme following four subjects were investigated to resolve the important problems for ground motion evaluation, (1) advanced evaluation of ground motion using fault model and uncertainty; (2) improving evaluation of ground motion using attenuation relation of response spectrum; (3) development of advanced and generic techniques for ground motion observation and observation tool in deep borehole; (4) improving the evaluation of site effect and seismic wave propagation characteristics. In addition as emergency requirements from NRA following two subjects were also investigated; (5) hazard evaluation development on fault displacement; (6) ground motion evaluation at near-by source location. Obtained results will be reflected not only in the domestic guideline established by NRA but in the national safety review and also in the safety standard guidelines of the International Atomic Energy Agency (IAEA) through its Extra-Budgetary Program (EBP), thereby contributing to technical cooperation in global nuclear seismic safety. (author)

Measurement of Walking Ground Reactions in Real-Life Environments: A Systematic Review of Techniques and Technologies.

Science.gov (United States)

Shahabpoor, Erfan; Pavic, Aleksandar

2017-09-12

Monitoring natural human gait in real-life environments is essential in many applications, including quantification of disease progression, monitoring the effects of treatment, and monitoring alteration of performance biomarkers in professional sports. Nevertheless, developing reliable and practical techniques and technologies necessary for continuous real-life monitoring of gait is still an open challenge. A systematic review of English-language articles from scientific databases including Scopus, ScienceDirect, Pubmed, IEEE Xplore, EBSCO and MEDLINE were carried out to analyse the 'accuracy' and 'practicality' of the current techniques and technologies for quantitative measurement of the tri-axial walking ground reactions outside the laboratory environment, and to highlight their strengths and shortcomings. In total, 679 relevant abstracts were identified, 54 full-text papers were included in the paper and the quantitative results of 17 papers were used for meta-analysis and comparison. Three classes of methods were reviewed: (1) methods based on measured kinematic data; (2) methods based on measured plantar pressure; and (3) methods based on direct measurement of ground reactions. It was found that all three classes of methods have competitive accuracy levels with methods based on direct measurement of the ground reactions showing highest accuracy while being least practical for long-term real-life measurement. On the other hand, methods that estimate ground reactions using measured body kinematics show highest practicality of the three classes of methods reviewed. Among the most prominent technical and technological challenges are: (1) reducing the size and price of tri-axial load-cells; (2) improving the accuracy of orientation measurement using IMUs; (3) minimizing the number and optimizing the location of required IMUs for kinematic measurement; (4) increasing the durability of pressure insole sensors, and (5) enhancing the robustness and versatility of the

Measurement of Walking Ground Reactions in Real-Life Environments: A Systematic Review of Techniques and Technologies

Directory of Open Access Journals (Sweden)

Erfan Shahabpoor

2017-09-01

Full Text Available Monitoring natural human gait in real-life environments is essential in many applications, including quantification of disease progression, monitoring the effects of treatment, and monitoring alteration of performance biomarkers in professional sports. Nevertheless, developing reliable and practical techniques and technologies necessary for continuous real-life monitoring of gait is still an open challenge. A systematic review of English-language articles from scientific databases including Scopus, ScienceDirect, Pubmed, IEEE Xplore, EBSCO and MEDLINE were carried out to analyse the ‘accuracy’ and ‘practicality’ of the current techniques and technologies for quantitative measurement of the tri-axial walking ground reactions outside the laboratory environment, and to highlight their strengths and shortcomings. In total, 679 relevant abstracts were identified, 54 full-text papers were included in the paper and the quantitative results of 17 papers were used for meta-analysis and comparison. Three classes of methods were reviewed: (1 methods based on measured kinematic data; (2 methods based on measured plantar pressure; and (3 methods based on direct measurement of ground reactions. It was found that all three classes of methods have competitive accuracy levels with methods based on direct measurement of the ground reactions showing highest accuracy while being least practical for long-term real-life measurement. On the other hand, methods that estimate ground reactions using measured body kinematics show highest practicality of the three classes of methods reviewed. Among the most prominent technical and technological challenges are: (1 reducing the size and price of tri-axial load-cells; (2 improving the accuracy of orientation measurement using IMUs; (3 minimizing the number and optimizing the location of required IMUs for kinematic measurement; (4 increasing the durability of pressure insole sensors, and (5 enhancing the robustness and

Evaluation of vibratory ground motion at nuclear power plant sites

International Nuclear Information System (INIS)

Hofmann, R.B.; Greeves, J.T.

1978-01-01

The evaluation of vibratory ground motion at nuclear power plant sites requires the cooperative effort of scientists and engineers in several disciplines. These include seismology, geology, geotechnical engineering and structural engineering. The Geosciences Branch of the NRC Division of Site Safety and Environmental Analysis includes two sections, the Geology/Seismology Section and the Geotechnical Engineering Section

A risk-based review of Instrument Air systems at nuclear power plants

International Nuclear Information System (INIS)

DeMoss, G.; Lofgren, E.; Rothleder, B.; Villeran, M.; Ruger, C.

1990-01-01

The broad objective of this analysis was to provide risk-based information to help focus regulatory actions related to Instrument Air (IA) systems at operating nuclear power plants. We first created an extensive data base of summarized and characterized IA-related events that gave a qualitative indication of the nature and severity of these events. Additionally, this data base was used to calculate the frequencies of certain events, which were used in the risk analysis. The risk analysis consisted of reviewing published PRAs and NRC Accident Sequence Precursor reports for IA-initiated accident sequences, IA interactions with frontline systems, and IA-related risk significant events. Sensitivity calculations were performed when possible. Generically, IA was found to contribute less to total risk than many safety systems; however, specific design weaknesses in safety systems, non-safety systems, and the IA system were found to be significant in risk. 22 refs., 13 figs., 24 tabs

Summary of ground motion prediction results for Nevada Test Site underground nuclear explosions related to the Yucca Mountain project

International Nuclear Information System (INIS)

Walck, M.C.

1996-10-01

This report summarizes available data on ground motions from underground nuclear explosions recorded on and near the Nevada Test Site, with emphasis on the ground motions recorded at stations on Yucca Mountain, the site of a potential high-level radioactive waste repository. Sandia National Laboratories, through the Weapons Test Seismic Investigations project, collected and analyzed ground motion data from NTS explosions over a 14-year period, from 1977 through 1990. By combining these data with available data from earlier, larger explosions, prediction equations for several ground motion parameters have been developed for the Test Site area for underground nuclear explosion sources. Also presented are available analyses of the relationship between surface and downhole motions and spectra and relevant crustal velocity structure information for Yucca Mountain derived from the explosion data. The data and associated analyses demonstrate that ground motions at Yucca Mountain from nuclear tests have been at levels lower than would be expected from moderate to large earthquakes in the region; thus nuclear explosions, while located relatively close, would not control seismic design criteria for the potential repository

Summary of ground motion prediction results for Nevada Test Site underground nuclear explosions related to the Yucca Mountain project

Energy Technology Data Exchange (ETDEWEB)

Walck, M.C.

1996-10-01

This report summarizes available data on ground motions from underground nuclear explosions recorded on and near the Nevada Test Site, with emphasis on the ground motions recorded at stations on Yucca Mountain, the site of a potential high-level radioactive waste repository. Sandia National Laboratories, through the Weapons Test Seismic Investigations project, collected and analyzed ground motion data from NTS explosions over a 14-year period, from 1977 through 1990. By combining these data with available data from earlier, larger explosions, prediction equations for several ground motion parameters have been developed for the Test Site area for underground nuclear explosion sources. Also presented are available analyses of the relationship between surface and downhole motions and spectra and relevant crustal velocity structure information for Yucca Mountain derived from the explosion data. The data and associated analyses demonstrate that ground motions at Yucca Mountain from nuclear tests have been at levels lower than would be expected from moderate to large earthquakes in the region; thus nuclear explosions, while located relatively close, would not control seismic design criteria for the potential repository.

Standard Review Plan for the review of safety analysis reports for nuclear power plants: LWR edition

International Nuclear Information System (INIS)

1987-06-01

The Standard Review Plan (SRP) is prepared for the guidance of staff reviewers in the Office of Nuclear Reactor Regulation in performing safety reviews of applications to construct or operate nuclear power plants. The principal purpose of the SRP is to assure the quality and uniformity of staff reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. It is also a purpose of the SRP to make information about regulatory matters widely available and to improve communication and understanding of the staff review process by interested members of the public and the nuclear power industry. The safety review is primarily based on the information provided by an applicant in a Safety Analysis Report (SAR). The SAR must be sufficiently detailed to permit the staff to determine whether the plant can be built and operated without undue risk to the health and safety of the public. The SAR is the principal document in which the applicant provides the information needed to understand the basis upon which this conclusion has been reached. The individual SRP sections address, in detail, who performs the review, the matters that are reviewed, the basis for review, how the review is accomplished, and the conclusions that are sought. The safety review is performed by 25 primary branches. One of the objectives of the SRP is to assign the review responsibilities to the various branches and to define the sometimes complex interfaces between them. Each SRP section identifies the branch that has the primary review responsibility for that section. In some review areas the primary branch may require support, and the branches that are assigned these secondary review responsibilities are also identified for each SRP section

Nuclear Safety Review for 2015

International Nuclear Information System (INIS)

2015-06-01

The Nuclear Safety Review 2015 focuses on the dominant nuclear safety trends, issues and challenges in 2014. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: improving radiation, transport and waste safety; strengthening safety in nuclear installations; enhancing emergency preparedness and response (EPR); and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the Agency’s safety standards. The global nuclear community continued to make steady progress in improving nuclear safety throughout the world in 2014; and, the Agency and its Member States continued to implement the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”), which was endorsed by the General Conference in 2011 after the Fukushima Daiichi accident in March 2011. • Significant progress has been made in reviewing and revising various Agency’s safety standards in areas such as management of radioactive waste, design basis hazard levels, protection of nuclear power plants (NPPs) against severe accidents, design margins to avoid cliff edge effects, multiple facilities at one site, and strengthening the prevention of unacceptable radiological consequences to the public and the environment, communications and EPR. In addition, the Guidelines for Drafting IAEA Safety Standards and Nuclear Security Series Publications was issued in July 2014.• The Agency continued to analyse the relevant technical aspects of the Fukushima Daiichi accident and to share and disseminate lessons learned to the wider nuclear community. In 2014, the Agency organized two international experts’ meetings (IEMs), one on radiation protection and one on severe accident management. Reports from previous IEMs were also published in 2014: IAEA Report on Human and Organizational Factors in Nuclear

Studies of Geomagnetic Pulsations Using Magnetometer Data from the CHAMP Low-Earth-Orbit Satellite and Ground-Based Stations: a Review

Directory of Open Access Journals (Sweden)

P R Sutcliffe

2011-06-01

Full Text Available We review research on geomagnetic pulsations carried out using magnetic field measurements from the CHAMP low-Earth-orbit (LEO satellite and ground-based stations in South Africa and Hungary. The high quality magnetic field measurements from CHAMP made it possible to extract and clearly resolve Pi2 and Pc3 pulsations in LEO satellite data. Our analyses for nighttime Pi2 pulsations are indicative of a cavity mode resonance. However, observations of daytime Pi2 pulsation events identified in ground station data show no convincing evidence of their occurrence in CHAMP data. We also studied low-latitude Pc3 pulsations and found that different types of field line resonant structure occur, namely discrete frequencies driven by a narrow band source and L-dependent frequencies driven by a broad band source.

Nuclear Fuel Safety Criteria Technical Review - Second edition

International Nuclear Information System (INIS)

Beck, Winfried; Blanpain, Patrick; Fuketa, Toyoshi; Gorzel, Andreas; Hozer, Zoltan; Kamimura, Katsuichiro; Koo, Yang-Hyun; Maertens, Dietmar; Nechaeva, Olga; Petit, Marc; Rehacek, Radomir; Rey-Gayo, Jose Maria; Sairanen, Risto; Sonnenburg, Heinz-Guenther; Valach, Mojmir; Waeckel, Nicolas; Yueh, Ken; Zhang, Jinzhao; Voglewede, John

2012-01-01

Most of the current nuclear fuel safety criteria were established during the 1960's and early 1970's. Although these criteria were validated against experiments with fuel designs available at that time, a number of tests were based on unirradiated fuels. Additional verification was performed as these designs evolved, but mostly with the aim of showing that the new designs adequately complied with existing criteria, and not to establish new limits. In 1996, the OECD Nuclear Energy Agency (NEA) reviewed existing fuel safety criteria, focusing on new fuel and core designs, new cladding materials and industry manufacturing processes. The results were published in the Nuclear Fuel Safety Criteria Technical Review of 2001. The NEA has since re-examined the criteria. A brief description of each criterion and its rationale are presented in this second edition, which will be of interest to both regulators and industry (fuel vendors, utilities)

Review of off-site emergency preparedness and response plan of Indian NPPs based on experience of Fukushima nuclear accident

International Nuclear Information System (INIS)

Singh, Hukum; Dash, M.; Shukla, Vikas; Vijayan, P.; Krishnamurthy, P.R.

2012-01-01

Nuclear power plants in India are designed, constructed and operated based on the principle of the highest priority to nuclear safety. To deal with any unlikely situation of radiological emergency, the emergency preparedness and response plans are ensured to be in place at all NPPs prior to their commissioning. These plans are periodically reviewed and tested by conducting emergency exercise with the participation of various agencies such as Nuclear Power Corporation of India Limited, NDMA, district authorities, regulatory body and general public. On March 11, 2011 an earthquake of magnitude 9.0 hit the Fukushima Dai-ichi and Dai-ni followed by tsunami waves of height 15 meters above reference sea level. This resulted in large scale release of radioactive material from Fukushima Dai-ichi NPS. This led to the evacuation of a large number of people from the areas surrounding the affected nuclear power plants. The event was rated as level 7 event in International Nuclear Event Scale (INES). The event also revealed the challenges in handling radiological emergency situation in adverse environmental conditions, The experience of managing radiological emergency situation during Fukushima nuclear accident provides opportunities to review and improve emergency preparedness and response programme. The present paper presents the chronology of the emergency situation, challenges faced and handled in Fukushima. Even though the possibility of a Fukushima type nuclear accident in India is very remote due to the low probability of a high intensity earthquake followed by tsunami at NPP sites, the efforts needs to be initiated from the regulatory point of view for an effective Nuclear and Radiological Emergency Preparedness and Response Plans. The Emergency Preparedness and Response Plans of NPP sites were reviewed in the light of unique challenges of accident at Fukushima. It is realized that multi unit events are the realities that must be addressed as part of Emergency

Review of off-site emergency preparedness and response plan of Indian NPPs based on experience of Fukushima nuclear accident

Energy Technology Data Exchange (ETDEWEB)

Singh, Hukum; Dash, M.; Shukla, Vikas; Vijayan, P.; Krishnamurthy, P.R., E-mail: vshukla@aerb.gov.in [Operating Plants Safety Division, Atomic Energy Regulatory Board, Mumbai (India)

2012-07-01

Nuclear power plants in India are designed, constructed and operated based on the principle of the highest priority to nuclear safety. To deal with any unlikely situation of radiological emergency, the emergency preparedness and response plans are ensured to be in place at all NPPs prior to their commissioning. These plans are periodically reviewed and tested by conducting emergency exercise with the participation of various agencies such as Nuclear Power Corporation of India Limited, NDMA, district authorities, regulatory body and general public. On March 11, 2011 an earthquake of magnitude 9.0 hit the Fukushima Dai-ichi and Dai-ni followed by tsunami waves of height 15 meters above reference sea level. This resulted in large scale release of radioactive material from Fukushima Dai-ichi NPS. This led to the evacuation of a large number of people from the areas surrounding the affected nuclear power plants. The event was rated as level 7 event in International Nuclear Event Scale (INES). The event also revealed the challenges in handling radiological emergency situation in adverse environmental conditions, The experience of managing radiological emergency situation during Fukushima nuclear accident provides opportunities to review and improve emergency preparedness and response programme. The present paper presents the chronology of the emergency situation, challenges faced and handled in Fukushima. Even though the possibility of a Fukushima type nuclear accident in India is very remote due to the low probability of a high intensity earthquake followed by tsunami at NPP sites, the efforts needs to be initiated from the regulatory point of view for an effective Nuclear and Radiological Emergency Preparedness and Response Plans. The Emergency Preparedness and Response Plans of NPP sites were reviewed in the light of unique challenges of accident at Fukushima. It is realized that multi unit events are the realities that must be addressed as part of Emergency

The nuclear review

International Nuclear Information System (INIS)

Robinson, C.

1995-01-01

Evidence in favour of privatisation which was submitted to the UK government's review of the nuclear industry is summarised. Only if capital markets judge proposals for new nuclear stations and they operate within competitive markets, can their economic and commercial viability be determined. The problem of state ownership is that politicians' time horizons are too short for an industry that must take a long view, unless standards are set by competitors, costs are likely to rise. Magnox stations, however, should remain in public ownership though to gain efficiency their operation should be contracted out. The rest of Nuclear Electric and Scottish Nuclear should be privatised as generation companies but should not be tied to nuclear generation. Current protective arrangements should be removed as soon as possible. Among the benefits expected from the entry of two formidable new companies into the privatised electricity are efficiency gains, price reductions, a stimulus to entrepeneurship and innovation, and more straightforward regulation. (UK)

PROBABILISTIC SEISMIC ASSESSMENT OF BASE-ISOLATED NPPS SUBJECTED TO STRONG GROUND MOTIONS OF TOHOKU EARTHQUAKE

Directory of Open Access Journals (Sweden)

AHMER ALI

2014-10-01

Full Text Available The probabilistic seismic performance of a standard Korean nuclear power plant (NPP with an idealized isolation is investigated in the present work. A probabilistic seismic hazard analysis (PSHA of the Wolsong site on the Korean peninsula is performed by considering peak ground acceleration (PGA as an earthquake intensity measure. A procedure is reported on the categorization and selection of two sets of ground motions of the Tohoku earthquake, i.e. long-period and common as Set A and Set B respectively, for the nonlinear time history response analysis of the base-isolated NPP. Limit state values as multiples of the displacement responses of the NPP base isolation are considered for the fragility estimation. The seismic risk of the NPP is further assessed by incorporation of the rate of frequency exceedance and conditional failure probability curves. Furthermore, this framework attempts to show the unacceptable performance of the isolated NPP in terms of the probabilistic distribution and annual probability of limit states. The comparative results for long and common ground motions are discussed to contribute to the future safety of nuclear facilities against drastic events like Tohoku.

Probabilistic seismic assessment of base-isolated NPPs subjected to strong ground motions of Tohoku earthquake

Energy Technology Data Exchange (ETDEWEB)

Ali, Ahmer; Hayah, Nadin Abu; Kim, Doo Kie [Dept. of Civil and Environmental Engineering, Kunsan National University, Kunsan (Korea, Republic of); Cho, Sung Gook [R and D Center, JACE KOREA Company, Gyeonggido (Korea, Republic of)

2014-10-15

The probabilistic seismic performance of a standard Korean nuclear power plant (NPP) with an idealized isolation is investigated in the present work. A probabilistic seismic hazard analysis (PSHA) of the Wolsong site on the Korean peninsula is performed by considering peak ground acceleration (PGA) as an earthquake intensity measure. A procedure is reported on the categorization and selection of two sets of ground motions of the Tohoku earthquake, i.e. long-period and common as Set A and Set B respectively, for the nonlinear time history response analysis of the base-isolated NPP. Limit state values as multiples of the displacement responses of the NPP base isolation are considered for the fragility estimation. The seismic risk of the NPP is further assessed by incorporation of the rate of frequency exceedance and conditional failure probability curves. Furthermore, this framework attempts to show the unacceptable performance of the isolated NPP in terms of the probabilistic distribution and annual probability of limit states. The comparative results for long and common ground motions are discussed to contribute to the future safety of nuclear facilities against drastic events like Tohoku.

Nuclear Energy Literature Review

International Nuclear Information System (INIS)

Simic, Z.; Wastin, F.

2016-01-01

In the light of five years after a major accident at the Fukushima Daiichi nuclear power plant it is interesting to make nuclear energy related literature review. There is a number of accidents related reports from all major international institutions (like the IAEA and OECD NEA) and research organizations have drawn conclusions and lessons to learn from this terrible accident. These reports are the result of expert and scientific analyses carried out during these five years and they present ideal sources for both understanding what has happened and what can be learned in order to avoid and mitigate effects of such events in the future. From a wider perspective it is also interesting to analyze the impact on research and development (R and D) activities. This literature review is performed with hope to gain some useful insights from the analysis of the volume and topics in all research activities related to the Fukushima accident and nuclear energy (NE) altogether. This kind of review should at least provide an overview of trends and provide base for better planning of future activities. This paper analyzes the published NE related research of over more than 50 years with focus on three major nuclear accidents (TMI, Chernobyl and Fukushima). It has been performed using Scopus tools and database, and mainly focuses on statistics related to the subjects, countries, keywords and type of publishing. It also analyses how responsive is nuclear energy related R and D regarding the volume and subjects, and how is that research spread among most active countries. Nuclear power accidents influence increase and change of research. Both accidents, Chernobyl and Fukushima had maximum share in all nuclear power related papers at similar yearly level (9 percent in 1991 and 12 percent in 2015 respectively). TMI peaked at the 2.5 percent share in 1982. Engineering is the most frequent subjects for TMI and cumulative NE related publishing. Medicine and environmental science subjects

Concept study of a hydrogen containment process during nuclear thermal engine ground testing

Directory of Open Access Journals (Sweden)

Ten-See Wang

Full Text Available A new hydrogen containment process was proposed for ground testing of a nuclear thermal engine. It utilizes two thermophysical steps to contain the hydrogen exhaust. First, the decomposition of hydrogen through oxygen-rich combustion at higher temperature; second, the recombination of remaining hydrogen with radicals at low temperature. This is achieved with two unit operations: an oxygen-rich burner and a tubular heat exchanger. A computational fluid dynamics methodology was used to analyze the entire process on a three-dimensional domain. The computed flammability at the exit of the heat exchanger was less than the lower flammability limit, confirming the hydrogen containment capability of the proposed process. Keywords: Hydrogen decomposition reactions, Hydrogen recombination reactions, Hydrogen containment process, Nuclear thermal propulsion, Ground testing

Nuclear Safety Review for the Year 2012

International Nuclear Information System (INIS)

2012-07-01

The Nuclear Safety Review for the Year 2012 contains an analytical overview of the dominant trends, issues and challenges worldwide in 2011 and the Agency's efforts to strengthen the global nuclear safety framework. This year's report also highlights issues and activities related to the accident at the Fukushima Daiichi nuclear power plant. The analytical overview is supported by the Appendix at the end of this document, entitled: The IAEA Safety Standards: Activities during 2011. A draft version of the Nuclear Safety Review for the Year 2012 was submitted to the March 2012 session of the Board of Governors in document GOV/2012/6. The final version of the Nuclear Safety Review for the Year 2012 was prepared in light of the discussions held during the Board of Governors and also of the comments received.

Ground beetles (Coleoptera, Carabidae of the Hanford Nuclear Site in south-central Washington State

Directory of Open Access Journals (Sweden)

Chris Looney

2014-04-01

Full Text Available In this paper we report on ground beetles (Coleoptera: Carabidae collected from the Hanford Nuclear Reservation and Hanford National Monument (together the Hanford Site, which is located in south-central Washington State. The Site is a relatively undisturbed relict of the shrub-steppe habitat present throughout much of the western Columbia Basin before the westward expansion of the United States. Species, localities, months of capture, and capture method are reported for field work conducted between 1994 and 2002. Most species were collected using pitfall traps, although other capture methods were employed. Trapping results indicate the Hanford Site supports a diverse ground beetle community, with over 90% of the 92 species captured native to North America. Four species collected during the study period are newly recorded for Washington State: Bembidion diligens Casey, Calosoma obsoletum Say, Pseudaptinus rufulus (LeConte, and Stenolophus lineola (Fabricius. Based on these data, the Site maintains a diverse ground beetle fauna and, due to its size and diversity of habitats, is an important repository of shrub-steppe biodiversity.

Nitrate Removal from Ground Water: A Review

Directory of Open Access Journals (Sweden)

Archna

2012-01-01

Full Text Available Nitrate contamination of ground water resources has increased in Asia, Europe, United States, and various other parts of the world. This trend has raised concern as nitrates cause methemoglobinemia and cancer. Several treatment processes can remove nitrates from water with varying degrees of efficiency, cost, and ease of operation. Available technical data, experience, and economics indicate that biological denitrification is more acceptable for nitrate removal than reverse osmosis and ion exchange. This paper reviews the developments in the field of nitrate removal processes which can be effectively used for denitrifying ground water as well as industrial water.

Isotopic and spin-nuclear effects in solid hydrogens (Review Article)

Science.gov (United States)

Freiman, Yuri A.; Crespo, Yanier

2017-12-01

The multiple isotopic family of hydrogens (H2, HD, D2, HT, DT, T2) due to large differences in the de Boer quantum parameter and inertia moments displays a diversity of pronounced quantum isotopic solid-state effects. The homonuclear members of this family (H2, D2, T2) due to the permutation symmetry are subjects of the constraints of quantum mechanics which link the possible rotational states of these molecules to their total nuclear spin giving rise to the existence of two spin-nuclear modifications, ortho- and parahydrogens, possessing substantially different properties. Consequently, hydrogen solids present an unique opportunity for studying both isotope and spin-nuclear effects. The rotational spectra of heteronuclear hydrogens (HD, HT, DT) are free from limitations imposed by the permutation symmetry. As a result, the ground state of these species in solid state is virtually degenerate. The most dramatic consequence of this fact is an effect similar to the Pomeranchuk effect in 3He which in the case of the solid heteronuclear hydrogens manifests itself as the reentrant broken symmetry phase transitions. In this review article we discuss thermodynamic and kinetic effects pertaining to different isotopic and spin-nuclear species, as well as problems that still remain to be solved.

Overview of Light Hydrogen-Based Low Energy Nuclear Reactions

Science.gov (United States)

Miley, George H.; Shrestha, Prajakti J.

This paper reviews light water and hydrogen-based low-energy nuclear reactions (LENRs) including the different methodologies used to study these reactions and the results obtained. Reports of excess heat production, transmutation reactions, and nuclear radiation emission are cited. An aim of this review is to present a summary of the present status of light water LENR research and provide some insight into where this research is heading.

Nuclear Safety Review for the Year 2003

International Nuclear Information System (INIS)

2004-08-01

The Nuclear Safety Review reports on worldwide efforts to strengthen nuclear, radiation and transport safety and the safety of radioactive waste management. In line with the suggestions made by the Board of Governors in March 2002, the first part is more analytical and less descriptive. This short analytical overview is supported by a second part, which describes significant safety related events and issues worldwide during 2003. A Draft Nuclear Safety Review for the Year 2003 was submitted to the March 2004 session of the Board of Governors in document GOV/2004/3. The final version of the Nuclear Safety Review for the Year 2003 was prepared in the light of the discussion by the Board.

Nuclear Safety Review for 2014

International Nuclear Information System (INIS)

2014-07-01

The Nuclear Safety Review 2014 focuses on the dominant nuclear safety trends, issues and challenges in 2013. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: strengthening safety in nuclear installations; improving radiation, transport and waste safety; enhancing emergency preparedness and response (EPR); improving regulatory infrastructure and effectiveness; and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards, and activities relevant to the Agency’s safety standards. The global nuclear community has made steady and continuous progress in strengthening nuclear safety in 2013, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”) and reported in Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2013/8-GC(57)/INF/5), and the Supplementary Information to that report and Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2014/2). • Significant progress continues to be made in several key areas, such as assessments of safety vulnerabilities of nuclear power plants (NPPs), strengthening of the Agency’s peer review services, improvements in EPR capabilities, strengthening and maintaining capacity building, and protecting people and the environment from ionizing radiation. The progress that has been made in these and other areas has contributed to the enhancement of the global nuclear safety framework. • Significant progress has also been made in reviewing the Agency’s safety standards, which continue to be widely applied by regulators, operators and the nuclear industry in general, with increased attention and focus on vitally important areas such as design and operation of NPPs, protection of NPPs against severe accidents, and EPR. • The Agency continued to

US nuclear safety review and experience

International Nuclear Information System (INIS)

Gilinsky, V.

1977-01-01

The nuclear safety review of commercial nuclear power reactors has changed over the years from the relatively simple review of Dresden 1 in 1955 to the highly complex and sophisticated regulatory process which characterizes today's reviews. Four factors have influenced this evolution: (1) maturing of the technology and industry; (2) development of the regulatory process and associated staff; (3) feedback of operating experience; and (4) public awareness and participation. The NRC's safety review responsibilities start before an application is tendered and end when the plant is decommissioned. The safety review for reactor licensing is a comprehensive, two-phase process designed to assure that all the established conservative acceptance criteria are satisfied. Operational safety is assured through a strong inspection and enforcement program which includes shutting down operating facilities when necessary to protect the health and safety of the public. The safety of operating reactors is further insured through close regulation of license changes and selective backfitting of new regulatory requirements. An effective NRC standards development program has been implemented and coordinates closely with the national standards program. A confirmatory safety research program has been developed. Both of these efforts are invaluable to the nuclear safety review because they provide the staff with key tools needed to carry out its regulatory responsibilities. Both have been given increased emphasis since the formation of the NRC in 1975. The safety review process will continue to evolve, but changes will be slower and more deliberate. It will be influenced by standardization, early site reviews and development of advanced reactor concepts. New legislation may make possible changes which will simplify and shorten the regulatory process. Certainly the experience provided by the increasing number and types of operating plants will have a very strong impact on future trends in the

Comparison of the inelastic response of steel building frames to strong earthquake and underground nuclear explosion ground motion

International Nuclear Information System (INIS)

Murray, R.C.; Tokarz, F.J.

1976-01-01

Analytic studies were made of the adequacy of simulating earthquake effects at the Nevada Test Site for structural testing purposes. It is concluded that underground nuclear explosion ground motion will produce inelastic behavior and damage comparable to that produced by strong earthquakes. The generally longer duration of earthquakes compared with underground nuclear explosions does not appear to significantly affect the structural behavior of the building frames considered. A comparison of maximum ductility ratios, maximum story drifts, and maximum displacement indicate similar structural behavior for both types of ground motion. Low yield (10 - kt) underground nuclear explosions are capable of producing inelastic behavior in large structures. Ground motion produced by underground nuclear explosions can produce inelastic earthquake-like effects in large structures and could be used for testing large structures in the inelastic response regime. The Nevada Test Site is a feasible earthquake simulator for testing large structures

Human factors design review guidelines for advanced nuclear control room technologies

International Nuclear Information System (INIS)

O'Hara, J.; Brown, W.; Granda, T.; Baker, C.

1991-01-01

Advanced control rooms (ACRs) for future nuclear power plants are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes the rationale, general approach, and initial development of an NRC Advanced Control Room Design Review Guideline. 20 refs., 1 fig

Review of nuclear waste isolation

International Nuclear Information System (INIS)

Richard, B.H.

1978-06-01

On Jun 22 and 23, 1978, Rockwell Hanford Operations assembled a committee of their personnel, subcontractors, and representatives of other waste isolation programs for a review of nuclear waste isolation. Appendix A lists the participants and their affiliations; Appendix B indicates the agenda. The purpose of the review was to gather experts in the areas pertaining to isolation of nuclear waste to discuss three basic issues that must be addressed in isolation studies. These were: the paths of transport to the biosphere; the barriers needed for containment; and the isolation time necessary for each radioactive isotope. In that these issues are media dependent, the basalt medium was emphasized. Conclusions of the review are described

Study of polonium isotopes ground state properties by simultaneous atomic- and nuclear-spectroscopy

CERN Multimedia

Koester, U H; Kalaninova, Z; Imai, N

2007-01-01

We propose to systematically study the ground state properties of neutron deficient $^{192-200}$Po isotopes by means of in-source laser spectroscopy using the ISOLDE laser ion source coupled with nuclear spectroscopy at the detection setup as successfully done before by this collaboration with neutron deficient lead isotopes. The study of the change in mean square charge radii along the polonium isotope chain will give an insight into shape coexistence above the mid-shell N = 104 and above the closed shell Z = 82. The hyperfine structure of the odd isotopes will also allow determination of the nuclear spin and the magnetic moment of the ground state and of any identifiable isomer state. For this study, a standard UC$_{x}$ target with the ISOLDE RILIS is required for 38 shifts.

Ground-based remote sensing profiling and numerical weather prediction model to manage nuclear power plants meteorological surveillance in Switzerland

Directory of Open Access Journals (Sweden)

B. Calpini

2011-08-01

Full Text Available The meteorological surveillance of the four nuclear power plants in Switzerland is of first importance in a densely populated area such as the Swiss Plateau. The project "Centrales Nucléaires et Météorologie" CN-MET aimed at providing a new security tool based on one hand on the development of a high resolution numerical weather prediction (NWP model. The latter is providing essential nowcasting information in case of a radioactive release from a nuclear power plant in Switzerland. On the other hand, the model input over the Swiss Plateau is generated by a dedicated network of surface and upper air observations including remote sensing instruments (wind profilers and temperature/humidity passive microwave radiometers. This network is built upon three main sites ideally located for measuring the inflow/outflow and central conditions of the main wind field in the planetary boundary layer over the Swiss Plateau, as well as a number of surface automatic weather stations (AWS. The network data are assimilated in real-time into the fine grid NWP model using a rapid update cycle of eight runs per day (one forecast every three hours. This high resolution NWP model has replaced the former security tool based on in situ observations (in particular one meteorological mast at each of the power plants and a local dispersion model. It is used to forecast the dynamics of the atmosphere in the planetary boundary layer (typically the first 4 km above ground layer and over a time scale of 24 h. This tool provides at any time (e.g. starting at the initial time of a nuclear power plant release the best picture of the 24-h evolution of the air mass over the Swiss Plateau and furthermore generates the input data (in the form of simulated values substituting in situ observations required for the local dispersion model used at each of the nuclear power plants locations. This paper is presenting the concept and two validation studies as well as the results of an

The value of peer reviews to nuclear plant safety

International Nuclear Information System (INIS)

Subalusky, W.T. Jr.

1994-01-01

On a global basis, the nuclear utility industry has clearly demonstrated the value of peer reviews for improving nuclear safety and overall plant performance. Peer reviews are conducted by small teams of technical experts who review various aspects of plant operation, recognize strengths and recommend improvements, thereby stimulating a positive response to the recommendations. U.S. nuclear utilities initiated the operator-to-operator peer review process first through the Institute of Nuclear Power Operations (INPO). Now, voluntary peer reviews are an important activity of the World Association of Nuclear Operators (WANO). Formed just five years ago. WANO has made significant progress in its key activities of the operator-to-operator exchanges, operating experience exchange, monitoring of plant performance indicators and sharing of good practices worldwide. A fifth activity, peer review on a strictly voluntary basis, is pertinent to this paper

Space weather effects on ground based technology

Science.gov (United States)

Clark, T.

Space weather can affect a variety of forms of ground-based technology, usually as a result of either the direct effects of the varying geomagnetic field, or as a result of the induced electric field that accompanies such variations. Technologies affected directly by geomagnetic variations include magnetic measurements made d ringu geophysical surveys, and navigation relying on the geomagnetic field as a direction reference, a method that is particularly common in the surveying of well-bores in the oil industry. The most obvious technology affected by induced electric fields during magnetic storms is electric power transmission, where the example of the blackout in Quebec during the March 1989 magnetic storm is widely known. Additionally, space weather effects must be taken into account in the design of active cathodic protection systems on pipelines to protect them against corrosion. Long-distance telecommunication cables may also have to be designed to cope with space weather related effects. This paper reviews the effects of space weather in these different areas of ground-based technology, and provides examples of how mitigation against hazards may be achieved. (The paper does not include the effects of space weather on radio communication or satellite navigation systems).

Research on review technology for three key safety factors of periodic safety review (PSR) and its application to Qinshan Nuclear Power Plant

International Nuclear Information System (INIS)

Xu Shoulv; Yao Weida; Dou Yikang; Lin Shaoxuan; Cao Yenan; Zhou Quanfu; Zheng Jiong; Zhang Ming

2009-04-01

In 2001, after 10 years' operation, Qinshan Nuclear Power Plant (Q1) started to carry out periodic safety review (PSR) based on a nuclear safety guideline, Periodic Safety Review for Operational Nuclear Power Plants (HAF0312), issued by National Nuclear Safety Administration of China (NNSA). Entrusted by the owner of Q1, Shanghai Nuclear Engineering Research and Design Institute (SNERDI) implemented reviews of three key safety factors including safety analysis, equipment qualification and ageing. PSR was a challenging work in China at that time and through three years' research and practice, SNERDI summarized a systematic achievement for the review including review methodology, scoping, review contents and implementation steps, etc.. During the process of review for the three safety factors, totally 148 review reports and 341 recommendations for corrections were submitted to Q1. These reports and recommendations have provided guidance for correction actions as follow-up of PSR. This paper focuses on technical aspects to carry out PSR for the above-mentioned three safety factors, including review scoping, contents, methodology and main steps. The review technology and relevant experience can be taken for reference for other NPPs to carry out PSR. (authors)

The nuclear review. Proceedings

International Nuclear Information System (INIS)

Dimson, E.; Staunton, M.; Jeffrey, R.; Robinson, C.; O'Neill, M.

1995-01-01

Four contributions to a seminar held in February 1995 at the University of Surrey on the hearings for the government's review of the future role of nuclear generated electricity in the United Kingdom are brought together in this document. They provide analysis and policy recommendations from the standpoint of the nuclear industry, the political opposition and the academic world. Separate abstracts have been prepared for each paper. (UK)

Using grounded theory as a method for rigorously reviewing literature

NARCIS (Netherlands)

Wolfswinkel, J.; Furtmueller-Ettinger, Elfriede; Wilderom, Celeste P.M.

2013-01-01

This paper offers guidance to conducting a rigorous literature review. We present this in the form of a five-stage process in which we use Grounded Theory as a method. We first probe the guidelines explicated by Webster and Watson, and then we show the added value of Grounded Theory for rigorously

The nuclear review

International Nuclear Information System (INIS)

Hawley, R.

1994-01-01

The United Kingdom Government's Review of the prospects for nuclear power, which commenced in May 1994, has terms of reference in which four key issues are identified. These are: whether privatisation is possible and on what timescale; the most cost-effective management of the public sector's liabilities; whether new nuclear stations can be built on a commercial basis and with private finance; and what particular benefits or disadvantages nuclear power has with respect to diversity, security of supply and environmental impacts. The response of Nuclear Electric to these issues is summarized. The Company believes that the financial obstacles to privatisation which existed when it was established in 1989 have been largely overcome and that privatisation now provides it with the best competitive opportunity in today's electricity market. Significant progress has been made in reducing and quantifying the financial liabilities associated with waste management and reactor decommissioning. To secure its future, Nuclear Electric must be allowed to build new plants to replace the 2500 MW(e) of Magnox capacity which will retire by the end of the century. Longer term wider policy objectives should also take account of the fact that during the last twelve months alone, Nuclear Electric has saved the emission of 60 million tonnes of carbon dioxide. (UK)

Nuclear technology review 2004

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-08-15

The viability and credibility of a wide range of nuclear-based technologies require ready access to high-quality atomic, molecular and nuclear data. The demands of new nuclear technologies continue to determine the direction(s) of future data development, including the requirements for data that address innovative fuel cycles, accelerator-driven systems, nuclear incineration, fusion devices, diagnostic and therapeutic medical treatment by radiation, optimization of medical isotope production, non-destructive materials testing, radiation analytical techniques, minerals exploration and land-mine detection. Some recent data development projects with diverse applications are a search engine for Atomic and Molecular data to permit simultaneous data retrieval from a number of different sources for both numerical and bibliographic databases to aid designers. For over 50 years, research reactors have made valuable contributions to the development of nuclear power, basic science, materials development, radioisotope production for medicine and industry, and education and training. They remain core experimental instruments. As of June 2004, 672 research reactors are recorded in the IAEA's Research Reactor Data Base (RRDB), of which 274 are operational in 56 countries (85 in 39 developing countries), 214 are shut down, 168 have been decommissioned and 16 are planned or under construction. Nuclear power supplied 16% of global electricity generation in 2002, and as of 31 December 2003 there were 439 NPPs operating worldwide. Their global energy availability factor has risen steadily from 74.2% in 1991 to approximately 84% in 2003. In 2003 two new NPPs were connected to the grid, a 665 MW(e) pressurized heavy water reactor (PHWR) in China and a 960 MW(e) pressurized water reactor (PWR) in the Republic of Korea. In addition Canada restarted two units that had been shutdown. Construction started on one new NPP in India. Four 50 MW(e) units in the UK were retired, as were one 640 MW

Nuclear technology review 2004

International Nuclear Information System (INIS)

2004-08-01

The viability and credibility of a wide range of nuclear-based technologies require ready access to high-quality atomic, molecular and nuclear data. The demands of new nuclear technologies continue to determine the direction(s) of future data development, including the requirements for data that address innovative fuel cycles, accelerator-driven systems, nuclear incineration, fusion devices, diagnostic and therapeutic medical treatment by radiation, optimization of medical isotope production, non-destructive materials testing, radiation analytical techniques, minerals exploration and land-mine detection. Some recent data development projects with diverse applications are a search engine for Atomic and Molecular data to permit simultaneous data retrieval from a number of different sources for both numerical and bibliographic databases to aid designers. For over 50 years, research reactors have made valuable contributions to the development of nuclear power, basic science, materials development, radioisotope production for medicine and industry, and education and training. They remain core experimental instruments. As of June 2004, 672 research reactors are recorded in the IAEA's Research Reactor Data Base (RRDB), of which 274 are operational in 56 countries (85 in 39 developing countries), 214 are shut down, 168 have been decommissioned and 16 are planned or under construction. Nuclear power supplied 16% of global electricity generation in 2002, and as of 31 December 2003 there were 439 NPPs operating worldwide. Their global energy availability factor has risen steadily from 74.2% in 1991 to approximately 84% in 2003. In 2003 two new NPPs were connected to the grid, a 665 MW(e) pressurized heavy water reactor (PHWR) in China and a 960 MW(e) pressurized water reactor (PWR) in the Republic of Korea. In addition Canada restarted two units that had been shutdown. Construction started on one new NPP in India. Four 50 MW(e) units in the UK were retired, as were one 640 MW

Review of nuclear power plant systems

International Nuclear Information System (INIS)

Doehler

1980-01-01

This presentation starts with a brief description of the Technischer Ueberwachungs-Verein (TUeV) and its main activities in the field of technical assessments. The TUeV-organisation is in general the assessor who performs the review if nuclear power plant systems, structures and equipment. All aspects relating to the safe operation of nuclear power plants are assessed by the TUeV. This paper stresses the review of the design of nuclear power plant systems and structures. It gives an outline on the procedure of an assessment, starting with the regulatory requirements, going into the papers of the applicant and finally ending with the TUeV-appraisal. This procedure is shown using settlement measuring requirements as an example. The review of the design of mechanical structures such as pipes, valves, pump and vessels is shown in detail. (RW)

NPP planning based on analysis of ground vibration caused by collapse of large-scale cooling towers

Energy Technology Data Exchange (ETDEWEB)

Lin, Feng; Ji, Hongkui [Department of Structural Engineering, Tongji University, No. 1239 Siping Road, Shanghai 200092 (China); Gu, Xianglin, E-mail: gxl@tongji.edu.cn [Department of Structural Engineering, Tongji University, No. 1239 Siping Road, Shanghai 200092 (China); Li, Yi [Department of Structural Engineering, Tongji University, No. 1239 Siping Road, Shanghai 200092 (China); Wang, Mingreng; Lin, Tao [East China Electric Power Design Institute Co., Ltd, No. 409 Wuning Road, Shanghai 200063 (China)

2015-12-15

Highlights: • New recommendations for NPP planning were addressed taking into account collapse-induced ground vibration. • Critical factors influencing the collapse-induced ground vibration were investigated. • Comprehensive approach was presented to describe the initiation and propagation of collapse-induced disaster. - Abstract: Ground vibration induced by collapse of large-scale cooling towers can detrimentally influence the safe operation of adjacent nuclear-related facilities. To prevent and mitigate these hazards, new planning methods for nuclear power plants (NPPs) were studied considering the influence of these hazards. First, a “cooling tower-soil” model was developed, verified, and used as a numerical means to investigate ground vibration. Afterwards, five critical factors influencing collapse-induced ground vibration were analyzed in-depth. These influencing factors included the height and weight of the towers, accidental loads, soil properties, overlying soil, and isolation trench. Finally, recommendations relating to the control and mitigation of collapse-induced ground vibration in NPP planning were proposed, which addressed five issues, i.e., appropriate spacing between a cooling tower and the nuclear island, control of collapse modes, sitting of a cooling tower and the nuclear island, application of vibration reduction techniques, and the influence of tower collapse on surroundings.

Piping support load data base for nuclear plants

International Nuclear Information System (INIS)

Childress, G.G.

1991-01-01

Nuclear Station Modifications are continuous through the life of a Nuclear Power Plant. The NSM often impacts an existing piping system and its supports. Prior to implementation of the NSM, the modified piping system is qualified and the qualification documented. This manual review process is tedious and an obvious bottleneck to engineering productivity. Collectively, over 100,000 piping supports exist at Duke Power Company's Nuclear Stations. Engineering support must maintain proper documentation of all data for each support. Duke Power Company has designed and developed a mainframe based system that: directly uses Support Load Summary data generated by a piping analysis computer program; streamlines the pipe support evaluation process; easily retrieves As-Built and NSM information for any pipe support from an NSM or AS-BUILT data base; and generated documentation for easy traceability of data to the information source. This paper discusses the design considerations for development of Support Loads Database System (SLDB) and reviews the program functionality through the user menus

Overview of light water/hydrogen-based low energy nuclear reactions

International Nuclear Information System (INIS)

Miley, George H.; Shrestha, Prajakti J.

2006-01-01

This paper reviews light water and hydrogen-based low-energy nuclear reactions (LENRs) including the different methodologies used to study these reactions and the results obtained. Reports of excess heat production, transmutation reactions, and nuclear radiation emission are cited. An aim of this review is to present a summary of the present status of light water LENR research and provide some insight into where this research is heading. (author)

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Tornado damage at the Grand Gulf, Mississippi nuclear power plant site: aerial and ground surveys

International Nuclear Information System (INIS)

Fujita, T.T.; McDonald, J.R.

1978-05-01

A tornado struck the Grand Gulf nuclear power generating station, Port Gibson, Mississippi, about 11:30 p.m. on April 17, 1978. Storm damage investigators from the University of Chicago and Texas Tech University were dispatched to survey the damage. The meteorological situation that spawned the Grand Gulf tornado and seven others in the area is discussed. Aerial surveys of the entire damage path and detailed surveys of the plant site are presented. An engineering evaluation of the damage is also presented based primarily on information gained from detailed ground surveys

Improving Agricultural Water Resources Management Using Ground-based Infrared Thermometry

Science.gov (United States)

Taghvaeian, S.

2014-12-01

Irrigated agriculture is the largest user of freshwater resources in arid/semi-arid parts of the world. Meeting rapidly growing demands in food, feed, fiber, and fuel while minimizing environmental pollution under a changing climate requires significant improvements in agricultural water management and irrigation scheduling. Although recent advances in remote sensing techniques and hydrological modeling has provided valuable information on agricultural water resources and their management, real improvements will only occur if farmers, the decision makers on the ground, are provided with simple, affordable, and practical tools to schedule irrigation events. This presentation reviews efforts in developing methods based on ground-based infrared thermometry and thermography for day-to-day management of irrigation systems. The results of research studies conducted in Colorado and Oklahoma show that ground-based remote sensing methods can be used effectively in quantifying water stress and consequently triggering irrigation events. Crop water use estimates based on stress indices have also showed to be in good agreement with estimates based on other methods (e.g. surface energy balance, root zone soil water balance, etc.). Major challenges toward the adoption of this approach by agricultural producers include the reduced accuracy under cloudy and humid conditions and its inability to forecast irrigation date, which is a critical knowledge since many irrigators need to decide about irrigations a few days in advance.

Nuclear Technology Review 2012

International Nuclear Information System (INIS)

2012-09-01

In 2011, nuclear energy continued to play an important role in global electricity production despite the accident at the Fukushima Daiichi nuclear power plant (NPP). Total generating nuclear power capacity was slightly lower than in previous years due to the permanent shutdown of 13 reactors in 2011, including 8 in Germany and 4 in Japan in the wake of the accident. However, there were 7 new grid connections compared to 5 in 2010, 2 in 2009 and none in 2008. Significant growth in the use of nuclear energy worldwide is still anticipated - between 35% and 100% by 2030 - although the Agency projections for 2030 are 7-8% lower than projections made in 2010. The factors that have contributed to an increased interest in nuclear power did not change: an increasing global demand for energy, concerns about climate change, energy security and uncertainty about fossil fuel supplies. Most of the growth is still expected in countries that already have operating NPPs, especially in Asia, with China and India remaining the main centres of expansion while the Russian Federation will also remain a centre of strong growth. The 7-8% drop in projected growth for 2030 reflects an accelerated phase-out of nuclear power in Germany, some immediate shutdowns and a government review of the planned expansion in Japan, as well as temporary delays in expansion in several other countries. Measures taken by countries as a result of the Fukushima Daiichi nuclear accident have been varied. A number of countries announced reviews of their programmes. Belgium, Germany and Switzerland took additional steps to phase out nuclear power entirely while others re-emphasized their expansion plans. Many Member States carried out national safety assessment reviews in 2011 (often called 'stress tests'), and commitments were made to complete any remaining assessments promptly and to implement the necessary corrective action. In countries considering the introduction of nuclear power, interest remained strong

Coupling analysis on the soft ground settlement laws in Qinshan nuclear power phase I sea wall project

International Nuclear Information System (INIS)

Sun Feng; Pan Rong; Zhu Xiuyun; Zhang Dingli

2011-01-01

Qinshan Nuclear Power Phase I sea wall project is a barrier engineering in defending the design basis flooding, which is of importance to the safety of NPP. The geological condition has the feature of high compressibility and low penetration, such as the soft ground of 1 + 450 section of Qinshan Nuclear Power Phase I sea wall. Based on parameters acquired from the site experiment, 3-D finite difference analysis is put forward to study the feature of consolidation settlement laws, which can embody the fluid-solid coupling interaction. The conclusions of numerical analysis agree well with the in-site measured data, and it, can contribute to the design and construction of raising sea wall project. (authors)

The Interagency Nuclear Safety Review Panel's Galileo safety evaluation report

International Nuclear Information System (INIS)

Nelson, R.C.; Gray, L.B.; Huff, D.A.

1989-01-01

The safety evaluation report (SER) for Galileo was prepared by the Interagency Nuclear Safety Review Panel (INSRP) coordinators in accordance with Presidential directive/National Security Council memorandum 25. The INSRP consists of three coordinators appointed by their respective agencies, the Department of Defense, the Department of Energy (DOE), and the National Aeronautics and Space Administration (NASA). These individuals are independent of the program being evaluated and depend on independent experts drawn from the national technical community to serve on the five INSRP subpanels. The Galileo SER is based on input provided by the NASA Galileo Program Office, review and assessment of the final safety analysis report prepared by the Office of Special Applications of the DOE under a memorandum of understanding between NASA and the DOE, as well as other related data and analyses. The SER was prepared for use by the agencies and the Office of Science and Technology Policy, Executive Office of the Present for use in their launch decision-making process. Although more than 20 nuclear-powered space missions have been previously reviewed via the INSRP process, the Galileo review constituted the first review of a nuclear power source associated with launch aboard the Space Transportation System

Ground beetles (Coleoptera, Carabidae) of the Hanford Nuclear Site in south-central Washington State.

Science.gov (United States)

Looney, Chris; Zack, Richard S; Labonte, James R

2014-01-01

Carabidae) collected from the Hanford Nuclear Reservation and Hanford National Monument (together the Hanford Site), which is located in south-central Washington State. The Site is a relatively undisturbed relict of the shrub-steppe habitat present throughout much of the western Columbia Basin before the westward expansion of the United States. Species, localities, months of capture, and capture method are reported for field work conducted between 1994 and 2002. Most species were collected using pitfall traps, although other capture methods were employed. Trapping results indicate the Hanford Site supports a diverse ground beetle community, with over 90% of the 92 species captured native to North America. Four species collected during the study period are newly recorded for Washington State: Bembidion diligens Casey, Calosoma obsoletum Say, Pseudaptinus rufulus (LeConte), and Stenolophus lineola (Fabricius). Based on these data, the Site maintains a diverse ground beetle fauna and, due to its size and diversity of habitats, is an important repository of shrub-steppe biodiversity.

Nuclear industry review

International Nuclear Information System (INIS)

1982-01-01

This review examines the consequences of projected excess electrical generating capacity for the maintenance of an independent nuclear power capability in Canada. Although consumption of electricity will continue to grow at rages well below historical averages, significant additions to capacity will be required in all parts of Canada in the 1990s. CANDU reactors are an attractive option for meeting load growth, particularly east of Manitoba. However, the absence of domestic orders in the 1980s may threaten the maintenance of this option. Even the most optimistic projections indicate that only one supplier of each component will remain in the nuclear business in the 1990s

Ground-based observations of exoplanet atmospheres

NARCIS (Netherlands)

Mooij, Ernst Johan Walter de

2011-01-01

This thesis focuses on the properties of exoplanet atmospheres. The results for ground-based near-infrared secondary eclipse observations of three different exoplanets, TrES-3b, HAT-P-1b and WASP-33b, are presented which have been obtained with ground-based telescopes as part of the GROUSE project.

Safety review for human factors engineering and control rooms of nuclear power plants

International Nuclear Information System (INIS)

Yang Mengzhuo

1998-01-01

Safety review for human factors engineering and control rooms of nuclear power plants (NPP) is in a forward position of science and technology, which began at American TMI severe accident and had been implemented in China. The importance and the significance of the safety review are expounded, the requirements of its scope and profundity are explained in detail. In addition, the situation of the technical document system for nuclear safety regulation on human factors engineering and control rooms of NPP in China is introduced briefly, on which the safety review is based

Study of seismic design bases for nuclear power plants in the US

International Nuclear Information System (INIS)

Kintzer, F.C.; Yanev, P.I.; Gotschall, H.L.

1983-01-01

This paper presents the results of an investigation of topics pertinent to establishing design basis seismic events and soil conditions for deployment of the High Temperature Gas-Cooled Reactor - Steam Cycle/Cogeneration (HTGR-SC/C) System. Generalized design ground accelerations and soil shear wave velocities are presented by regions of the continental United States. Design basis accelerations and soil conditions for existing nuclear power plants are summarized. Finally, analytical approaches to assess soil-structure interaction, including the effects of embedment, are reviewed

Nuclear Installation Safety: General Observations and Trends from IAEA Peer Reviews

International Nuclear Information System (INIS)

Rzentkowski, G.

2016-01-01

The Safety Review Services (SRSs) for nuclear installations address the needs of Member States at all stages of installations’ lifecycle. SRSs are based on the IAEA Safety Standards and are provided on Member States’ request to peer review national regulatory frameworks and safety provisions for nuclear installations. They result in recommendations and suggestions to improve national regulations and operational safety, and serve to exert peer pressure to ensure that that every Member State with nuclear installations recognizes its safety responsibility and the need to comply with the IAEA Safety Standards. This presentation provides an overview of SRSs for Nuclear Installations, including their structure and main subject areas. The presentation also summarizes general findings and trends which clearly demonstrate that there is continuous improvement in regulation of nuclear installations and in safety of their operation. Nevertheless, there is the need to further enhance the efficiency and effectiveness of SRSs through review of the overall governance model and service delivery to better serve the needs of Member States. The presentation points out some areas of improvements which have already been implemented or are being considered for implementation. Just as important, SRSs are conducted by teams of experts from around the world to strengthening international cooperation, ensure diversity and impartiality, and improve the overall quality of the safety review being conducted. The review team members are also provided with the opportunity for mutual learning and sharing good practices among themselves and with the Member State undergoing the review. As a result, SRAs play an important role in a quest to harmonize regulatory requirements and approaches globally. (author)

ICT based training on nuclear technology applications in Tanzania

Energy Technology Data Exchange (ETDEWEB)

Mdoe, S.L. [Nuclear Technology Applications Directorate, Tanzania Atomic Energy Commission, P.O. Box 743, Arusha (Tanzania)]. E-mail: slcmdoe@yahoo.com; Kimaro, E. [Nuclear Technology Applications Directorate, Tanzania Atomic Energy Commission, P.O. Box 743, Arusha (Tanzania)]. E-mail: taec@habari.co.tz

2006-07-01

Peaceful application of nuclear technology has contributed to socio-economic resource development in Tanzania. The Tanzania Atomic Energy Commission has taken some active steps for the incorporation and or adoption of ICT-based training modules in nuclear science and technology and its applications. The overall objective of this programme is to establish a sustainable national capability for using the potential of information communication technologies (ICTs) for training and education in the field of nuclear science and technology. This paper reviews some of the experience which the authors gained in the area of ICT based training in nuclear technology applications, it describes some of the challenges experienced, and some proposals to address the issues involved. (author)

ICT based training on nuclear technology applications in Tanzania

International Nuclear Information System (INIS)

Mdoe, S.L.; Kimaro, E.

2006-01-01

Peaceful application of nuclear technology has contributed to socio-economic resource development in Tanzania. The Tanzania Atomic Energy Commission has taken some active steps for the incorporation and or adoption of ICT-based training modules in nuclear science and technology and its applications. The overall objective of this programme is to establish a sustainable national capability for using the potential of information communication technologies (ICTs) for training and education in the field of nuclear science and technology. This paper reviews some of the experience which the authors gained in the area of ICT based training in nuclear technology applications, it describes some of the challenges experienced, and some proposals to address the issues involved. (author)

First observations of tritium in ground water outside chimneys of underground nuclear explosions, Yucca Flat, Nevada Test Site

International Nuclear Information System (INIS)

Crow, N.B.

1976-01-01

Abnormal levels of radionuclides had not been detected in ground water at the Nevada Test Site beyond the immediate vicinity of underground nuclear explosions until April 1974, when above-background tritium activity levels were detected in ground-water inflow from the tuff beneath Yucca Flat to an emplacement chamber being mined in hole U2aw in the east-central part of Area 2. No other radionuclides were detected in a sample of water from the chamber. In comparison with the amount of tritium estimated to be present in the ground water in nearby nuclear chimneys, the activity level at U2aw is very low. To put the tritium activity levels at U2aw into proper perspective, the maximum tritium activity level observed was significantly less than the maximum permissible concentration (MPC) for a restricted area, though from mid-April 1974 until the emplacement chamber was expended in September 1974, the tritium activity exceeded the MPC for the general public. Above-background tritium activity was also detected in ground water from the adjacent exploratory hole, Ue2aw. The nearest underground nuclear explosion detonated beneath the water table, believed to be the source of the tritium observed, is Commodore (U2am), located 465 m southeast of the emplacement chamber in U2aw. Commodore was detonated in May 1967. In May 1975, tritium activity May significantly higher than regional background. was detected in ground water from hole Ue2ar, 980 m south of the emplacement chamber in U2aw and 361 m from a second underground nuclear explosion, Agile (U2v), also detonated below the water table, in February 1967. This paper describes these occurrences of tritium in the ground water. A mechanism to account for the movement of tritium is postulated

Nuclear Technology Review 2013. Report by the Director General

International Nuclear Information System (INIS)

2013-01-01

In response to requests by Member States, the Secretariat produces a comprehensive Nuclear Technology Review each year. Attached is this year's report, which highlights notable developments principally in 2012. The Nuclear Technology Review 2013 covers the following areas: power applications, atomic and nuclear data, accelerators and research reactors, and nuclear sciences and applications. Additional documentation associated with the Nuclear Technology Review 2013 is available on the Agency's website1 in English on nuclear hydrogen production technology and preliminary lessons learned from the Fukushima Daiichi accident for advanced nuclear power plant technology development. Information on the IAEA's activities related to nuclear science and technology can also be found in the IAEA's Annual Report 2012 (GC(57)/3), in particular the Technology section, and the Technical Cooperation Report for 2012 (GC(57)/INF/4). The document has been modified to take account, to the extent possible, of specific comments by the Board of Governors and other comments received from Member States. (author)

A worldwide review of the cost of nuclear power

International Nuclear Information System (INIS)

Lecomte, M.; Mario, N.; Vignon, D.

2014-01-01

The 'true cost' of nuclear energy is a subject of great controversy, especially when considering capital costs of recent projects which opponents to this technology claim to be out of control. In order to provide an objective assessment of nuclear competitiveness, a systematic review of nuclear costs as estimated by stakeholders on a worldwide basis (parliamentary commissions, general accounting offices, academics from universities, non-governmental organizations [either promoting nuclear, or nonnuclear energy], utilities and vendors) was done. Based on these data, levelised costs of electricity (LCOE) were calculated, for different technologies and different regional areas. A breakdown between the key factors (pre-construction and owner costs, Capex, Opex, spent fuel management, dismantling and decommissioning) was provided. The study generally concludes that nuclear energy remains competitive, although costs of advanced technologies soared compared to Gen II. It also demonstrates the benefit of steady and ongoing nuclear programs compared to construction of single projects from time to time. (authors)

REVIEW Of COMPUTERIZED PROCEDURE GUIDELINES FOR NUCLEAR POWER PLANT CONTROL ROOMS

Energy Technology Data Exchange (ETDEWEB)

David I Gertman; Katya Le Blanc; Ronald L Boring

2011-09-01

Computerized procedures (CPs) are recognized as an emerging alternative to paper-based procedures for supporting control room operators in nuclear power plants undergoing life extension and in the concept of operations for advanced reactor designs. CPs potentially reduce operator workload, yield increases in efficiency, and provide for greater resilience. Yet, CPs may also adversely impact human and plant performance if not designed and implemented properly. Therefore, it is important to ensure that existing guidance is sufficient to provide for proper implementation and monitoring of CPs. In this paper, human performance issues were identified based on a review of the behavioral science literature, research on computerized procedures in nuclear and other industries, and a review of industry experience with CPs. The review of human performance issues led to the identification of a number of technical gaps in available guidance sources. To address some of the gaps, we developed 13 supplemental guidelines to support design and safety. This paper presents these guidelines and the case for further research.

A systematic review of grounded theory studies in physiotherapy.

Science.gov (United States)

Ali, Nancy; May, Stephen; Grafton, Kate

2018-05-23

This systematic review aimed at appraising the methodological rigor of grounded theory research published in the field of physiotherapy to assess how the methodology is understood and applied. A secondary aim was to provide research implications drawn from the findings to guide future grounded theory methodology (GTM) research. A systematic search was conducted in MEDLINE, CINHAL, SPORT Discus, Science Direct, PubMed, Scopus, and Web of Science to identify studies in the field of physiotherapy that reported using GTM and/or methods in the study title and/or abstract. The descriptive characteristics and methodological quality of eligible studies were examined using grounded theory methodology assessment guidelines. The review included 68 studies conducted between 1998 and 2017. The findings showed that GTM is becoming increasingly used by physiotherapy researchers. Thirty-six studies (53%) demonstrated a good understanding and appropriate application of GTM. Thirty-two studies (47%) presented descriptive findings and were considered to be of poor methodological quality. There are several key tenets of GTM that are integral to the iterative process of qualitative theorizing and need to be applied throughout all research practices including sampling, data collection, and analysis.

Reliability research to nuclear power plant operators based on several methods

International Nuclear Information System (INIS)

Fang Xiang; Li Fu; Zhao Bingquan

2009-01-01

The paper utilizes many kinds of international reliability research methods, and summarizes the review of reliability research of Chinese nuclear power plant operators in past over ten years based on the simulator platform of nuclear power plant. The paper shows the necessity and feasibility of the research to nuclear power plant operators from many angles including human cognition reliability, fuzzy mathematics model and psychological research model, etc. It will be good to the safe operation of nuclear power plant based on many kinds of research methods to the reliability research of nuclear power plant operators. (authors)

Nuclear rocket propulsion

International Nuclear Information System (INIS)

Clark, J.S.; Miller, T.J.

1991-01-01

NASA has initiated planning for a technology development project for nuclear rocket propulsion systems for Space Exploration Initiative (SEI) human and robotic missions to the Moon and to Mars. An Interagency project is underway that includes the Department of Energy National Laboratories for nuclear technology development. This paper summarizes the activities of the project planning team in FY 1990 and FY 1991, discusses the progress to date, and reviews the project plan. Critical technology issues have been identified and include: nuclear fuel temperature, life, and reliability; nuclear system ground test; safety; autonomous system operation and health monitoring; minimum mass and high specific impulse

IAEA Completes Safety Review at Czech Nuclear Power Plant

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts, led by the International Atomic Energy Agency (IAEA), today completed a review of safety practices at Temelin Nuclear Power Station in the Czech Republic. The team highlighted the Power Plant's good practices and also recommended improvements to some safety measures. At the request of the Government of the Czech Republic, the IAEA assembled a team of nuclear installation safety experts to send an Operational Safety Review Team (OSART) to the Power Plant, and the mission was conducted from 5 to 22 November 2012. The team was comprised of experts from Brazil, Hungary, Slovakia, South Africa, Sweden, Ukraine and the United Kingdom. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the Plant's overall safety status. The team at Temelin conducted an in-depth review of the functions essential to the safe operation of the Power Plant, which are under the responsibility of the site's management. The review covered the areas of management, organization and administration; operations; maintenance; technical support; operating experience; radiation protection; chemistry; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of potential application elsewhere. Examples include the following: - The Power Plant has adopted effective computer software to improve the efficiency of the plant to prepare and isolate equipment for maintenance; - The Power Plant undertakes measures to control precisely the chemical parameters that limit corrosion in the reactor's coolant system, which in turn reduce radiation exposure to the workforce; and - The Temelin

Nuclear Medicine Engineering

International Nuclear Information System (INIS)

Mateescu, Gheorghe; Craciunescu, Teddy

2000-01-01

'An image is more valuable than a thousand words' - this is the thought that underlies the authors' vision about the field of nuclear medicine. The monograph starts with a review of some theoretical and engineering notions that grounds the field of nuclear medicine: nuclear radiation, interaction of radiation with matter, radiation detection and measurement, numerical analysis. Products and methods needed for the implementation of diagnostic and research procedures in nuclear medicine are presented: radioisotopes and radiopharmaceuticals, equipment for in-vitro (radioimmunoassay, liquid scintillation counting) and in-vivo investigations (thyroid uptake, renography, dynamic studies, imaging). A special attention is focused on medical imaging theory and practice as a source of clinical information (morphological and functional). The large variety of parameters, components, biological structures and specific properties of live matter determines the practical use of three-dimensional tomographic techniques based on diverse physical principles: single-photon emission, positron emission, X-rays transmission, nuclear magnetic resonance, ultrasounds transmission and reflection, electrical impedance measurement. The fundamental reconstruction algorithms i.e., algorithms based on the projection theorem and Fourier filtering, algebraic reconstruction techniques and the algorithms based on statistical principles: maximum entropy, maximum likelihood, Monte Carlo algorithms, are depicted in details. A method based on the use of the measured point spread function is suggested. Some classical but often used techniques like linear scintigraphy and Anger gamma camera imaging are also presented together with some image enhancement techniques like Wiener filtering and blind deconvolution. The topic of the book is illustrated with some clinical samples obtained with nuclear medicine devices developed in the Nuclear Medicine Laboratory of the National Institute of Nuclear Physics and

The nuclear review

International Nuclear Information System (INIS)

O'Neill, M.

1995-01-01

The position of the Labour Party on the future of nuclear power in the United Kingdom is presented. Although nuclear power is seen to have a role for many years to come, a future Labour government would not build any more nuclear power stations nor extend the life of existing ones. The relative abundance of cheaper, gas fired generating plants and the attractiveness of environmentally friendly, smaller stations, nearer to their markets and cheap to run, argues against further investment in nuclear power. Nevertheless, the Labour party would sustain a dialogue with the nuclear industry and would be interested in technical developments. For too long attitudes to nuclear power have been based on fear rather than facts. The case for the privatisation of nuclear power stations is considered to be unfounded and the retention of back-end operations in the public sector is essential. (UK)

Virtual reality at nuclear issues : a review study

International Nuclear Information System (INIS)

Silva, Marcio Henrique da; Legey, Ana Paula; Mol, Antonio Carlos de A.

2015-01-01

Recently, several applications using concepts related to virtual reality has been proposed to help on solving issues of great interest in Nuclear Engineering. Among them are power plant's control rooms simulators; measurement of the estimated radiation dose in a nuclear power plant; use of game engines to create virtual environments to support evacuation planning of buildings and circulation in areas subjected to radiation; development of a man - machine interface based on speech recognition; virtual control tables for simulation of nuclear power plants; evacuation plans support; security teams training and evaluation of physical protection barriers; ergonomic evaluation of control rooms, and other ones. Many of these applications are developed at Instituto de Engenharia Nuclear (IEN), having their results published in form of articles in periodicals and conferences. This article presents a review of some of these studies showing the evolution in the use of these concepts, describing some of its results and showing prospects for future applications that can make use of virtual reality technology. (author)

Virtual reality at nuclear issues : a review study

Energy Technology Data Exchange (ETDEWEB)

Silva, Marcio Henrique da; Legey, Ana Paula; Mol, Antonio Carlos de A., E-mail: marciohenrique@lmp.ufrj.br, E-mail: ana.legey@pq.cnpq.br, E-mail: mol@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2015-07-01

Recently, several applications using concepts related to virtual reality has been proposed to help on solving issues of great interest in Nuclear Engineering. Among them are power plant's control rooms simulators; measurement of the estimated radiation dose in a nuclear power plant; use of game engines to create virtual environments to support evacuation planning of buildings and circulation in areas subjected to radiation; development of a man - machine interface based on speech recognition; virtual control tables for simulation of nuclear power plants; evacuation plans support; security teams training and evaluation of physical protection barriers; ergonomic evaluation of control rooms, and other ones. Many of these applications are developed at Instituto de Engenharia Nuclear (IEN), having their results published in form of articles in periodicals and conferences. This article presents a review of some of these studies showing the evolution in the use of these concepts, describing some of its results and showing prospects for future applications that can make use of virtual reality technology. (author)

Tectonic stability and expected ground motion at Yucca Mountain

International Nuclear Information System (INIS)

1984-01-01

A workshop was convened on August 7-8, 1984 at the direction of DOE to discuss effects of natural and artificial earthquakes and associated ground motion as related to siting of a high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. A panel of experts in seismology and tectonics was assembled to review available data and analyses and to assess conflicting opinions on geological and seismologic data. The objective of the meeting was to advise the Nevada Nuclear Waste Storage Investigations (NNWSI) Project about how to present a technically balanced and scientifically credible evaluation of Yucca Mountain for the NNWSI Project EA. The group considered two central issues: the magnitude of ground motion at Yucca Mountain due to the largest expected earthquake, and the overall tectonic stability of the site given the current geologic and seismologic data base. 44 refs

Tectonic stability and expected ground motion at Yucca Mountain

Energy Technology Data Exchange (ETDEWEB)

NONE

1984-10-02

A workshop was convened on August 7-8, 1984 at the direction of DOE to discuss effects of natural and artificial earthquakes and associated ground motion as related to siting of a high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. A panel of experts in seismology and tectonics was assembled to review available data and analyses and to assess conflicting opinions on geological and seismologic data. The objective of the meeting was to advise the Nevada Nuclear Waste Storage Investigations (NNWSI) Project about how to present a technically balanced and scientifically credible evaluation of Yucca Mountain for the NNWSI Project EA. The group considered two central issues: the magnitude of ground motion at Yucca Mountain due to the largest expected earthquake, and the overall tectonic stability of the site given the current geologic and seismologic data base. 44 refs.

Learning from nuclear waste repository design: the ground-control plan

International Nuclear Information System (INIS)

Schmidt, B.

1988-01-01

At present, under a U.S. Department of Energy program, three repositories for commercial spent fuel-in salt, tuff and basalt-are in the phase of site characterization and conceptual design, and one pilot project for defense waste in salt is under development. Because of strict quality assurance requirements throughout design and construction, and the need to predict and ascertain in advance the satisfactory performance of the underground openings, underground openings in the unusual circumstances of the repository environment have been analysed. This will lead to an improved understanding of rock behavior and improved methods of underground analysis and design. A formalized ground control plan was developed, the principles of which may be applied to other types of projects. This paper summarizes the status of underground design and construction for nuclear waste repositories and presents some details of the ground control plan and its individual elements. (author)

Preparing and Conducting Review Missions of Instrumentation and Control Systems in Nuclear Power Plants

International Nuclear Information System (INIS)

2011-06-01

The mission for Independent Engineering Review of Instrumentation and Control (I and C) Systems (IERICS) in Nuclear Power Plants (NPPs) has been established with the aim of conducting peer reviews of I and C design documents, implementation processes, prototype I and C systems, and actual systems already deployed in operating NPPs. Organizations in IAEA Member States, such as nuclear utilities, regulators, and technical support organizations can benefit from I and C technical reviews through requesting IERICS missions that provide a detailed technical assessment on I and C systems, as well as recommendations for improvement. The IERICS mission is conducted by a team of international subject matter experts from various complementing technical areas. The review is based on appropriate IAEA documents, such as Safety Guides and Nuclear Energy Series, and the mission's findings are summarized in a mission report, including a list of recommendations, suggestions, and identified good practices. The review is not intended to be a regulatory inspection or an audit against international codes and standards. Rather, it is a peer review aimed at improving design and implementation procedures through an exchange of technical experiences and practices at the working level. The IERICS mission is applicable at any stages of the life cycle of I and C systems in NPPs and it is initiated based on a formal request through official IAEA channels from an organization of a Member State. The formation of the IERICS mission is based on the recommendation of the IAEA Technical Working Group on Nuclear Power Plant Instrumentation and Control (TWG-NPPIC). The recommendation came from the recognition that the IAEA can play an important role in the independent assessment and review of NPP I and C systems in terms of their compliance with IAEA safety guides and technical documents.

Submillimetric motion detection with a 94 GHz ground based synthetic aperture radar

OpenAIRE

Martinez Cervera, Arturo; Lort Cuenca, Marc; Aguasca Solé, Alberto; Broquetas Ibars, Antoni

2015-01-01

The paper presents the validation and experimental assessment of a 94 GHz (W-Band) CW-FM Radar that can be configured as a Ground Based SAR for high resolution imaging and interferometry. Several experimental campaigns have been carried out to assess the capability of the system to remotely observe submillimetric deformation and vibration in infrastructures. Peer Reviewed

Ground-based VHE γ ray astronomy with air Cherenkov imaging telescopes

International Nuclear Information System (INIS)

Mirzoyan, R.

2000-01-01

The history of astronomy has been one of the scientific discovery following immediately the introduction of new technology. In this report, we will review shortly the basic development of the atmospheric air Cherenkov light detection technique, particularly the imaging telescope technique, which in the last years led to the firm establishment of a new branch in experimental astronomy, namely ground-based very high-energy (VHE) γ ray astronomy. Milestones in the technology and in the analysis of imaging technique will be discussed. The design of the 17 m diameter MAGIC Telescope, being currently under construction, is based on the development of new technologies for all its major parts and sets new standards in the performance of the ground-based γ detectors. MAGIC is one of the next major steps in the development of the technique being the first instrument that will allow one to carry out measurements also in the not yet investigated energy gap i.e. between 10 and 300 GeV

On some aspects of nuclear safety surveillance and review

International Nuclear Information System (INIS)

Li Ganjie; Zhu Hong; Zhou Shanyuan

2004-01-01

Five aspects of the nuclear safety surveillance and review are discussed: Strict implementation of nuclear safety regulation, making the nuclear safety surveillance and review more normalization, procedurization, scientific decision-making; Strictly requiring the applicant to comply with the requirements of codes, do not allowing the utilization of mixing of codes; Properly controlling the strictness for the review on significant non-conformance; Strengthening the co-operation between regional offices and technical support units, Properly treat the relations between administrational management unit and technical support units. (authors)

Seismic Hazard Assessment in Site Evaluation for Nuclear Installations: Ground Motion Prediction Equations and Site Response

International Nuclear Information System (INIS)

2016-07-01

The objective of this publication is to provide the state-of-the-art practice and detailed technical elements related to ground motion evaluation by ground motion prediction equations (GMPEs) and site response in the context of seismic hazard assessments as recommended in IAEA Safety Standards Series No. SSG-9, Seismic Hazards in Site Evaluation for Nuclear Installations. The publication includes the basics of GMPEs, ground motion simulation, selection and adjustment of GMPEs, site characterization, and modelling of site response in order to improve seismic hazard assessment. The text aims at delineating the most important aspects of these topics (including current practices, criticalities and open problems) within a coherent framework. In particular, attention has been devoted to filling conceptual gaps. It is written as a reference text for trained users who are responsible for planning preparatory seismic hazard analyses for siting of all nuclear installations and/or providing constraints for anti-seismic design and retrofitting of existing structures

Russian Minatom nuclear safety research strategic plan. An international review

International Nuclear Information System (INIS)

Royen, J.

1999-01-01

An NEA study on safety research needs of Russian-designed reactors, carried out in 1996, strongly recommended that a strategic plan for safety research be developed with respect to Russian nuclear power plants. Such a plan was developed at the Russian International Nuclear Safety Centre (RINSC) of the Russian Ministry of Atomic Energy (Minatom). The Strategic Plan is designed to address high-priority safety-research needs, through a combination of domestic research, the application of appropriate foreign knowledge, and collaboration. It represents major progress toward developing a comprehensive and coherent safety-research programme for Russian nuclear power plants (NPPs). The NEA undertook its review of the Strategic Plan with the objective of providing independent verification on the scope, priority, and content of the research described in the Plan based upon the experience of the international group of experts. The principal conclusions of the review and the general comments of the NEA group are presented. (K.A.)

Operation of Nuclear Fuel Based on Reprocessed Uranium for VVER-type Reactors in Competitive Nuclear Fuel Cycles

Energy Technology Data Exchange (ETDEWEB)

Troyanov, V.; Molchanov, V.; Tuzov, A. [TVEL Corporation, 49 Kashirskoe shosse, Moscow 115409 (Russian Federation); Semchenkov, Yu.; Lizorkin, M. [RRC ' Kurchatov Institute' (Russian Federation); Vasilchenko, I.; Lushin, V. [OKB ' Gidropress' (Russian Federation)

2009-06-15

Current nuclear fuel cycle of Russian nuclear power involves reprocessed low-enriched uranium in nuclear fuel production for some NPP units with VVER-type LWR. This paper discusses design and performance characteristics of commercial nuclear fuel based on natural and reprocessed uranium. It presents the review of results of commercial operation of nuclear fuel based on reprocessed uranium on Russian NPPs-unit No.2 of Kola NPP and unit No.2 of Kalinin NPP. The results of calculation and experimental validation of safe fuel operation including necessary isotope composition conformed to regulation requirements and results of pilot fuel operation are also considered. Meeting the customer requirements the possibility of high burn-up achieving was demonstrated. In addition the paper compares the characteristics of nuclear fuel cycles with maximum length based on reprocessed and natural uranium considering relevant 5% enrichment limitation and necessity of {sup 236}U compensation. The expedience of uranium-235 enrichment increasing over 5% is discussed with the aim to implement longer fuel cycles. (authors)

Probability based load criteria for the design of nuclear structures: a critical review of the state-of-the-art

Energy Technology Data Exchange (ETDEWEB)

Shinozuka, M.; Ellingwood, B.R.; Wang, P.C.; Meyer, C.; Wen, Y.K.; Kao, S.; Shooman, M.L.; Philippacopoulos, A.J.

1981-04-01

Structures for nuclear power plant facilities must be designed to withstand safely and effectively all kinds of loads and load combinations that may be expected to occur during their lifetime. The traditional methods of structural design attempt to account for the inevitable variability in the loads, material strengths, in-service environments, and fabrication process, etc., through the use of safety factor, allowable stresses or load and resistance factors. These approaches may result in an unknown and nonuniform reliability because of the subjective manner in which the safety factors have been determined. The stochastic nature loads and the uncertainties in material properties dictate a probabilistic approach for a rational assessment of structural safety and performance. This report presents: an in-depth review of the state-of-the-art pertaining to probability-based analysis and design of civil engineering structures; basis for extending existing probability-based methods to seismic category I nuclear structures; and the availability of the pertinent data required to perform probabilistic analysis for seismic category I nuclear structures.

Ground-water sampling of the NNWSI (Nevada Nuclear Waste Storage Investigation) water table test wells surrounding Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Matuska, N.A.

1988-12-01

The US Geological Survey (USGS), as part of the Nevada Nuclear Waste Storage Investigation (NNWSI) study of the water table in the vicinity of Yucca Mountain, completed 16 test holes on the Nevada Test Site and Bureau of Land Management-administered lands surrounding Yucca Mountain. These 16 wells are monitored by the USGS for water-level data; however, they had not been sampled for ground-water chemistry or isotropic composition. As part of the review of the proposed Yucca Mountain high-level nuclear waste repository, the Desert Research Institute (DRI) sampled six of these wells. The goal of this sampling program was to measure field-dependent parameters of the water such as electrical conductivity, pH, temperature and dissolved oxygen, and to collect samples for major and minor element chemistry and isotopic analysis. This information will be used as part of a program to geochemically model the flow direction between the volcanic tuff aquifers and the underlying regional carbonate aquifer

New nuclear technology; International developments. Review 1995

International Nuclear Information System (INIS)

Devell, L.; Aggeryd, I.; Hultgren, Aa.; Lundell, B.; Pedersen, T.

1995-09-01

A summary review of the development of new nuclear rector technology is presented in this report. Fuel cycle strategies and waste handling developments are also commented. Different plans for dismantling nuclear weapons are presented. 18 refs

Recommendations for the hydrogeologic review and assessment of sites for nuclear power installations within the framework of the radiation protection licensing procedure

International Nuclear Information System (INIS)

Adam, C.; Petschel, M.; Koerner, W.

1985-01-01

Article 4 of the Nuclear Facility Licensing Ordinance requires the information to be submitted in support of licensing applications for nuclear power installations to include an expertise on the hydrogeologic characteristics of the site environment with main emphasis on the movement of radionuclides through groundwater in the event of accident conditions, and on measures to protect ground and surface waters. Recommendations are given for the conduct of a hydrogeologic review and assessment process and its timing relative to the individual stages in the licensing procedure. (author)

Global nuclear-structure calculations

International Nuclear Information System (INIS)

Moeller, P.; Nix, J.R.

1990-01-01

The revival of interest in nuclear ground-state octupole deformations that occurred in the 1980's was stimulated by observations in 1980 of particularly large deviations between calculated and experimental masses in the Ra region, in a global calculation of nuclear ground-state masses. By minimizing the total potential energy with respect to octupole shape degrees of freedom in addition to ε 2 and ε 4 used originally, a vastly improved agreement between calculated and experimental masses was obtained. To study the global behavior and interrelationships between other nuclear properties, we calculate nuclear ground-state masses, spins, pairing gaps and Β-decay and half-lives and compare the results to experimental qualities. The calculations are based on the macroscopic-microscopic approach, with the microscopic contributions calculated in a folded-Yukawa single-particle potential

Review and evaluation of the Nuclear Materials Management and Safeguards System (NMMSS). Volume 1. Comparison of DOE nuclear materials information system requirements with NMMSS capabilities and recommendations for NMMSS improvements

International Nuclear Information System (INIS)

1984-03-01

This report documents the result of a review of the Nuclear Materials Management and Safeguards System (NMMSS), a Department of Energy nuclear materials control and accountability data base and information processing system. This review was performed to determine what data are required from the NMMSS, how it is collected, and how it is used. Based upon the review, NMMSS deficiencies and excess capabilities were identified and a draft set of requirements for the nuclear materials information system that the Office of Safeguards and Security (OSS) should be supporting as well as recommendations for attaining that capability

Nuclear renaissance, public perception and design criteria: An exploratory review

International Nuclear Information System (INIS)

Goodfellow, Martin J.; Williams, Hugo R.; Azapagic, Adisa

2011-01-01

There is currently an international drive to build new nuclear power plants, bringing about what is being termed a 'nuclear renaissance'. However, the public perception of nuclear energy has historically been, and continues to be, a key issue, particularly in light of the Fukushima nuclear incident. This paper discusses the disparity between perceived and calculated risks based on the last four decades of research into risk perception. The leading psychological and sociological theories, Psychometric Paradigm and Cultural Theory, respectively, are critically reviewed. The authors then argue that a new nuclear-build policy that promotes a broader approach to design incorporating a wider range of stakeholder inputs, including that of the lay public, may provide a means for reducing the perceived risk of a nuclear plant. Further research towards such a new approach to design is proposed, based on integrating expert and lay stakeholder inputs and taking into account broader socio-cultural factors whilst maintaining the necessary emphasis on safety, technological development, economics and environmental sustainability. - Highlights: → Globally, a number of countries are investing in or considering building new nuclear plants. → Public acceptance of nuclear safety is important to continuing new nuclear build efforts. → Theories are discussed attempting to explain the public perception of nuclear safety. → A socially informed design process is proposed which could assist in ensuring public support. → Further research to understand how this design process might be performed is proposed.

Management review of nuclear material control and accounting systems

International Nuclear Information System (INIS)

1975-06-01

Section 70.58, ''Fundamental Nuclear Material Controls,'' of 10 CFR Part 70, ''Special Nuclear Materials,'' requires, in paragraph 70.58(c), that certain licensees authorized to possess more than one effective kilogram of special nuclear material establish a management system to provide for the development, revision, implementation, and enforcement of nuclear material control and accounting procedures. Such a system must provide for a review of the nuclear material control system at least every 12 months. This guide describes the purpose and scope, personnel qualifications, depth of detail, and procedures that are acceptable to the NRC staff for the management review of nuclear material control systems required under paragraph 70.58(c) of 10 CFR Part 70. (U.S.)

Critical Review of EU Nuclear Stress Tests in Bulgaria, Hungary, Romania and Ukraine

International Nuclear Information System (INIS)

Becker, O.; Lorenz, P.; Wallner, A.

2012-01-01

In March 2011, the core melt accidents at the Fukushima Daiichi 1 nuclear power plant (NPP) showed the world that the nuclear industry cannot prevent severe accidents from happening. The accidents in Japan proved that highly unlikely accidents cannot be excluded. The Fukushima accident confirmed the mistrust towards nuclear power among the Japanese but also European citizens. In reaction to the devastating nuclear disaster in Japan the European Council concluded in March 2011, that the safety of all EU nuclear plants should be reviewed on the basis of a comprehensive and transparent risk and safety assessment ('stress tests'). The EU Nuclear Safety Regulators Group – ENSREG took over the task to provide a “targeted reassessment of the safety margins of nuclear power plants”, thus examining whether the safety margins which were used in the licensing of NPPs are sufficient to cover unexpected events. It is important to understand that the stress tests could not take into account all key safety issues such as the capability to prevent accidents - the scope of the stress tests defined by ENSREG didn´t promise to deliver a comprehensive risk and safety assessment. According to some observers the stress tests were mainly set up to improve the confidence in the safety of European NPPs. Nevertheless, the stress tests provided some interesting findings concerning safety: This study assesses the safety of the nuclear power plants in Bulgaria, Hungary, Romania and the Ukraine. The introduction contains an overview of the content and procedure of the stress tests. This “Critical Review of the Stress Tests” is based on the national stress tests reports written by the national nuclear safety authorities and on the Peer review country reports attached to the Peer review report - Stress tests performed on European nuclear power plants written by the Peer review Teams, the Peer Review Board respectively, and endorsed by ENSREG [ENSREG 2012a, ENSREG 2012c]. It

Critical Review of EU Nuclear Stress Tests in Bulgaria, Hungary, Romania and Ukraine

Energy Technology Data Exchange (ETDEWEB)

Becker, O.; Lorenz, P.; Wallner, A.

2012-07-01

In March 2011, the core melt accidents at the Fukushima Daiichi 1 nuclear power plant (NPP) showed the world that the nuclear industry cannot prevent severe accidents from happening. The accidents in Japan proved that highly unlikely accidents cannot be excluded. The Fukushima accident confirmed the mistrust towards nuclear power among the Japanese but also European citizens. In reaction to the devastating nuclear disaster in Japan the European Council concluded in March 2011, that the safety of all EU nuclear plants should be reviewed on the basis of a comprehensive and transparent risk and safety assessment ('stress tests'). The EU Nuclear Safety Regulators Group – ENSREG took over the task to provide a “targeted reassessment of the safety margins of nuclear power plants”, thus examining whether the safety margins which were used in the licensing of NPPs are sufficient to cover unexpected events. It is important to understand that the stress tests could not take into account all key safety issues such as the capability to prevent accidents - the scope of the stress tests defined by ENSREG didn´t promise to deliver a comprehensive risk and safety assessment. According to some observers the stress tests were mainly set up to improve the confidence in the safety of European NPPs. Nevertheless, the stress tests provided some interesting findings concerning safety: This study assesses the safety of the nuclear power plants in Bulgaria, Hungary, Romania and the Ukraine. The introduction contains an overview of the content and procedure of the stress tests. This “Critical Review of the Stress Tests” is based on the national stress tests reports written by the national nuclear safety authorities and on the Peer review country reports attached to the Peer review report - Stress tests performed on European nuclear power plants written by the Peer review Teams, the Peer Review Board respectively, and endorsed by ENSREG [ENSREG 2012a, ENSREG 2012c]. It continues

An Evaluation of the Physical Environments of a Nuclear Power Plants for Human Factors Review in Periodic Safety Review

International Nuclear Information System (INIS)

Kim, Dae Ho; Lee, Yong Hee

2006-01-01

Currently, operation of a nuclear power plants(NPP) is highly emphasized by the integrity of the H/W and the human factors security, so the periodic safety review(PSR) is performed to NPP. The PSR activities on human factors include physical environments (illumination, noise, vibration, temperature and humidity etc). The review on these physical environments is to verify the possible affect to the human error during the operation of the man machine interface. Physical environments affect the health, job stress and job satisfaction of NPP's employees. On the ground of the reason, we need integrating the management program for the sufficient satisfaction of the regulatory basis and standards of physical environment and considering a health, a job stress and satisfaction of NPP's employees. So, this paper describes the planning of the setup procedures of physical environments and the adequate management program for the field applications in NPPs

An Evaluation of the Physical Environments of a Nuclear Power Plants for Human Factors Review in Periodic Safety Review

Energy Technology Data Exchange (ETDEWEB)

Kim, Dae Ho; Lee, Yong Hee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

2006-07-01

Currently, operation of a nuclear power plants(NPP) is highly emphasized by the integrity of the H/W and the human factors security, so the periodic safety review(PSR) is performed to NPP. The PSR activities on human factors include physical environments (illumination, noise, vibration, temperature and humidity etc). The review on these physical environments is to verify the possible affect to the human error during the operation of the man machine interface. Physical environments affect the health, job stress and job satisfaction of NPP's employees. On the ground of the reason, we need integrating the management program for the sufficient satisfaction of the regulatory basis and standards of physical environment and considering a health, a job stress and satisfaction of NPP's employees. So, this paper describes the planning of the setup procedures of physical environments and the adequate management program for the field applications in NPPs.

From Regional Hazard Assessment to Nuclear-Test-Ban Treaty Support - InSAR Ground Motion Services

Science.gov (United States)

Lege, T.; Kalia, A.; Gruenberg, I.; Frei, M.

2016-12-01

There are numerous scientific applications of InSAR methods in tectonics, earthquake analysis and other geologic and geophysical fields. Ground motion on local and regional scale measured and monitored via the application of the InSAR techniques provide scientists and engineers with plenty of new insights and further understanding of subsurface processes. However, the operational use of InSAR is not yet very widespread. To foster the operational utilization of the Copernicus Sentinel Satellites in the day-to-day business of federal, state and municipal work and planning BGR (Federal Institute for Geosciences and Natural Resources) initiated workshops with potential user groups. Through extensive reconcilement of interests and demands with scientific, technical, economic and governmental stakeholders (e.g. Ministries, Mining Authorities, Geological Surveys, Geodetic Surveys and Environmental Agencies on federal and state level, SMEs, German Aerospace Center) BGR developed the concept of the InSAR based German National Ground Motion Service. One important backbone for the nationwide ground motion service is the so-called Persistent Scatterer Interferometry Wide Area Product (WAP) approach developed with grants of European research funds. The presentation shows the implementation of the ground motion service and examples for product developments for operational supervision of mining, water resources management and spatial planning. Furthermore the contributions of Copernicus Sentinel 1 radar data in the context of CTBT are discussed. The DInSAR processing of Sentinel 1 IW (Interferometric Wide Swath) SAR acquisitions from January 1st and 13th Jan. 2016 allow for the first time a near real time ground motion measurement of the North Korean nuclear test site. The measured ground displacements show a strong spatio-temporal correlation to the calculated epicenter measured by teleseismic stations. We are convinced this way another space technique will soon contribute even

Thailand: fertile ground for nuclear technology

International Nuclear Information System (INIS)

Innes, R.

1990-01-01

Thailand's Office of Atomic Energy for Peace (OAEP) is bringing the benefits of food irradiation and nuclear-based agricultural techniques to the population. One of the most successful OAEP programs involves irradiating a popular Thai delicacy, 'nham' (fermented raw pork) which is otherwise often contaminated with salmonella, and sometimes with trichinella. Irradiated nham has proven popular with Thai consumers. Other nuclear techniques are being applied as follows: neutron densitometry and isotope tracer techniques are providing a better understanding of the relationships between soil, fertilizer and plants; radioimmunoassay of progesterone is improving breeding of cattle and buffaloes; seed irradiation is producing improved varieties of plants; irradiation is being used to sterilize control fruit flies

Review Of Concrete Biodeterioration In Relation To Buried Nuclear Waste

International Nuclear Information System (INIS)

Turick, C.

2012-01-01

Long-term storage of low level radioactive material in below ground concrete disposal units (DUs) (Saltstone Disposal Facility) is a means of depositing wastes generated from nuclear operations of the U.S. Department of Energy. Based on the currently modeled degradation mechanisms, possible microbial induced effects on the structural integrity of buried low level wastes must be addressed. Previous international efforts related to microbial impacts on concrete structures that house low level radioactive waste showed that microbial activity can play a significant role in the process of concrete degradation and ultimately structural deterioration. This literature review examines the recent research in this field and is focused on specific parameters that are applicable to modeling and prediction of the fate of concrete vaults housing stored wastes and the wastes themselves. Rates of concrete biodegradation vary with the environmental conditions, illustrating a need to understand the bioavailability of key compounds involved in microbial activity. Specific parameters require pH and osmotic pressure to be within a certain range to allow for microbial growth as well as the availability and abundance of energy sources like components involved in sulfur, iron and nitrogen oxidation. Carbon flow and availability are also factors to consider in predicting concrete biodegradation. The results of this review suggest that microbial activity in Saltstone, (grouted low level radioactive waste) is unlikely due to very high pH and osmotic pressure. Biodegradation of the concrete vaults housing the radioactive waste however, is a possibility. The rate and degree of concrete biodegradation is dependent on numerous physical, chemical and biological parameters. Results from this review point to parameters to focus on for modeling activities and also, possible options for mitigation that would minimize concrete biodegradation. In addition, key chemical components that drive microbial

Review of Concrete Biodeterioration in Relation to Buried Nuclear Waste

Energy Technology Data Exchange (ETDEWEB)

Turick, C; Berry, C.

2012-10-15

Long-term storage of low level radioactive material in below ground concrete disposal units (DUs) (Saltstone Disposal Facility) is a means of depositing wastes generated from nuclear operations of the U.S. Department of Energy. Based on the currently modeled degradation mechanisms, possible microbial induced effects on the structural integrity of buried low level wastes must be addressed. Previous international efforts related to microbial impacts on concrete structures that house low level radioactive waste showed that microbial activity can play a significant role in the process of concrete degradation and ultimately structural deterioration. This literature review examines the recent research in this field and is focused on specific parameters that are applicable to modeling and prediction of the fate of concrete vaults housing stored wastes and the wastes themselves. Rates of concrete biodegradation vary with the environmental conditions, illustrating a need to understand the bioavailability of key compounds involved in microbial activity. Specific parameters require pH and osmotic pressure to be within a certain range to allow for microbial growth as well as the availability and abundance of energy sources like components involved in sulfur, iron and nitrogen oxidation. Carbon flow and availability are also factors to consider in predicting concrete biodegradation. The results of this review suggest that microbial activity in Saltstone, (grouted low level radioactive waste) is unlikely due to very high pH and osmotic pressure. Biodegradation of the concrete vaults housing the radioactive waste however, is a possibility. The rate and degree of concrete biodegradation is dependent on numerous physical, chemical and biological parameters. Results from this review point to parameters to focus on for modeling activities and also, possible options for mitigation that would minimize concrete biodegradation. In addition, key chemical components that drive microbial

Nuclear safety review for qualification of class 1E motor inside containment for nuclear power stations

International Nuclear Information System (INIS)

Li Shixin; Wu Qi; Zhang Yunbo; Wu Caixia

2013-01-01

In nuclear power plants with pressurized water reactors, the review for class 1E motor inside containment qualification process and documents is an important aspect of nuclear safety equipment review, and the reviewers should make evaluations for the qualification test results in terms of the compliance with standard and regulation, and the consistency with inside containment environment. Firstly, this paper introduces the qualification test of class 1E motor inside containment for nuclear power generating stations, such as aging test and design-basis-event test. Second, there is a discussion about typical problems of review. At last, comparison of IEEE334 with RCC-E is conducted and explored. (authors)

IAEA Completes Nuclear Security Review Mission in Indonesia

International Nuclear Information System (INIS)

2014-01-01

A team of International Atomic Energy Agency (IAEA) experts today completed a two-week mission to review nuclear security practices in Indonesia. At the request of the Indonesian Government, the IAEA conducted an International Physical Protection Advisory Service (IPPAS) mission that reviewed the current status of the State's Physical Protection Regime of nuclear and other radioactive material, as well as associated facilities and activities in Indonesia. This included the country's nuclear security-related legislative and regulatory framework and the physical protection systems at the nuclear research sites in Serpong, Bandung and Yogyakarta, as well as radioactive facilities at Bekasi and Cibitung. The mission also reviewed how the recommendations of previous IPPAS missions in 2001 and 2007 had been implemented. The IPPAS team concluded that, since the last missions, Indonesia has improved its national security regime, especially its legislation and regulations, and had introduced new physical protection equipment. It also found that areas remained that required attention and efforts were needed to reach an overall comprehensive and effective nuclear security regime. The team made a number of new recommendations and suggestions aimed at further strengthening the overall regime

On development and improvement of evaluation techniques for strong ground motion

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-08-15

Issues regarding evaluation of active fault and ground motion for formulation of design basis ground motion (Ss) were identified during NISA and NSC seismic safety reviewing activities, which have been conducted in the light of the revision of the relevant seismic regulatory guide in 2006 and the experiences of the Niigataken Chuetsu-oki Earthquake in 2007 and the 2011 off the Pacific Coast of Tohoku Earthquake. In this theme following four subjects were investigated to resolve the important problems for ground motion evaluation, (1) advanced evaluation of ground motion using fault model and uncertainty; (2) improving evaluation of ground motion using attenuation relation of response spectrum; (3) development of advanced technique for ground motion observation and observation tool in deep borehole; (4) improving the evaluation of site effect and seismic wave propagation characteristics. Obtained results will be incorporated into the national safety review and also in the safety standard guidelines of the International Atomic Energy Agency (IAEA) using its Extra-Budgetary Program (IAEA EBP), thereby contributing to technical cooperation in global nuclear seismic safety. (author)

Our response to the earthquake at Onagawa Nuclear Power Station

International Nuclear Information System (INIS)

Hirakawa, Tomoshi

2008-01-01

When the Miyagi Offshore earthquake occurred on August 16, 2005, all three units at the Onagawa NPS were shut down automatically according to the Strong Seismic Acceleration' signal. Our inspection after the earthquake confirmed there was no damage to the equipment of the nuclear power plants, but the analysis of the response spectrum observed at the bedrock showed the earthquake had exceeded the 'design-basis earthquake', at certain periods, so that we implemented a review of the seismic safety of plant facilities. In the review, the ground motion of Miyagi Offshore Earthquake which are predicted to occur in the near future were reexamined based on the observation data, and then 'The Ground Motion for Safety Check' surpassing the supposed ground motion of the largest earthquake was established. The seismic safety of plant facilities, important for safety, was assured. At present, No.1 to No.3 units at Onagawa NPS have returned to normal operation. (author)

IAEA Reviews Niger’s Nuclear Power Infrastructure Development

International Nuclear Information System (INIS)

2018-01-01

An International Atomic Energy Agency (IAEA) team of experts has concluded an eight-day mission to Niger to review its infrastructure development for a nuclear power programme. The Integrated Nuclear Infrastructure Review (INIR) was carried out at the invitation of the Government of the Republic of Niger. Niger, whose economic development is hampered by a lack of consistent electricity supply, is considering a potential role for nuclear power in its energy mix. A country of about 21 million people in Western Africa, Niger is currently ranked as the world’s fourth largest producer of uranium ore. The INIR team observed a strong Government commitment to developing the infrastructure for a nuclear power programme. The Government has established a Strategic Orientation Committee for the Nuclear Power Programme chaired by the Prime Minister, and a National Technical Committee for the Nuclear Power Programme chaired by the President of the Nigerien High Authority for Atomic Energy (HANEA). Those two committees form the Nuclear Energy Programme Implementing Organization (NEPIO). Niger has already completed or initiated several studies related to nuclear infrastructure development, and prepared a comprehensive report summarizing the results.

Nuclear Physics Review

Energy Technology Data Exchange (ETDEWEB)

Walker-Loud, Andre

2014-11-01

Anchoring low-energy nuclear physics to the fundamental theory of strong interactions remains an outstanding challenge. I review the current progress and challenges of the endeavor to use lattice QCD to bridge this connection. This is a particularly exciting time for this line of research as demonstrated by the spike in the number of different collaborative efforts focussed on this problem and presented at this conference. I first digress and discuss the 2013 Ken Wilson Award.

Computer-based control systems of nuclear power plants

International Nuclear Information System (INIS)

Kalashnikov, V.K.; Shugam, R.A.; Ol'shevsky, Yu.N.

1975-01-01

Computer-based control systems of nuclear power plants may be classified into those using computers for data acquisition only, those using computers for data acquisition and data processing, and those using computers for process control. In the present paper a brief review is given of the functions the systems above mentioned perform, their applications in different nuclear power plants, and some of their characteristics. The trend towards hierarchic systems using control computers with reserves already becomes clear when consideration is made of the control systems applied in the Canadian nuclear power plants that pertain to the first ones equipped with process computers. The control system being now under development for the large Soviet reactors of WWER type will also be based on the use of control computers. That part of the system concerned with controlling the reactor assembly is described in detail

Australian Nuclear Science and Technology Organisation strategy review recommendations. Final Report

International Nuclear Information System (INIS)

1994-01-01

In May 1994 the Australian Nuclear Science and Technology Organization (ANSTO)'s Board initiated a comprehensive five month review which purpose was to develop a mission for ANSTO and thus define its role both domestically and internationally. The review took into account the needs of ANSTO stakeholders, analysed ANSTO capabilities as well as available international opportunities. Outcomes of the review included an assessment of the priorities and needs of stakeholders, an understanding of how these needs can be meet, and the resulting resource implications. ANSTO's major mission objectives, as defined in the consultants's report should be: to support the Government's nuclear policies (this objective is paramount), support industrial competitiveness and innovation through technology transfer, as well as to maintain a high quality nuclear science base and to enable academic institutions and other science organizations to perform research by providing access to unique facilities and expertise. The consultants also made recommendations on appropriate management arrangements for ANSTO, an implementation plan, progress milestones and operational targets. Details of the relevance-excellence analysis, commercial customer analysis and justification for recommended activity action imperatives are presented in the appendices. 48 figs

Integrated Nuclear Infrastructure Review (INIR) Missions: The First Six Years

International Nuclear Information System (INIS)

2015-12-01

IAEA Integrated Nuclear Infrastructure Review (INIR) missions are designed to assist Member States in evaluating the status of their national infrastructure for the introduction of a nuclear power programme. INIR missions are conducted upon request from the Member State. Each INIR mission is coordinated and led by the IAEA and conducted by a team of IAEA staff and international experts drawn from Member States which have experience in different aspects of developing and deploying nuclear infrastructure. INIR missions cover the 19 infrastructure issues described in Milestones in the Development of a National Infrastructure for Nuclear Power, IAEA Nuclear Energy Series No. NG-G-3.1, published in 2007 and revised in 2015, and the assessment is based on an analysis of a self-evaluation report prepared by the Member State, a review of the documents it provides and interviews with its key officials. Phase 1 INIR missions evaluate the status of the infrastructure to achieve Milestone 1 (Ready to make a knowledgeable commitment to a nuclear power programme). Phase 2 INIR missions evaluate the status of the infrastructure to achieve Milestone 2 (Ready to invite bids/negotiate a contract for the first nuclear power plant). From 2009 to 2014, 14 IAEA INIR missions and follow-ups were conducted in States embarking on a nuclear power programme and one State expanding its programme. During this time, considerable experience was gained by the IAEA on the conduct of INIR missions, and this feedback has been used to continually improve the overall INIR methodology. The INIR methodology has thus evolved and is far more comprehensive today than in 2009. Despite the limited number of INIR missions conducted, some common findings were identified in Member States embarking on nuclear power programmes. This publication summarizes the results of the missions and highlights the most significant areas in which recommendations were made

Review of Current Nuclear Vacuum System Technologies

International Nuclear Information System (INIS)

Carroll, M.; McCracken, J.; Shope, T.

2003-01-01

Nearly all industrial operations generate unwanted dust, particulate matter, and/or liquid wastes. Waste dust and particulates can be readily tracked to other work locations, and airborne particulates can be spread through ventilation systems to all locations within a building, and even vented outside the building - a serious concern for processes involving hazardous, radioactive, or nuclear materials. Several varieties of vacuum systems have been proposed and/or are commercially available for clean up of both solid and liquid hazardous and nuclear materials. A review of current technologies highlights both the advantages and disadvantages of the various systems, and demonstrates the need for a system designed to address issues specific to hazardous and nuclear material cleanup. A review of previous and current hazardous/nuclear material cleanup technologies is presented. From simple conventional vacuums modified for use in industrial operations, to systems specifically engineered for such purposes, the advantages and disadvantages are examined in light of the following criteria: minimal worker exposure; minimal secondary waste generation;reduced equipment maintenance and consumable parts; simplicity of design, yet fully compatible with all waste types; and ease of use. The work effort reviews past, existing and proposed technologies in light of such considerations. Accomplishments of selected systems are presented, including identified areas where technological improvements could be suggested

Joliot-Curie nuclear physics school 1983

International Nuclear Information System (INIS)

The 1983 Joliot-Curie school was aimed at reviewing some outstanding aspects of current research in nuclear spectroscopy. The recent developments of high and very high spin states study are presented. The most important experimental methods and explaining concepts concerning the ground states and the first excited levels of nuclei far from beta stability are reviewed. Spin-isospin excitations are dealt with from a theoretical point of view and also for the most outstanding experimental results. At last, basic concepts and limits of the shell model nuclear description are outlined and illustrated [fr

CORR Guidelines. Preparing and Conducting Review Missions of Construction Project Readiness for Nuclear Power Plants

International Nuclear Information System (INIS)

2013-01-01

The construction readiness review (CORR) mission for nuclear power plant projects has been established with the aim of conducting peer reviews of construction projects related to nuclear power plants. Such a mission provides a detailed assessment of readiness for construction, construction progress, readiness for turnover, as well as recommendations for improvement. Organizations in Member States, such as nuclear utilities, owners, regulators and technical support organizations, can benefit from such reviews. A team of international experts with complementing specialities will conduct the CORR mission. The review is based on appropriate IAEA publications, such as IAEA Safety Standards Series Guides and IAEA Nuclear Energy Series publications, as well as on internationally recognized project and construction management guides. Mission findings are summarized in a mission report, which includes a list of recommendations, suggestions and identified good practices. The review is not intended to be a regulatory inspection or an audit against international codes and standards. Rather, it is a peer review aimed at improving implementation processes and procedures through an exchange of technical experiences and practices at the working level. The mission is applicable at any stage of a nuclear power plant construction project, although two specific phases are targeted: (1) start of construction mission (Phase 1 mission) and (2) an in-progress mission (Phase 2 mission). Missions are initiated when official requests are submitted by Member States through the appropriate IAEA channels

Review of oxidation rates of DOE spent nuclear fuel : Part 1 : nuclear fuel

International Nuclear Information System (INIS)

Hilton, B.A.

2000-01-01

The long-term performance of Department of Energy (DOE) spent nuclear fuel (SNF) in a mined geologic disposal system depends highly on fuel oxidation and subsequent radionuclide release. The oxidation rates of nuclear fuels are reviewed in this two-volume report to provide a baseline for comparison with release rate data and technical rationale for predicting general corrosion behavior of DOE SNF. The oxidation rates of nuclear fuels in the DOE SNF inventory were organized according to metallic, Part 1, and non-metallic, Part 2, spent nuclear fuels. This Part 1 of the report reviews the oxidation behavior of three fuel types prototypic of metallic fuel in the DOE SNF inventory: uranium metal, uranium alloys and aluminum-based dispersion fuels. The oxidation rates of these fuels were evaluated in oxygen, water vapor, and water. The water data were limited to pure water corrosion as this represents baseline corrosion kinetics. Since the oxidation processes and kinetics discussed in this report are limited to pure water, they are not directly applicable to corrosion rates of SNF in water chemistry that is significantly different (such as may occur in the repository). Linear kinetics adequately described the oxidation rates of metallic fuels in long-term corrosion. Temperature dependent oxidation rates were determined by linear regression analysis of the literature data. As expected the reaction rates of metallic fuels dramatically increase with temperature. The uranium metal and metal alloys have stronger temperature dependence than the aluminum dispersion fuels. The uranium metal/water reaction exhibited the highest oxidation rate of the metallic fuel types and environments that were reviewed. Consequently, the corrosion properties of all DOE SNF may be conservatively modeled as uranium metal, which is representative of spent N-Reactor fuel. The reaction rate in anoxic, saturated water vapor was essentially the same as the water reaction rate. The long-term intrinsic

Illumination compensation in ground based hyperspectral imaging

Science.gov (United States)

Wendel, Alexander; Underwood, James

2017-07-01

Hyperspectral imaging has emerged as an important tool for analysing vegetation data in agricultural applications. Recently, low altitude and ground based hyperspectral imaging solutions have come to the fore, providing very high resolution data for mapping and studying large areas of crops in detail. However, these platforms introduce a unique set of challenges that need to be overcome to ensure consistent, accurate and timely acquisition of data. One particular problem is dealing with changes in environmental illumination while operating with natural light under cloud cover, which can have considerable effects on spectral shape. In the past this has been commonly achieved by imaging known reference targets at the time of data acquisition, direct measurement of irradiance, or atmospheric modelling. While capturing a reference panel continuously or very frequently allows accurate compensation for illumination changes, this is often not practical with ground based platforms, and impossible in aerial applications. This paper examines the use of an autonomous unmanned ground vehicle (UGV) to gather high resolution hyperspectral imaging data of crops under natural illumination. A process of illumination compensation is performed to extract the inherent reflectance properties of the crops, despite variable illumination. This work adapts a previously developed subspace model approach to reflectance and illumination recovery. Though tested on a ground vehicle in this paper, it is applicable to low altitude unmanned aerial hyperspectral imagery also. The method uses occasional observations of reference panel training data from within the same or other datasets, which enables a practical field protocol that minimises in-field manual labour. This paper tests the new approach, comparing it against traditional methods. Several illumination compensation protocols for high volume ground based data collection are presented based on the results. The findings in this paper are

Practical Applications of Cosmic Ray Science: Spacecraft, Aircraft, Ground-Based Computation and Control Systems, Exploration, and Human Health and Safety

Science.gov (United States)

Koontz, Steve

2015-01-01

In this presentation a review of galactic cosmic ray (GCR) effects on microelectronic systems and human health and safety is given. The methods used to evaluate and mitigate unwanted cosmic ray effects in ground-based, atmospheric flight, and space flight environments are also reviewed. However not all GCR effects are undesirable. We will also briefly review how observation and analysis of GCR interactions with planetary atmospheres and surfaces and reveal important compositional and geophysical data on earth and elsewhere. About 1000 GCR particles enter every square meter of Earth’s upper atmosphere every second, roughly the same number striking every square meter of the International Space Station (ISS) and every other low- Earth orbit spacecraft. GCR particles are high energy ionized atomic nuclei (90% protons, 9% alpha particles, 1% heavier nuclei) traveling very close to the speed of light. The GCR particle flux is even higher in interplanetary space because the geomagnetic field provides some limited magnetic shielding. Collisions of GCR particles with atomic nuclei in planetary atmospheres and/or regolith as well as spacecraft materials produce nuclear reactions and energetic/highly penetrating secondary particle showers. Three twentieth century technology developments have driven an ongoing evolution of basic cosmic ray science into a set of practical engineering tools needed to design, test, and verify the safety and reliability of modern complex technological systems and assess effects on human health and safety effects. The key technology developments are: 1) high altitude commercial and military aircraft; 2) manned and unmanned spacecraft; and 3) increasingly complex and sensitive solid state micro-electronics systems. Space and geophysical exploration needs drove the development of the instruments and analytical tools needed to recover compositional and structural data from GCR induced nuclear reactions and secondary particle showers. Finally, the

Nuclear bodies in the oocyte nucleus of ground beetles are enriched in snRNPs.

Science.gov (United States)

Jaglarz, M K

2001-08-01

Within the oocyte nucleus of many insect species, a variable number of intensely stained spherical bodies occur. These nuclear bodies differ significantly from nucleoli and their precise role in nuclei has not been elucidated yet. I have examined some of the histochemical properties as well as the molecular composition of these structures in a representative of ground (carabid) beetles. I demonstrate, using molecular markers, that the nuclear bodies are composed of small nuclear RNAs and associated proteins, including p80 coilin. Hence, they correspond to Cajal bodies (= coiled bodies) described in somatic cell nuclei as well as oocyte germinal vesicles in plant and animal organisms. It is suggested that Cajal bodies in the carabid germinal vesicle serve as a storage site for splicing factors.

Reviewing industrial safety in nuclear power plants

International Nuclear Information System (INIS)

1990-02-01

This document contains guidance and reference materials for Operational Safety Review Team (OSART) experts, in addition to the OSART Guidelines (TECDOC-449), for use in the review of industrial safety activities at nuclear power plants. It sets out objectives for an excellent industrial safety programme, and suggests investigations which should be made in evaluating industrial safety programmes. The attributes of an excellent industrial safety programme are listed as examples for comparison. Practical hints for reviewing industrial safety are discussed, so that the necessary information can be obtained effectively through a review of documents and records, discussions with counterparts, and field observations. There are several annexes. These deal with major features of industrial safety programmes such as safety committees, reporting and investigation systems and first aid and medical facilities. They include some examples which are considered commendable. The document should be taken into account not only when reviewing management, organization and administration but also in the review of related areas, such as maintenance and operations, so that all aspects of industrial safety in an operating nuclear power plant are covered

Reviewing surveillance activities in nuclear power plants

International Nuclear Information System (INIS)

1989-03-01

This document provides guidance to Operational Safety Review Teams (OSARTs) for reviewing surveillance activities at a nuclear power plant. In addition, the document contains reference material to support the review of surveillance activities, to assist within the Technical Support area and to ensure consistency between individual reviews. Drafts of the document have already been used on several OSART missions and found to be useful. The document first considers the objectives of an excellent surveillance programme. Investigations to determine the quality of the surveillance programme are then discussed. The attributes of an excellent surveillance programme are listed. Advice follows on how to phrase questions so as to obtain an informative response on surveillance features. Finally, specific equipment is mentioned that should be considered when reviewing functional tests. Four annexes provide examples drawn from operating nuclear power plants. They were selected to supplement the main text of the document with the best international practices as found in OSART reviews. They should in no way limit the acceptance and development of alternative approaches that lead to equivalent or better results. Refs, figs and tabs

Ground Shock Resistant of Buried Nuclear Power Plant Facility

International Nuclear Information System (INIS)

Ornai, D.; Adar, A.; Gal, E.

2014-01-01

Nuclear Power Plant (NPP) might be subjected to hostile attacks such as Earth Penetrating Weapons (EPW) that carry explosive charges. Explosions of these weapons near buried NPP facility might cause collapse, breaching, spalling, deflection, shear, rigid body motion (depending upon the foundations), and in-structure shock. The occupants and the equipment in the buried facilities are exposed to the in-structure motions, and if they are greater than their fragility values than occupants might be wounded or killed and the equipment might be damaged, unless protective measures will be applied. NPP critical equipment such as pumps are vital for the normal safe operation since it requires constant water circulation between the nuclear reactor and the cooling system, including in case of an immediate shut down. This paper presents analytical- semi empirical formulation and analysis of the explosion of a penetrating weapon with a warhead of 100kgs TNT (Trinitrotoluene) that creates ground shock effect on underground NPP structure containing equipment, such as a typical pump. If the in-structure spectral shock is greater than the pump fragility values than protective measures are required, otherwise a real danger to the NPP safety might occur

Seismic review of existing nuclear power plants

International Nuclear Information System (INIS)

Yanev, P.I.; Mayes, R.L.; Jones, L.R.

1975-01-01

Because of developments in the fields of earthquake and structural engineering over the last two decades, the codes, standards and design criteria for Nuclear Power Plants and other critical structures have changed substantially. As a result, plants designed only a few years ago do not satisfy the requirements for new plants. Accordingly, the Regulatory Agencies are requiring owners of older Nuclear Power Plants to re-qualify the plants seismically, using codes, standards, analytical techniques and knowledge developed in recent years. Seismic review consists of three major phases: establishing the design and performance criteria, re-qualifying the structures, and re-qualifying the equipment. The authors of the paper have been recently involved in the seismic review of existing nuclear power plants in the United States. This paper is a brief summary of their experiences

A review of calixarene applications in nuclear industries

International Nuclear Information System (INIS)

Bahram Mokhtari; Iranian Offshore Oil Company, Lavan Island; Kobra Pourabdollah; Naser Dallali

2011-01-01

Calixarenes has been subject to extensive research in development of many extractants, transporters, stationary phases, electrode ionophores and optical and electrochemical sensors over the past four decades. In this paper, the nuclear applications of calixarenes are summarized in six fields including complexation studies, solvent extraction, membrane transport, chromatography, luminescent and colorimetric applications, and electroanalytical applications. In the first to fourth sections, the extractability, extraction equilibria and extraction constants of lanthanide, actinide and other nuclear waste cations ions, which were subjected to solvent extraction by the macrocyclic ligands, are reviewed. In two last sections, the analytical applications of calixarene complexes towards nuclear waste cations, including spectroscopic and electroanalytic sensors, are discussed. The examples described in this review illustrate the potential of calixarene derivatives in the rapidly growing field of cations recognition in nuclear wastes. (author)

The review of online maintenance in nuclear power plants

International Nuclear Information System (INIS)

Yamamoto, Tetsuya

2009-01-01

The Nuclear and Industrial Safety Agency (NISA) has begun the review of online maintenance in nuclear power plants in its advisory committee. The experts in the committee study the necessary actions in the regulation and safe and secure measure to implement the online maintenance. This paper explains the current progress of the review. (author)

Review on the role of nuclear power

International Nuclear Information System (INIS)

Cao Chi; Le Van Hong; Nguyen Tri Ho

1993-03-01

This report consists of 2 parts. The first part reviews opinions against nuclear power on the aspects: waste disposal, safety and environment, financial; technology, etc. and gives results of a preliminary survey for nuclear power in Vietnam among scientists in 1990. The second part presents advanced reactor concepts and advantages of nuclear power to economy and environment in comparison with other energy sources. (N.H.A). 39 refs, 9 figs, 2 tabs

IAEA Concludes Safety Review at Gravelines Nuclear Power Plant, France

International Nuclear Information System (INIS)

2012-01-01

Full text: An IAEA-led international team of nuclear safety experts noted a series of good practices and made recommendations to reinforce some safety measures during a review of operational safety at France's Gravelines Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 12 November 2012, focused on aspects essential to the safe operation of the NPP. The team was composed of experts from Bulgaria, China, Germany, Hungary, Japan, Romania, Slovakia, South Africa, Spain, Ukraine and the IAEA. The review covered the areas of management, organization and administration; training and qualification; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their possible use elsewhere. Examples include the following: - The Power Plant uses a staff-skills mapping process that significantly enhances knowledge of the facility's collective and individual skills and provides proactive management to address the loss of such skills; - As a measure to reduce the risk of workers' radiation exposure, the Power Plant uses a system to ensure that dose rate measurements are carried out at a precise distance from the source of radiation; and - Flood protection of the Power Plant is supported by special technical guidance documents and associated arrangements. The team identified a number of proposals for improvements to operational safety at Gravelines NPP. Examples include the following: - The Power Plant should reinforce its measures to prevent foreign objects from entering plant systems; - The Power Plant should ensure the 24-hour presence of an operator

Review of Soviet studies related to peaceful underground nuclear explosions

International Nuclear Information System (INIS)

Lin, W.

1978-01-01

Theoretical and empirical studies of contained and crater-forming underground nuclear explosions by USSR investigators are reviewed and summarized. Published data on U.S., USSR, and French cavity-forming nuclear explosions are compared with those predicted by the formula. Empirical studies on U.S. and USSR cratering explosions, both high explosions, both high explosive and nuclear are summarized. The parameters governing an excavation explosion are reviewed

Evaluation and summary of seismic response of above ground nuclear power plant piping to strong motion earthquakes

International Nuclear Information System (INIS)

Stevenson, J.D.

1985-01-01

The purpose of this paper is to summarize the observations and experience which has been developed relative to the seismic behavior of above-ground, building-supported, industrial type piping (similar to piping used in nuclear power plants) in strong motion earthquakes. The paper also contains observations regarding the response of piping in experimental tests which attempted to excite the piping to failure. Appropriate conclusions regarding the behavior of such piping in large earthquakes and recommendations as to future design of such piping to resist earthquake motion damage are presented based on observed behavior in large earthquakes and simulated shake table testing

Integration of a satellite ground support system based on analysis of the satellite ground support domain

Science.gov (United States)

Pendley, R. D.; Scheidker, E. J.; Levitt, D. S.; Myers, C. R.; Werking, R. D.

1994-11-01

This analysis defines a complete set of ground support functions based on those practiced in real space flight operations during the on-orbit phase of a mission. These functions are mapped against ground support functions currently in use by NASA and DOD. Software components to provide these functions can be hosted on RISC-based work stations and integrated to provide a modular, integrated ground support system. Such modular systems can be configured to provide as much ground support functionality as desired. This approach to ground systems has been widely proposed and prototyped both by government institutions and commercial vendors. The combined set of ground support functions we describe can be used as a standard to evaluate candidate ground systems. This approach has also been used to develop a prototype of a modular, loosely-integrated ground support system, which is discussed briefly. A crucial benefit to a potential user is that all the components are flight-qualified, thus giving high confidence in their accuracy and reliability.

A review of ground-based heavy-ion radiobiology relevant to space radiation risk assessment: Part II. Cardiovascular and immunological effects

Energy Technology Data Exchange (ETDEWEB)

Blakely, Eleanor A.; Chang, Polly Y.

2007-02-26

The future of manned space flight depends on an analysis of the numerous potential risks of travel into deep space. Currently no radiation dose limits have been established for these exploratory missions. To set these standards more information is needed about potential acute and late effects on human physiology from appropriate radiation exposure scenarios, including pertinent radiation types and dose rates. Cancer risks have long been considered the most serious late effect from chronic daily relatively low-dose exposures to the complex space radiation environment. However, other late effects from space radiation exposure scenarios are under study in ground-based accelerator facilities and have revealed some unique particle radiation effects not observed with conventional radiations. A comprehensive review of pertinent literature that considers tissue effects of radiation leading to functional detriments in specific organ systems has recently been published (NCRP National Council on Radiation Protection and Measurements, Information Needed to Make Radiation Protection Recommendations for Space Missions Beyond Low-Earth Orbit, Report 153, Bethesda, MD, 2006). This paper highlights the review of two non-cancer concerns from this report: cardiovascular and immunological effects.

Design basis ground motion (Ss) required on new regulatory guide

International Nuclear Information System (INIS)

Kamae, Katsuhiro

2013-01-01

New regulatory guide is enforced on July 8. Here, it is introduced how the design basis ground motion (Ss) for seismic design of nuclear power reactor facilities was revised on the new guide. Ss is formulated as two types of earthquake ground motions, earthquake ground motions with site specific earthquake source and with no such specific source locations. The latter is going to be revised based on the recent observed near source ground motions. (author)

Human factors engineering plan for reviewing nuclear plant modernization programs

International Nuclear Information System (INIS)

O'Hara, John; Higgins, James

2004-12-01

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

Human factors engineering plan for reviewing nuclear plant modernization programs

Energy Technology Data Exchange (ETDEWEB)

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

2004-12-01

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

Catawba nuclear station preoperational ALARA review

International Nuclear Information System (INIS)

Deal, W.P.

1985-01-01

This paper describes the particular emphasis placed on preoperational as los as reasonably achievable (ALARA) considerations at Duke Power's Catawba Nuclear Station. A strong station commitment to the ALARA philosophy, and review of existing capabilities, led to development of an aggressive two-part ALARA program. Capabilities consisted of sufficient numbers of available personnel, lengthy lead time during construction, a very detailed plastic model, and a sister plant of similar design. The program, as developed, consisted of a preoperational program, which looked at design and construction aspects of ALARA, and the operational program, dealing with the ALARA committee and operational problems. MAnagement's philosophy of holding everyone responsible for ALARA provided the motivation to organize the preoperational program to use that resource. The Health Physics group accepted responsibility for development, coordination, and reviewer training. The problem provided a base to build on as station personnel gained experience in their own crafts and radiation protection in general

Review of the 6th Pacific Basin Nuclear Conference

International Nuclear Information System (INIS)

Zhao Renkai; Jiang Yue; Yao Minzhi; Tong Yunxian; Ruan Keqiang; Luo Cheng; Liu Dingqin; Yang Chuande; Tu Zhuguo.

1987-01-01

This paper reviews the 6th Pacific Basin Nuclear Conference on eight monographs. These monographs are present status and prospects of nucliar energy, advancement of commercial power reactor, advanced nuclear reactor and research and test reactor, perspectives on nuclear power safety in 1990's, application of radioisotope and irradiation technique, advancement in nuclear fuel, improvement of nuclear power plant management and regional cooperation and personnel training

The review conference mechanism in nuclear law: issues and opportunities

International Nuclear Information System (INIS)

Stoiber, C.

2009-01-01

This paper seeks to assess the major issues arising from reliance on the review conference mechanism as a measure for enhancing the effectiveness of multilateral legal instruments, particularly those in the nuclear field. In view of the perceived failure of the 2005 review conference of the Parties to the Treaty on the non-proliferation of nuclear weapons and the need to avoid a similar result at the upcoming 2010 review conference, it is hoped that this analysis will provide a timely review of the review conference mechanism. (N.C.)

Interagency Advanced Power Group, Joint Electrical and Nuclear Working Group, meeting minutes, November 16--17, 1993

Energy Technology Data Exchange (ETDEWEB)

1993-12-31

Reports on soldier power R&D review, N-MCT power electronic building blocks, silicon carbide power semiconductor work, and ground based radar were made to the Power Conditioning Panel. An introduction to high temperature electronics needs, research and development was made to the High Temperature Electronics Subcommittee. The Pulse Power Panel received reports on the navy ETC gun, and army pulse power. The Superconductivity Panel received reports on high-tc superconducting wires, superconducting magnetic energy storage, and superconducting applications. The Nuclear Working Group received presentations on the Topaz nuclear power program, and space nuclear work in the Department of Energy.

Tank farm nuclear criticality review

International Nuclear Information System (INIS)

Bratzel, D.R.

1996-01-01

The technical basis for the nuclear criticality safety of stored wastes at the Hanford Site Tank Farm Complex was reviewed by a team of senior technical personnel whose expertise covered all appropriate aspects of fissile materials chemistry and physics. The team concluded that the detailed and documented nucleonics-related studies underlying the waste tanks criticality safety basis were sound. The team concluded that, under current plutonium inventories and operating conditions, a nuclear criticality accident is incredible in any of the Hanford single-shell tanks (SST), double-shell tanks (DST), or double-contained receiver tanks (DCRTS) on the Hanford Site

State-of-the-art review of materials properties of nuclear waste forms

International Nuclear Information System (INIS)

Mendel, J.E.; Nelson, R.D.; Turcotte, R.P.; Gray, W.J.; Merz, M.D.; Roberts, F.P.; Weber, W.J.; Westsik, J.H. Jr.; Clark, D.E.

1981-04-01

The Materials Characterization Center (MCC) was established at the Pacific Northwest Laboratory to assemble a standardized nuclear waste materials data base for use in research, systems and facility design, safety analyses, and waste management decisions. This centralized data base will be provided through the means of a Nuclear Waste Materials Handbook. The first issue of the Handbook will be published in the fall of 1981 in looseleaf format so that it can be updated as additional information becomes available. To ensure utmost reliability, all materials data appearing in the Handbook will be obtained by standard procedures defined in the Handbook and approved by an independent Materials Review Board (MRB) comprised of materials experts from Department of Energy laboratories and from universities and industry. In the interim before publication of the Handbook there is need for a report summarizing the existing materials data on nuclear waste forms. This review summarizes materials property data for the nuclear waste forms that are being developed for immobilization of high-level radioactive waste. It is intended to be a good representation of the knowledge concerning the properties of HLW forms as of March 1981. The table of contents lists the following topics: introduction which covers waste-form categories, and important waste-form materials properties; physical properties; mechanical properties; chemical durability; vaporization; radiation effects; and thermal phase stability

Second review meeting of the Contracting Parties to the Convention on Nuclear Safety

International Nuclear Information System (INIS)

Rafferty, Barbara

2002-01-01

The Second Review Meeting of the Contracting Parties to the Convention on Nuclear Safety was held in the Headquarters of the International Atomic Energy Agency in Vienna from 15-26 April 2002, under the chairmanship of the President, Mr Miroslav Gregoric, Director of the Slovenian Nuclear Safety Authority. The Convention on Nuclear Safety entered into force in October 1996, has been signed by sixty-five States and ratified by fifty-four, bringing within its scope 428 of the 448 nuclear reactors worldwide. The Convention aims to achieve and maintain a high level of nuclear safety worldwide, through inter alia enhancement of national measures and international co-operation. Obligations on Contracting Parties in accordance with the Convention include: the establishment and maintenance of a legislative and regulatory framework to govern the safety of land-based civil nuclear installations; the allocation of adequate financial and human resources to support the safety objectives; ensuring that all reasonably practicable improvements to safety are made as a matter of urgency. Adherence to this Convention entails two basic commitments by each Contracting Party: to prepare and make available a national report for review; and to subject its national report to a peer review by the other Contracting Parties. Thus, being a Contracting Party to this Convention involves: including in the national report a self-assessment of steps and measures already taken and in progress to implement the Convention obligations; taking an active part in an open and transparent review of its national report and the Reports of other Contracting Parties; and a commitment to a continuous learning and improving process, something which is a key element of a strong safety culture. The peer review of national reports takes place every three years, the first having been held in 1999. The Second Review Meeting was attended by delegates from 46 contracting parties. During the review certain issues were

Prediction of ground motion from underground nuclear weapons tests as it relates to siting of a nuclear waste storage facility at NTS and compatibility with the weapons test program

International Nuclear Information System (INIS)

Vortman, L.J. IV.

1980-04-01

This report assumes reasonable criteria for NRC licensing of a nuclear waste storage facility at the Nevada Test Site where it would be exposed to ground motion from underground nuclear weapons tests. Prediction equations and their standard deviations have been determined from measurements on a number of nuclear weapons tests. The effect of various independent parameters on standard deviation is discussed. That the data sample is sufficiently large is shown by the fact that additional data have little effect on the standard deviation. It is also shown that coupling effects can be separated out of the other contributions to the standard deviation. An example, based on certain licensing assumptions, shows that it should be possible to have a nuclear waste storage facility in the vicinity of Timber Mountain which would be compatible with a 700 kt weapons test in the Buckboard Area if the facility were designed to withstand a peak vector acceleration of 0.75 g. The prediction equation is a log-log linear equation which predicts acceleration as a function of yield of an explosion and the distance from it

Systematic review of perceptive studies on nuclear risk

International Nuclear Information System (INIS)

Freitas, Mariana Gama de

2014-01-01

This present work contains the study of risk perception in different areas of interaction. For it was made an analysis using methodology previously recognized and tested: a systematic review in the search for better understanding of the perception of risk in the nuclear area. Through this study it was possible to understand the potential of the systematic review as a tool for information that encompass the perception of risk as a whole. Making it possible to trace parameters to find out why the world's people have an aversion to certain matters relating to nuclear energy. Considering that if you can understand what drives the people has disgust on nuclear area, it is probably possible to create alternatives to remedy this lack of information and knowledge about the area. Causing the population to realize the benefits that nuclear power brings to people. (author)

Key Response Planning Factors for the Aftermath of Nuclear Terrorism

Energy Technology Data Exchange (ETDEWEB)

Buddemeier, B R; Dillon, M B

2009-01-21

Despite hundreds of above-ground nuclear tests and data gathered from Hiroshima and Nagasaki, the effects of a ground-level, low-yield nuclear detonation in a modern urban environment are still the subject of considerable scientific debate. Extensive review of nuclear weapon effects studies and discussions with nuclear weapon effects experts from various federal agencies, national laboratories, and technical organizations have identified key issues and bounded some of the unknowns required to support response planning for a low-yield, ground-level nuclear detonation in a modern U.S. city. This study, which is focused primarily upon the hazards posed by radioactive fallout, used detailed fallout predictions from the advanced suite of three-dimensional (3-D) meteorology and plume/fallout models developed at Lawrence Livermore National Laboratory (LLNL), including extensive global Key Response Planning Factors for the Aftermath of Nuclear Terrorism geographical and real-time meteorological databases to support model calculations. This 3-D modeling system provides detailed simulations that account for complex meteorology and terrain effects. The results of initial modeling and analysis were presented to federal, state, and local working groups to obtain critical, broad-based review and feedback on strategy and messaging. This effort involved a diverse set of communities, including New York City, National Capitol Regions, Charlotte, Houston, Portland, and Los Angeles. The largest potential for reducing casualties during the post-detonation response phase comes from reducing exposure to fallout radiation. This can be accomplished through early, adequate sheltering followed by informed, delayed evacuation.B The response challenges to a nuclear detonation must be solved through multiple approaches of public education, planning, and rapid response actions. Because the successful response will require extensive coordination of a large number of organizations, supplemented by

Nuclear safety review for the year 1997

International Nuclear Information System (INIS)

1998-12-01

The Nuclear Safety Review attempts to summarize the global nuclear safety scene during 1997. It starts with discussion of significant safety related events worldwide: International cooperation; reactor facilities; radioactive waste management; medical uses of radiation sources; events at other facilities and transport of radioactive material. This is followed by a description of principal IAEA activities that contributed to global nuclear safety, namely: legally binding international agreements; non-binding safety standards and their application. The third part highlights developments in Member States as they reported them. The review closes with a description of issues that are likely to be prominent in the coming year(s). A draft version was submitted to the March 1998 session of the IAEA Board of Governors, and this final version has been prepared in light of the discussion in the Board and was submitted for information to the 42nd session of the IAEA General Conference

Reaching for the stars - New developments in ground-based astronomy

CERN Document Server

CERN. Geneva

2015-01-01

I will briefly review the state-of-the-art in ground-based astronomy - both on the telescope side and the instrument side. Interesting parallels can be drawn in cost, construction and operations with the particle physics facilities. I will then present some recent results in the two hottest topics in astronomy, driving the requests for more advanced facilities: exoplanets and the hunt for life beyond the solar system (calling for Extremely Large Telescope); and cosmology and the understanding of dark energy (calling for large survey telescopes). This will lead to a description of the latest telescope project developments on the ground: the on-going construction of the Large Synoptic Telescope on a quest to better understand dark energy, and the start of the construction of three Extremely Large Telescopes by European and US-led international consortia, hoping to find life on planets around nearby stars.   ATS Seminars Organisers: H. Burkhardt (BE), M. Modena (TE), T. Stora (EN) Coffee / tea will ...

Base isolation for nuclear power and nuclear material facilities

International Nuclear Information System (INIS)

Eidinger, J.M.; Kircher, C.A.; Vaidya, N.; Constantinou, M.; Kelly, J.M.; Seidensticker, R.; Tajirian, F.F.; Ovadia, D.

1989-01-01

This report serves to document the status of the practice for the use of base isolation systems in the design and construction of nuclear power and nuclear material facilities. The report first describes past and current (1989) applications of base isolation in nuclear facilities. The report then provides a brief discussion of non-nuclear applications. Finally, the report summarizes the status of known base-isolation codes and standards

Nuclear Safety: Technical progress review, January--March 1989

Energy Technology Data Exchange (ETDEWEB)

Silver, E. G. [ed.

1989-01-01

This review journal covers significant developments in the field of nuclear safety. Its scope includes 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.

Nuclear computational science a century in review

CERN Document Server

Azmy, Yousry

2010-01-01

Nuclear engineering has undergone extensive progress over the years. In the past century, colossal developments have been made and with specific reference to the mathematical theory and computational science underlying this discipline, advances in areas such as high-order discretization methods, Krylov Methods and Iteration Acceleration have steadily grown. Nuclear Computational Science: A Century in Review addresses these topics and many more; topics which hold special ties to the first half of the century, and topics focused around the unique combination of nuclear engineering, computational

Review of operating history at the Palisades Nuclear Plant

International Nuclear Information System (INIS)

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

1982-01-01

the Systematic Evaluation Program Branch (SEPB) of the Nuclear Regulatory Commission (NRC) is conducting the Systematic Evaluation Program whose purpose is to determine the safety margins of the design and operation of the eleven oldest operating commercial nuclear power plants in the United States. A portion of the SEP includes the compilation and interpretation of operational occurrences at these plants. This summary describes the methodology and results of the operational experience review of Palisades Nuclear Plant. The review includes a detailed examination of the operating experience in two segments - plant shutdowns and power reductions, and reportable events

ESRS guidelines for software safety reviews. Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

The IAEA provides safety review services to assist Member States in the application of safety standards and, in particular, to evaluate and facilitate improvements in nuclear power plant safety performance. Complementary to the Operational Safety Review Team (OSART) and the International Regulatory Review Team (IRRT) services are the Engineering Safety Review Services (ESRS), which include reviews of siting, external events and structural safety, design safety, fire safety, ageing management and software safety. Software is of increasing importance to safety in nuclear power plants as the use of computer based equipment and systems, controlled by software, is increasing in new and older plants. Computer based devices are used in both safety related applications (such as process control and monitoring) and safety critical applications (such as reactor protection). Their dependability can only be ensured if a systematic, fully documented and reviewable engineering process is used. The ESRS on software safety are designed to assist a nuclear power plant or a regulatory body of a Member State in the review of documentation relating to the development, application and safety assessment of software embedded in computer based systems important to safety in nuclear power plants. The software safety reviews can be tailored to the specific needs of the requesting organization. Examples of such reviews are: project planning reviews, reviews of specific issues and reviews prior final acceptance. This report gives information on the possible scope of ESRS software safety reviews and guidance on the organization and conduct of the reviews. It is aimed at Member States considering these reviews and IAEA staff and external experts performing the reviews. The ESRS software safety reviews evaluate the degree to which software documents show that the development process and the final product conform to international standards, guidelines and current practices. Recommendations are

Review of the nuclear liability act

International Nuclear Information System (INIS)

1990-01-01

There has always been concern that nuclear materials have the potential to cause injury and property damage. For this reason, nuclear operators have always been required by national regulatory authorities to exercise special precautions in the operation of their facilities. Federal legislation was drafted in Canada as the Nuclear Liability Act in 1970. The Act ensures that funds are available from all operators of nuclear facilities to provide financial compensation to third parties for injuries or damages suffered as a result of a nuclear incident; at the same time the Act provides protection to the operators by limiting their related liability. The Act also protects persons other than operators. The review of the Act has progressed in stages. The first stage was conducted by the staff of the Atomic Energy Control Board and catalogued previously identified difficulties with the Act. The second stage was a preliminary examination of the Act by an Interdepartmental Working Group. 2 figs

Interagency Nuclear Safety Review Panel Power System Subpanel review for the Ulysses mission

International Nuclear Information System (INIS)

McCulloch, W.H.

1991-01-01

As part of the Interagency Nuclear Safety Review Panel's assessment of the nuclear safety of NASA's Ulysses Mission to investigate properties of the sun, the Power System Subpanel has reviewed the safety analyses and risk evaluations done for the General Purpose Heat Source-Radioisotope Thermoelectric Generator which provides on-board electrical power for the spacecraft. This paper summarizes the activities and results of that review. In general, the approach taken in the primary analysis, executed by the General Electric Company under contract to the Department of Energy, and the resulting conclusions were confirmed by the review. However, the Subpanel took some exceptions and modified the calculations accordingly, producing an independent evaluation of potential releases of radioactive fuel in launch and reentry accidents. Some of the more important of these exceptions are described briefly

Concept study of a hydrogen containment process during nuclear thermal engine ground testing

OpenAIRE

Wang, Ten-See; Stewart, Eric T.; Canabal, Francisco

2016-01-01

A new hydrogen containment process was proposed for ground testing of a nuclear thermal engine. It utilizes two thermophysical steps to contain the hydrogen exhaust. First, the decomposition of hydrogen through oxygen-rich combustion at higher temperature; second, the recombination of remaining hydrogen with radicals at low temperature. This is achieved with two unit operations: an oxygen-rich burner and a tubular heat exchanger. A computational fluid dynamics methodology was used to analyze ...

A Review on the Regulatory Strategy of Human Factors Engineering Consideration in Pakistan Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Sohail, Sabir [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Choi, Seong Nam [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2013-10-15

In this paper, the legal and regulatory infrastructure available in Pakistan for HFE requirements is assessed, and the methodology for strengthening of legal infrastructure is presented. The regulatory strategy on evaluation of HFE consideration should provide reviewers with guidance on review process. Therefore, the suggested methodology is based on preparation of guidance documents such as checklist, working procedures, S and Gs etc.; incorporation of PRM elements in regulatory system; and finally the development of PRM implementation criteria. Altogether, the scheme provide the enhancement in regulatory infrastructure and also the effective and efficient review process. The Three Mile Island (TMI) accident brought the general consensus among the nuclear community on the integration of human factors engineering (HFE) principles in all phases of nuclear power. This notion has further strengthened after the recent Fukushima nuclear accident. Much effort has been put over to incorporate the lesson learned and continuous technical evolution on HFE to device different standards. The total of 174 ergonomics standards are alone identified by Dul et al. (2004) published by International Organization for Standardization (ISO) and the European Committee for Standardization (CEN) and number of standards and HFE guidelines (S and Gs) are also published by organizations like Institute for Electrical and Electronics Engineering (IEEE), International Electrotechnical Commission (IEC), International Atomic Energy Agency (IAEA), United States Nuclear Regulatory Commission (USNRC), etc. The ambition of effective review on HFE integration in nuclear facility might be accomplished through the development of methodology for systematic implementation of S and Gs. Such kind of methodology would also be beneficial for strengthening the regulatory framework and practices for countries new in the nuclear arena and with small scale nuclear program. The objective of paper is to review the

78 FR 4477 - Review of Safety Analysis Reports for Nuclear Power Plants, Introduction

Science.gov (United States)

2013-01-22

... Analysis Reports for Nuclear Power Plants: LWR Edition.'' The new subsection is the Standard Review Plan... Nuclear Power Plants: Integral Pressurized Water Reactor (iPWR) Edition.'' DATES: Comments must be filed... NUCLEAR REGULATORY COMMISSION [NRC-2012-0268] Review of Safety Analysis Reports for Nuclear Power...

IAEA Completes Nuclear Security Review Mission in United States

International Nuclear Information System (INIS)

2013-01-01

Full text: A team of nuclear security experts led by the International Atomic Energy Agency (IAEA) today completed a mission to review nuclear security practices of civil nuclear facilities licensed by the United States Nuclear Regulatory Commission (NRC). Conducted at the U.S. Government's request, the two-week International Physical Protection Advisory Service (IPPAS) mission reviewed the United States' nuclear security-related legislative and regulatory framework. As part of this work, the IPPAS team, led by John O'Dacre of Canada and comprising nine experts from eight IAEA Member States, met with NRC officials and reviewed the physical protection systems at the Center for Neutron Research (NCNR) at the National Institute of Standards and Technology. The IPPAS team concluded that nuclear security within the U.S. civil nuclear sector is robust and sustainable and has been significantly enhanced in recent years. The team identified a number of good practices in the nation's nuclear security regime and at the NCNR. The IPPAS team also made a recommendation and some suggestions for the continuing improvement of nuclear security overall. The mission in the United States was the 60th IPPAS mission organized by the IAEA. 'Independent international peer reviews such as IAEA IPPAS missions are increasingly being recognized for their value as a key component for exchanges of views and advice on nuclear security measures', said Khammar Mrabit, Director of the IAEA Office of Nuclear Security. 'The good practices identified during this mission will contribute to the continuous improvements of nuclear security in other Member States'. The IPPAS team provided a draft report to the NRC and will submit a final report soon. Because it contains security-related information about a specific nuclear site, IPPAS reports are not made public. 'The IPPAS programme gives us a chance to learn from the experience and perspective of our international partners', said NRC Chairman Allison M

Review of IAEA documentation on Nuclear and radiological emergency

International Nuclear Information System (INIS)

Mukhono, P. M.

2014-10-01

The project focuses on the review of IAEA documentation on nuclear or radiological emergencies with main focus on methodology for developing and arrangement for nuclear and radiological emergencies. The main objective of this work is to identify limitations in IAEA documentation on emergency preparedness and response (EPR) and provide recommendation on the main actions needed to fill the gaps identified thus aiding in improvement of emergency preparedness and response to nuclear and radiological accidents. The review of IAEA documentation on nuclear and radiological emergency has been carried out by evaluating various emergency response elements. Several elements for EPR were highlighted covering the safety fundamentals, general safety requirements and EPR methods for development of an effective emergence response capability for nuclear or radiological emergencies. From these issues, the limitations of IAEA documentation on EPR were drawn and recommendations suggested as a means of improving EPR methods. Among them was the need for IAEA consider establishment of follow up and inspection programmes to facilitate implementation of EPR requirements in most developing countries, establishment of programmes that provide platforms for the countries to be motivated to update their system in line with the current status of emergency preparedness, review of the international information exchange aspects of nuclear emergencies in order to improve capabilities to communicate reliable data, information and decisions quickly and effectively among national authorities and their emergency and emergency response centres. (au)

Review of nuclear pharmacy practice in hospitals

International Nuclear Information System (INIS)

Kawada, T.K.; Tubis, M.; Ebenkamp, T.; Wolf, W.

1982-01-01

An operational profile for nuclear pharmacy practice is presented, and the technical and professional role of nuclear pharmacists is reviewed. Key aspects of nuclear pharmacy practice in hospitals discussed are the basic facilities and equipment for the preparation, quality control, and distribution of radioactive drug products. Standards for receiving, storing, and processing radioactive material are described. The elements of a radiopharmaceutical quality assurance program, including the working procedures, documentation systems, data analysis, and specific control tests, are presented. Details of dose preparation and administration and systems of inventory control for radioactive products are outlined

Guidelines for Preparing and Conducting an Integrated Nuclear Infrastructure Review (INIR)

International Nuclear Information System (INIS)

2017-01-01

As of 1 July 2017, there were 447 operational nuclear power reactors in 30 countries and another 60 were under construction in 15 countries. Technically and financially, access to nuclear power is no longer limited to advanced economies. Many developing countries are interested in introducing or expanding nuclear energy programmes because they regard nuclear power as a stable and reliable source of baseload electricity, which, in addition, makes a significant contribution to climate change mitigation. While several operating countries are planning to expand current capacity, about 30 Member States, mostly developing countries, are considering embarking on a nuclear power programme, some are developing the necessary infrastructure, and some others are negotiating or building their first nuclear power plant. Building a nuclear power programme is a major undertaking with significant international implications and is based upon a commitment to use nuclear power for peaceful purposes, in a safe, secure and sustainable manner. This commitment requires establishing a sustainable national infrastructure that provides governmental, legal, regulatory, managerial, technological, human resource, industrial and stakeholder support for the nuclear power programme throughout its life cycle. The demonstration of compliance with international legal instruments, internationally accepted nuclear safety standards, nuclear security guidelines and safeguards requirements is essential in establishing a responsible nuclear power programme. In response to growing demand by embarking countries for advice and assistance, the IAEA has developed an approach to assist Member States that are considering or planning their first nuclear power plant to understand the commitments and obligations associated with developing a nuclear power programme. States that already have nuclear power can also assess their preparedness for expansion. This approach is set out in the publication Milestones in the

Review: Franz Breuer with Assistance of Barbara Dieris and Antje Lettau (2009. Reflexive Grounded Theory. Eine Einführung für die Forschungspraxis [Reflexive Grounded Theory: An Introduction to Research Praxis

Directory of Open Access Journals (Sweden)

Sandra Da Rin

2010-03-01

Full Text Available This textbook by Franz BREUER, produced with the assistance of Barbara DIERIS and Antje LETTAU, is of interest more for the introduction it provides to reflexive research praxis than to grounded theory methodology. This means the subjectivity of the researcher is included in the research process as a decisive source of cognition. Reflexive grounded theory methodology is characterized by three elements that also structure the textbook. In the present review, I focus on two of these in detail: the approach to the research field based on ethnography, particular its epistemological prerequisites, and the inclusion of (self- reflexivity. The latter points to questions that are addressed at the end of this review. URN: urn:nbn:de:0114-fqs1002140

Nuclear Explosion Monitoring History and Research and Development

Science.gov (United States)

Hawkins, W. L.; Zucca, J. J.

2008-12-01

Within a year after the nuclear detonations over Hiroshima and Nagasaki the Baruch Plan was presented to the newly formed United Nations Atomic Energy Commission (June 14, 1946) to establish nuclear disarmament and international control over all nuclear activities. These controls would allow only the peaceful use of atomic energy. The plan was rejected through a Security Council veto primarily because of the resistance to unlimited inspections. Since that time there have been many multilateral, and bilateral agreements, and unilateral declarations to limit or eliminate nuclear detonations. Almost all of theses agreements (i.e. treaties) call for some type of monitoring. We will review a timeline showing the history of nuclear testing and the more important treaties. We will also describe testing operations, containment, phenomenology, and observations. The Comprehensive Nuclear Test Ban Treaty (CTBT) which has been signed by 179 countries (ratified by 144) established the International Monitoring System global verification regime which employs seismic, infrasound, hydroacoustic and radionuclide monitoring techniques. The CTBT also includes on-site inspection to clarify whether a nuclear explosion has been carried out in violation of the Treaty. The US Department of Energy (DOE) through its National Nuclear Security Agency's Ground-Based Nuclear Explosion Monitoring R&D Program supports research by US National Laboratories, and universities and industry internationally to detect, locate, and identify nuclear detonations. This research program builds on the broad base of monitoring expertise developed over several decades. Annually the DOE and the US Department of Defense jointly solicit monitoring research proposals. Areas of research include: seismic regional characterization and wave propagation, seismic event detection and location, seismic identification and source characterization, hydroacoustic monitoring, radionuclide monitoring, infrasound monitoring, and

Performance Based Failure Criteria of the Base Isolation System for Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Jung Han; Kim, Min Kyu; Choi, In Kil

2013-01-01

The realistic approach to evaluate the failure state of the base isolation system is necessary. From this point of view, several concerns are reviewed and discussed in this study. This is the preliminary study for the performance based risk assessment of a base isolated nuclear power plant. The items to evaluate the capacity and response of an individual base isolator and a base isolation system were briefly outlined. However, the methodology to evaluate the realistic fragility of a base isolation system still needs to be specified. For the quantification of the seismic risk for a nuclear power plant structure, the failure probabilities of the structural component for the various seismic intensity levels need to be calculated. The failure probability is evaluated as the probability when the seismic response of a structure exceeds the failure criteria. Accordingly, the failure mode of the structural system caused by an earthquake vibration should be defined first. The type of a base isolator appropriate for a nuclear power plant structure is regarded as an elastometric rubber bearing with a lead core. The failure limit of the lead-rubber bearing (LRB) is not easy to be predicted because of its high nonlinearity and a complex loading condition by an earthquake excitation. Furthermore, the failure mode of the LRB system installed below the nuclear island cannot be simply determined because the basemat can be sufficiently supported if the number of damaged isolator is not much

Regional analysis of ground and above-ground climate

Science.gov (United States)

1981-12-01

The regional suitability of underground construction as a climate control technique is discussed with reference to (1) a bioclimatic analysis of long term weather data for 29 locations in the United States to determine appropriate above ground climate control techniques, (2) a data base of synthesized ground temperatures for the coterminous United States, and (3) monthly dew point ground temperature comparisons for identifying the relative likelihood of condensation from one region to another. It is concluded that the suitability of Earth tempering as a practice and of specific Earth sheltered design stereotypes varies geographically; while the subsurface almost always provides a thermal advantage on its own terms when compared to above ground climatic data, it can, nonetheless, compromise the effectiveness of other, regionally more important climate control techniques. Reviews of above and below ground climate mapping schemes related to human comfort and architectural design, and detailed description of a theoretical model of ground temperature, heat flow, and heat storage in the ground are included. Strategies of passive climate control are presented in a discussion of the building bioclimatic analysis procedure which has been applied in a computer analysis of 30 years of weather data for each of 20 locations in the United States.

Regional analysis of ground and above-ground climate

Energy Technology Data Exchange (ETDEWEB)

1981-12-01

The regional suitability of underground construction as a climate control technique is discussed with reference to (1) a bioclimatic analysis of long-term weather data for 29 locations in the United States to determine appropriate above ground climate control techniques, (2) a data base of synthesized ground temperatures for the coterminous United States, and (3) monthly dew point ground temperature comparisons for identifying the relative likelihood of condensation from one region to another. It is concluded that the suitability of earth tempering as a practice and of specific earth-sheltered design stereotypes varies geographically; while the subsurface almost always provides a thermal advantage on its own terms when compared to above ground climatic data, it can, nonetheless, compromise the effectiveness of other, regionally more important climate control techniques. Also contained in the report are reviews of above and below ground climate mapping schemes related to human comfort and architectural design, and detailed description of a theoretical model of ground temperature, heat flow, and heat storage in the ground. Strategies of passive climate control are presented in a discussion of the building bioclimatic analysis procedure which has been applied in a computer analysis of 30 years of weather data for each of 29 locations in the United States.

Risk-based inspection in the context of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G., E-mail: soaresw@cdtn.br, E-mail: vasconv@cdtn.br, E-mail: egr@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2015-07-01

Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

Risk-based inspection in the context of nuclear power plants

International Nuclear Information System (INIS)

Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G.

2015-01-01

Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

Electron momentum spectroscopy of aniline taking account of nuclear dynamics in the initial electronic ground state

International Nuclear Information System (INIS)

Farasat, M; Golzan, M M; Shojaei, S H R; Morini, F; Deleuze, M S

2016-01-01

The electronic structure, electron binding energy spectrum and (e, 2e) momentum distributions of aniline have been theoretically predicted at an electron impact energy of 1.500 keV on the basis of Born–Oppenheimer molecular dynamical simulations, in order to account for thermally induced nuclear motions in the initial electronic ground state. Most computed momentum profiles are rather insensitive to thermally induced alterations of the molecular structure, with the exception of the profiles corresponding to two ionization bands at electron binding energies comprised between ∼10.0 and ∼12.0 eV (band C) and between ∼16.5 and ∼20.0 eV (band G). These profiles are found to be strongly influenced by nuclear dynamics in the electronic ground state, especially in the low momentum region. The obtained results show that thermal averaging smears out most generally the spectral fingerprints that are induced by nitrogen inversion. (paper)

Experience with nonuniform damping in the seismic analysis of nuclear plant components

International Nuclear Information System (INIS)

Winkel, B.V.; Julyk, L.J.

1983-01-01

Individual components of nuclear power plants may exhibit pronounced differences in damping magnitude. Various methods for accounting for nonuniform damping in a structural model are reviewed and evaluated. The methods are compared by solving a beam/pipe model subjected to a typical seismic ground motion. A two-degree-of-freedom variable damping parameter study is also presented. Based upon the experience of evaluating and applying the available methods, application guidelines are presented

Nuclear properties for astrophysical applications

Energy Technology Data Exchange (ETDEWEB)

Moeller, P.; Nix, J.R. [Los Alamos National Lab., NM (United States); Kratz, K.L. [Mainz Univ. (Germany). Inst. fuer Kernchemie

1994-09-23

We tabulate the ground-state odd-proton and odd-neutron spins, proton and neutron pairing gaps, binding energies, neuton separation energies, quantities related to {beta}-delayed one, two and three neutron emission probabilities, {beta}-decay Q values and half-lives with respect to Gamow-Teller decay, proton separation energies, and {alpha}-decay Q values and half-lives. The starting point of the calculations is a calculation of nuclear ground-states and (information based on the finite-range droplet model and the folded-Yukawa single-particle model published in a previous issue of ATOMIC DATA AND NUCLEAR DATA TABLES. The {beta}-delayed neutron-emission probabilities and Gamow-Teller {beta}-decay rates are obtained from a QRPA model that uses single-particle levels and wave-functions at the calculated nuclear ground-state shape as the starting point.

Hydrogeology, simulated ground-water flow, and ground-water quality, Wright-Patterson Air Force Base, Ohio

Science.gov (United States)

Dumouchelle, D.H.; Schalk, C.W.; Rowe, G.L.; De Roche, J.T.

1993-01-01

Ground water is the primary source of water in the Wright-Patterson Air Force Base area. The aquifer consists of glacial sands and gravels that fill a buried bedrock-valley system. Consolidated rocks in the area consist of poorly permeable Ordovician shale of the Richmondian stage, in the upland areas, the Brassfield Limestone of Silurian age. The valleys are filled with glacial sediments of Wisconsinan age consisting of clay-rich tills and coarse-grained outwash deposits. Estimates of hydraulic conductivity of the shales based on results of displacement/recovery tests range from 0.0016 to 12 feet per day; estimates for the glacial sediments range from less than 1 foot per day to more than 1,000 feet per day. Ground water flow from the uplands towards the valleys and the major rivers in the region, the Great Miami and the Mad Rivers. Hydraulic-head data indicate that ground water flows between the bedrock and unconsolidated deposits. Data from a gain/loss study of the Mad River System and hydrographs from nearby wells reveal that the reach of the river next to Wright-Patterson Air Force Base is a ground-water discharge area. A steady-state, three-dimensional ground-water-flow model was developed to simulate ground-water flow in the region. The model contains three layers and encompasses about 100 square miles centered on Wright-Patterson Air Force Base. Ground water enters the modeled area primarily by river leakage and underflow at the model boundary. Ground water exits the modeled area primarily by flow through the valleys at the model boundaries and through production wells. A model sensitivity analysis involving systematic changes in values of hydrologic parameters in the model indicates that the model is most sensitive to decreases in riverbed conductance and vertical conductance between the upper two layers. The analysis also indicates that the contribution of water to the buried-valley aquifer from the bedrock that forms the valley walls is about 2 to 4

Modal-pushover-based ground-motion scaling procedure

Science.gov (United States)

Kalkan, Erol; Chopra, Anil K.

2011-01-01

Earthquake engineering is increasingly using nonlinear response history analysis (RHA) to demonstrate the performance of structures. This rigorous method of analysis requires selection and scaling of ground motions appropriate to design hazard levels. This paper presents a modal-pushover-based scaling (MPS) procedure to scale ground motions for use in a nonlinear RHA of buildings. In the MPS method, the ground motions are scaled to match to a specified tolerance, a target value of the inelastic deformation of the first-mode inelastic single-degree-of-freedom (SDF) system whose properties are determined by the first-mode pushover analysis. Appropriate for first-mode dominated structures, this approach is extended for structures with significant contributions of higher modes by considering elastic deformation of second-mode SDF systems in selecting a subset of the scaled ground motions. Based on results presented for three actual buildings-4, 6, and 13-story-the accuracy and efficiency of the MPS procedure are established and its superiority over the ASCE/SEI 7-05 scaling procedure is demonstrated.

Factors relevant to the decommissioning of land-based nuclear reactor plants

International Nuclear Information System (INIS)

1980-01-01

This document applies to all classes of land-based nuclear fission reactors, including those reactors used for the production of electricity or heat, for testing, for research, and for the production of radionuclides. The document covers the technical and administrative aspects related to the conduct of decommissioning, and to the associated radiation protection of man and his environment both during and after decommissioning. The document is intended to provide assistance to those responsible for planning or implementing the decommissioning of a land-based nuclear reactor. The user of this report is further encouraged to review past experience gained with nuclear facilities and the published technical data cited in the section entitled Bibliography

Periodic Safety Review of Nuclear Power Plants: Experience of Member States

International Nuclear Information System (INIS)

2010-04-01

Routine reviews of nuclear power plant operation (including modifications to hardware and procedures, operating experience, plant management and personnel competence) and special reviews following major events of safety significance are the primary means of safety verification. In addition, many Member States of the IAEA have initiated systematic safety reassessments, termed periodic safety reviews, of nuclear power plants, to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments and siting aspects. The reviews include an assessment of plant design and operation against current safety standards and practices, and they have the objective of ensuring a high level of safety throughout the plant's operating lifetime. They are complementary to the routine and special safety reviews and do not replace them. Periodic safety reviews of nuclear power plants are considered an effective way to obtain an overall view of actual plant safety, and to determine reasonable and practical modifications that should be made in order to maintain a high level of safety. They can be used as a means of identifying time limiting features of the plant in order to determine nuclear power plant operation beyond the designed lifetime. The periodic safety review process can be used to support the decision making process for long term operation or licence renewal. Since 1994, the use of periodic safety reviews by Member States has substantially broadened and confirmed its benefits. Periodic safety review results have, for example, been used by some Member States to help provide a basis for continued operation beyond the current licence term, to communicate more effectively with stakeholders regarding nuclear power plant safety, and to help identify changes to plant operation that enhance safety. This IAEA-TECDOC is intended to assist Member States in the implementation of a periodic safety review. This publication complements the

IAEA Concludes Safety Review at Chooz Nuclear Power Plant in France

International Nuclear Information System (INIS)

2013-01-01

Full text: An IAEA-led international team of nuclear safety experts noted good practices and made recommendations to reinforce safety measures during a review of operational safety at France's Chooz Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 17 June, focused on aspects essential to the safe operation of the NPP. The team comprised experts from Switzerland, Belgium, Germany, China, India, United Kingdom, Czech Republic, Canada, Hungary and the IAEA. The review covered the areas of management, organization and administration; training and qualification of personnel; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team identified good plant practices that will be shared with the rest of the nuclear industry for consideration. Examples include: The plant has a professional development programme as part of a joint employment effort shared by the plant and its contractors. This enables trainees to develop professional capability, understand practices and gain experience from other nuclear power plants in terms of work planning and coordination; The plant has built a strong relationship between the on-shift response team of the plant and the local fire brigade to improve firefighting and rescue operations; Self-assessment groups discuss and resolve specific issues within operations, empowering operations personnel to take ownership of improvement programmes; and The plant has improved warnings at entrances to all o range zones , areas of elevated dose rates to which only authorized staff have access. The team identified a number of improvements to operational safety at Chooz NPP. Examples include: The plant should review its process for the

Review of nuclear power costs around the world

International Nuclear Information System (INIS)

Bennett, L.L.; Karousakis, P.M.; Moynet, G.

1983-01-01

This paper presents highlights of nuclear power costs around the world from studies carried out by the IAEA and by UNIPEDE. Emphasis is placed on trends within each country of key parameters which affect both investment costs and total power generation costs, including construction and project durations, size of units, regulatory environment, scope of project, fuel cycle costs and general economic conditions. A synthesis of these trends, taking into consideration both nuclear and coal-fired plant capital and fuel costs as they are estimated to evolve in the near and medium term, is presented in terms of nuclear-to-coal cost ratios for both plant investment costs and total generating costs. The plant investment costs are expressed as ''overnight'' or ''fore'' costs, in constant money, for plants expected to enter commercial operation in the early 1990s. Pertinent assumptions are based on conditions prevailing in the particular country under review. These studies indicate that in most countries nuclear plant investment costs are rising more rapidly than the costs for coal-fired plants. A major cause for the rapid rise in nuclear plant costs is the drastic lengthening of project duration in most countries. France, as a notable exception, has been able to maintain a stable and reasonably short project time. In spite of the rapidly escalating nuclear plant investment costs, nuclear electricity generation has an economic advantage over coal in Europe and Canada and is competitive with coal in the eastern and midwestern parts of the United States of America (USA). The availability of abundant, low-cost coal gives coal-fired generation an economic advantage in the western USA. (author)

Assessment of erecting nuclear power plants below ground in an open building pit

International Nuclear Information System (INIS)

Kroeger, W.; Altes, J.; Bongartz, R.; David, P.H.; Escherich, K.H.; Kasper, K.; Koschmieder, D.; Roethig, K.D.; Schwarzer, K.; Wolters, J.

1978-01-01

The technical feasibility, costs and safety potential of siting a nuclear power plant below ground level have been assessed. The reference plant was a 1,300 MWsub(e) PWR and the siting was based on a 'cut-and-cover' design in soil. The 'cut-and-cover' design enhances the safety potential of the site both with regard to extreme internal accidents and to external impacts inclusive of hostile attack. The measures required to 'harden' the site against these extreme conditions do not cancel each other. The realization of the safety potential is strongly dependent on the reliability of the closure equipment on routes to the atmosphere. These closures represent the remaining vulnerable feature of the design, as all other release paths are through soil which prevents any immediate danger to the public. The concepts considered include partial or complete lowering of the reactor. The thickness of the coverage depends on the degree of protection required and is typically between 8 and 13 m. The essential systems of the above-ground design are unchanged and therefore prior experience and existing designs can be applied. The concepts appear to be technically feasible including, in particular, the large pits and the additional closures; the technical difficulties, however, should not be underestimated. The depth of lowering does not determine the gain in safety because a well designed coverage can act as natural soil. Partial lowering, in fact, appears to be the more economic method. According to the degree of protection and the variations of design, the concepts would cost between 8 and 14% more than the capital cost of an equivalent above-ground plant. The construction time would be extended by 1.4 years for the concepts investigated. (orig./HP) [de

Solid-state nuclear-spin quantum computer based on magnetic resonance force microscopy

International Nuclear Information System (INIS)

Berman, G. P.; Doolen, G. D.; Hammel, P. C.; Tsifrinovich, V. I.

2000-01-01

We propose a nuclear-spin quantum computer based on magnetic resonance force microscopy (MRFM). It is shown that an MRFM single-electron spin measurement provides three essential requirements for quantum computation in solids: (a) preparation of the ground state, (b) one- and two-qubit quantum logic gates, and (c) a measurement of the final state. The proposed quantum computer can operate at temperatures up to 1 K. (c) 2000 The American Physical Society

Scaling earthquake ground motions for performance-based assessment of buildings

Science.gov (United States)

Huang, Y.-N.; Whittaker, A.S.; Luco, N.; Hamburger, R.O.

2011-01-01

The impact of alternate ground-motion scaling procedures on the distribution of displacement responses in simplified structural systems is investigated. Recommendations are provided for selecting and scaling ground motions for performance-based assessment of buildings. Four scaling methods are studied, namely, (1)geometric-mean scaling of pairs of ground motions, (2)spectrum matching of ground motions, (3)first-mode-period scaling to a target spectral acceleration, and (4)scaling of ground motions per the distribution of spectral demands. Data were developed by nonlinear response-history analysis of a large family of nonlinear single degree-of-freedom (SDOF) oscillators that could represent fixed-base and base-isolated structures. The advantages and disadvantages of each scaling method are discussed. The relationship between spectral shape and a ground-motion randomness parameter, is presented. A scaling procedure that explicitly considers spectral shape is proposed. ?? 2011 American Society of Civil Engineers.

Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

Energy Technology Data Exchange (ETDEWEB)

Duran, Felicia Angelica [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.; Waymire, Russell L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.

2013-10-01

Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

International Nuclear Information System (INIS)

Duran, Felicia Angelica; Waymire, Russell L.

2013-01-01

Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

Hanford Ground-Water Data Base management guide

International Nuclear Information System (INIS)

Rieger, J.T.; Mitchell, P.J.; Muffett, D.M.; Fruland, R.M.; Moore, S.B.; Marshall, S.M.

1990-02-01

This guide describes the Hanford Ground-Water Data Base (HGWDB), a computerized data base used to store hydraulic head, sample analytical, temperature, geologic, and well-structure information for ground-water monitoring wells on the Hanford Site. These data are stored for the purpose of data retrieval for report generation and also for historical purposes. This guide is intended as an aid to the data base manager and the various staff authorized to enter and verify data, maintain the data base, and maintain the supporting software. This guide focuses on the structure of the HGWDB, providing a fairly detailed description of the programs, files, and parameters. Data-retrieval instructions for the general user of the HGWDB will be found in the HGWDB User's Manual. 6 figs

Space and Ground-Based Infrastructures

Science.gov (United States)

Weems, Jon; Zell, Martin

This chapter deals first with the main characteristics of the space environment, outside and inside a spacecraft. Then the space and space-related (ground-based) infrastructures are described. The most important infrastructure is the International Space Station, which holds many European facilities (for instance the European Columbus Laboratory). Some of them, such as the Columbus External Payload Facility, are located outside the ISS to benefit from external space conditions. There is only one other example of orbital platforms, the Russian Foton/Bion Recoverable Orbital Capsule. In contrast, non-orbital weightless research platforms, although limited in experimental time, are more numerous: sounding rockets, parabolic flight aircraft, drop towers and high-altitude balloons. In addition to these facilities, there are a number of ground-based facilities and space simulators, for both life sciences (for instance: bed rest, clinostats) and physical sciences (for instance: magnetic compensation of gravity). Hypergravity can also be provided by human and non-human centrifuges.

Confirmation test on the dynamic interaction between a model reactor-building foundation and ground in the Sendai Nuclear Power Station

International Nuclear Information System (INIS)

Umezu, Hideo; Kisaki, Noboru; Shiota, Mutsumi

1982-01-01

On the site of unit 2 (planned) in the Sendai Nuclear Power Station, a model reactor-building foundation of reinforced concrete with diameter of 12 m and height of 5 m was installed. With a vibration generator, its forced vibration tests were carried out in October to December, 1980. Valuable data were able to be obtained on the dynamic interaction between the model foundation and the ground, and also the outlook for the application of theories in hard base rock was obtained. (1) The resonance frequency of the model foundation in horizontal vibration was 35 Hz in both NS and EW directions. (2) Remarkable difference was not observed in the horizontal vibration behavior between NS and EW directions, so that there is not anisotropy in the ground. (3) The model foundation was deformed nearly as a rigid body. (J.P.N.)

Nuclear Energy Infrastructure Database Fitness and Suitability Review

Energy Technology Data Exchange (ETDEWEB)

Heidrich, Brenden [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-03-01

In 2014, the Deputy Assistant Secretary for Science and Technology Innovation (NE-4) initiated the Nuclear Energy-Infrastructure Management Project by tasking the Nuclear Science User Facilities (NSUF) to create a searchable and interactive database of all pertinent NE supported or related infrastructure. This database will be used for analyses to establish needs, redundancies, efficiencies, distributions, etc. in order to best understand the utility of NE’s infrastructure and inform the content of the infrastructure calls. The NSUF developed the database by utilizing data and policy direction from a wide variety of reports from the Department of Energy, the National Research Council, the International Atomic Energy Agency and various other federal and civilian resources. The NEID contains data on 802 R&D instruments housed in 377 facilities at 84 institutions in the US and abroad. A Database Review Panel (DRP) was formed to review and provide advice on the development, implementation and utilization of the NEID. The panel is comprised of five members with expertise in nuclear energy-associated research. It was intended that they represent the major constituencies associated with nuclear energy research: academia, industry, research reactor, national laboratory, and Department of Energy program management. The Nuclear Energy Infrastructure Database Review Panel concludes that the NSUF has succeeded in creating a capability and infrastructure database that identifies and documents the major nuclear energy research and development capabilities across the DOE complex. The effort to maintain and expand the database will be ongoing. Detailed information on many facilities must be gathered from associated institutions added to complete the database. The data must be validated and kept current to capture facility and instrumentation status as well as to cover new acquisitions and retirements.

Seismic design of nuclear power plants - an assessment

International Nuclear Information System (INIS)

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

1976-01-01

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

Ground disposal of oil shale wastes: a review with an indexed annotated bibliography through 1976

Energy Technology Data Exchange (ETDEWEB)

Routson, R.C.; Bean, R.M.

1977-12-01

This review covers the available literature concerning ground-disposed wastes and effluents of a potential oil shale industry. Ground disposal has been proposed for essentially all of the solid and liquid wastes produced (Pfeffer, 1974). Since an oil shale industry is not actually in operation, the review is anticipatory in nature. The section, Oil Shale Technology, provides essential background for interpreting the literature on potential shale oil wastes and the topics are treated more completely in the section entitled Environmental Aspects of the Potential Disposal of Oil Shale Wastes to Ground. The first section of the annotated bibliography cites literature concerning potential oil shale wastes and the second section cites literature concerning oil shale technology. Each section contains references arranged historically by year. An index is provided.

Nuclear safety review for the year 2001

International Nuclear Information System (INIS)

2002-07-01

The Nuclear Safety Review for the Year 2001 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts. Part 1 describes those events in 2001 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety. Part 2 describes some of the IAEA's efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2001. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2001. Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2001 was presented to the March 2002 session of IAEA's Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2002 that were considered pertinent to the discussion of events during 2001

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.

International nuclear safety experts complete IAEA peer review of German regulatory system

International Nuclear Information System (INIS)

2008-01-01

Full text: An international expert team has today completed a two-week IAEA review of Germany's nuclear regulatory system. The team identified good practices within the system and gave advice on some areas for further improvement. The IAEA has conveyed the initial findings to German authorities but the final report will be submitted within two months. At the request of the Government of the Federal Republic of Germany, the International Atomic Energy Agency (IAEA) assembled a team of 14 experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This is a peer review based on IAEA Standards. It is not an inspection, nor an audit. The scope of the mission was limited to the safety regulation of nuclear power plants. Experts from Canada, the Czech Republic, Finland, France, Japan, the Netherlands, Republic of Korea, Spain, Switzerland, the UK, the US and from the IAEA took part in the mission, which was conducted from 7 to 19 September in Bonn, Stuttgart and Berlin. The main basis for the review was a well-prepared self-assessment made by the Federal Ministry of Environment, Nature Conservation and Nuclear Safety (BMU) and the Ministry of Environment of the federal state of Baden-Wuerttemberg (UM BW). 'The team members were impressed by the extensive preparation and dedication of the staff both at BMU and UM BW to excellence in nuclear safety,' said Mike Weightman, IRRS Team Leader and Chief Inspector of the UK nuclear regulatory body, the Nuclear Directorate of the Health and Safety Executive. 'We hope the IRRS mission will facilitate further improvements in the safety regulation of nuclear power in Germany and throughout the world.' 'Germany's invitation to undergo such a detailed review is a clear demonstration of its openness and commitment to continuously improve nuclear safety regulation,' said Philippe Jamet, Director of the IAEA's Nuclear Installation Safety Division. Among the particular strengths of BMU and UM BW associated with their

Review of radioactive discharges from nuclear power stations

International Nuclear Information System (INIS)

1991-02-01

HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report is a review of the arisings and concludes that suitable technologies exist, which if applied, could reduce discharges from nuclear power plants in England and Wales in line with the rest of Europe. (author)

2007 Nuclear Data Review

International Nuclear Information System (INIS)

Holden, N.E.

2008-01-01

The results of a review and evaluation of neutron and non-neutron nuclear data published in the scientific literature are presented. The status of new chemical elements is examined. Data on revised values for the isotopic composition of the elements are reviewed and recommended values are presented. Half-lives of very long-lived nuclides are presented, including double beta decay, double electron capture, long-lived alpha decay and long-lived beta decay. Data from new measurements on the very heavy elements (trans-meitnerium elements) are discussed and tabulated. The first observation of the radioactive decay mode of the free neutron is discussed. New measurements that have expanded the neutron drip line for magnesium and aluminum are discussed. Data on recent neutron cross-section and resonance integral measurements are also discussed

IAEA Mission Concludes Peer Review of Slovenia's Nuclear Regulatory Framework

International Nuclear Information System (INIS)

2014-01-01

Senior international nuclear safety and radiation protection experts today concluded an eight-day International Atomic Energy Agency (IAEA) mission to review the regulatory framework for nuclear and radiation safety at the Slovenian Nuclear Safety Administration (SNSA). The team reviewed measures taken to address the recommendations and suggestions made during an earlier Integrated Regulatory Review Service (IRRS) mission conducted in 2011. The IRRS team said in its preliminary findings that Slovenia had made significant progress since the review in 2011. The team identified a good practice in the country's nuclear regulatory system additional to those identified in 2011 and made new recommendations and suggestions to SNSA and the Government to strengthen the effectiveness of the country's regulatory framework in line with IAEA Safety Standards. ''By hosting a follow-up mission, Slovenia demonstrated its commitment to enhance its regulatory programmes, including by implementing the recommendations of the 2011 mission,'' said Petr Krs, mission leader and Vice Chairman of the Czech Republic's State Office for Nuclear Safety. SNSA's Director, Andrej Stritar, welcomed the progress noted by the team, while also emphasizing that the mission highlighted important future nuclear safety challenges for Slovenia. The five-member review team, comprising experts from Belgium, the Czech Republic, France and Romania, as well as four IAEA staff members, conducted the mission at the request of the Slovenian Government from 9 to 16 September 2014. The main observations of the IRRS Review team included the following: SNSA has made significant progress in addressing the findings of the 2011 IRRS mission and has demonstrated commitment to effective implementation of the IRRS programme; The economic situation in Slovenia might in the short and long term affect SNSA's ability to maintain its capacity and competence; and A radioactive waste disposal project is stalled and the licensing

Review on Overseas Contracts of a Nuclear Research Institute in Korea

Energy Technology Data Exchange (ETDEWEB)

Lee, Myung Ho; Lee, Eui Jin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2010-10-15

Since its establishment, Korea Atomic Energy Research Institute (KAERI) has made various contracts in research, design, engineering and consultation with a lot of foreign counterparts all over the world, including international organizations. As one of the global nuclear energy research leaders, KAERI can make a large scale contract because it has already procured a turnkey EPC (Engineering, Procurement, Construction) contract for a research and training reactor in the spring of 2010 by forming a consortium with a construction and engineering company. A contract in nuclear business industries is to be made under the limited control of regulatory authorities because the contractors must ensure nuclear safety and follow the international nuclear non-proliferation guidelines to secure the peaceful use of nuclear energy at an international level. The export and import of strategic technologies, products or materials (including nuclear materials) must be directly controlled by the authorities in accordance with the applicable law. In 2009, KAERI organized a new team to manage the overseas contracts and to make the limited control reflected in the contract documentation. In large scale project contracts, more attention shall be given to the contracts to prevent claims and also to the consideration of the regulatory requirements. In this context, the nature of the past KAERI contracts was reviewed. The conditions of several recent KAERI contracts were also individually reviewed based on the FIDIC (Federation Internationale des Ingenieurs-Conseils) model service agreement, which is generally accepted by service contractors. Ways to increase the quality of future contracts and to improve the standard model agreement which is used to prepare the draft contract were also considered

Review on Overseas Contracts of a Nuclear Research Institute in Korea

International Nuclear Information System (INIS)

Lee, Myung Ho; Lee, Eui Jin

2010-01-01

Since its establishment, Korea Atomic Energy Research Institute (KAERI) has made various contracts in research, design, engineering and consultation with a lot of foreign counterparts all over the world, including international organizations. As one of the global nuclear energy research leaders, KAERI can make a large scale contract because it has already procured a turnkey EPC (Engineering, Procurement, Construction) contract for a research and training reactor in the spring of 2010 by forming a consortium with a construction and engineering company. A contract in nuclear business industries is to be made under the limited control of regulatory authorities because the contractors must ensure nuclear safety and follow the international nuclear non-proliferation guidelines to secure the peaceful use of nuclear energy at an international level. The export and import of strategic technologies, products or materials (including nuclear materials) must be directly controlled by the authorities in accordance with the applicable law. In 2009, KAERI organized a new team to manage the overseas contracts and to make the limited control reflected in the contract documentation. In large scale project contracts, more attention shall be given to the contracts to prevent claims and also to the consideration of the regulatory requirements. In this context, the nature of the past KAERI contracts was reviewed. The conditions of several recent KAERI contracts were also individually reviewed based on the FIDIC (Federation Internationale des Ingenieurs-Conseils) model service agreement, which is generally accepted by service contractors. Ways to increase the quality of future contracts and to improve the standard model agreement which is used to prepare the draft contract were also considered

International Nuclear Safety Experts Conclude IAEA Peer Review of Korea's Regulatory System

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of senior nuclear safety experts concluded today a two-week mission to review the regulatory framework for nuclear safety in the Republic of Korea. The team identified good practices and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of Korea, while the final report will be submitted by the end of summer 2011. At the request of the Korean Government, the IAEA assembled a team of 16 senior regulatory experts from 14 nations to conduct the Integrated Regulatory Review Service (IRRS) mission involving the Korean Ministry for Education, Science and Technology (MEST) and the Korean Institute for Nuclear Safety (KINS). The mission is a peer-review based on the IAEA Safety Standards. ''This was the first IRRS mission organized after Japan's Fukushima Daiichi nuclear accident and it included a review of the regulatory implications of that event,' explains Denis Flory, IAEA Deputy Director General and Head of the Department of Nuclear Safety and Security. William Borchardt, Executive Director of Operations from the US Nuclear Regulatory Commission and Team Leader of this mission commended the Korean authorities for their openness and commitment to sharing their experience with the world's nuclear safety community. ''IRRS missions such as the one that was just concluded here in the Republic of Korea are crucial to the enhancement of nuclear safety worldwide,'' he said. The IRRS team reviewed Korea's current regulatory framework while acknowledging the fact that the country's Government has already decided to establish, as of October 2011, a new independent regulatory body to be called Nuclear Safety Commission (NSC). As a consequence, KINS role will be as a regulatory expert organization reporting to the NSC, while MEST's role will be restricted to promoting the utilization of nuclear energy. The IRRS team identified particular strengths in the Korean regulatory system

Simulated earthquake ground motions

International Nuclear Information System (INIS)

Vanmarcke, E.H.; Gasparini, D.A.

1977-01-01

The paper reviews current methods for generating synthetic earthquake ground motions. Emphasis is on the special requirements demanded of procedures to generate motions for use in nuclear power plant seismic response analysis. Specifically, very close agreement is usually sought between the response spectra of the simulated motions and prescribed, smooth design response spectra. The features and capabilities of the computer program SIMQKE, which has been widely used in power plant seismic work are described. Problems and pitfalls associated with the use of synthetic ground motions in seismic safety assessment are also pointed out. The limitations and paucity of recorded accelerograms together with the widespread use of time-history dynamic analysis for obtaining structural and secondary systems' response have motivated the development of earthquake simulation capabilities. A common model for synthesizing earthquakes is that of superposing sinusoidal components with random phase angles. The input parameters for such a model are, then, the amplitudes and phase angles of the contributing sinusoids as well as the characteristics of the variation of motion intensity with time, especially the duration of the motion. The amplitudes are determined from estimates of the Fourier spectrum or the spectral density function of the ground motion. These amplitudes may be assumed to be varying in time or constant for the duration of the earthquake. In the nuclear industry, the common procedure is to specify a set of smooth response spectra for use in aseismic design. This development and the need for time histories have generated much practical interest in synthesizing earthquakes whose response spectra 'match', or are compatible with a set of specified smooth response spectra

Selection of earthquake resistant design criteria for nuclear power plants: Methodology and technical cases: Dislocation models of near-source earthquake ground motion: A review

International Nuclear Information System (INIS)

Luco, J.E.

1987-05-01

The solutions available for a number of dynamic dislocation fault models are examined in an attempt at establishing some of the expected characteristics of earthquake ground motion in the near-source region. In particular, solutions for two-dimensional anti-plane shear and plane-strain models as well as for three-dimensional fault models in full space, uniform half-space and layered half-space media are reviewed

International Expert Team Concludes IAEA Peer Review of Slovakia's Regulatory Framework for Nuclear Safety

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of senior nuclear safety and radiation protection experts today concluded an 11-day mission to review the regulatory framework for nuclear safety in Slovakia. At the request of the Slovak Government, the IAEA assembled a team of 12 senior regulatory experts from 12 nations to conduct the Integrated Regulatory Review Service (IRRS) mission involving the Nuclear Regulatory Authority of the Slovak Republic (UJD SR). The international experts also met officials from the Public Health Authority of the Slovak Republic (UVZ SR) regarding the regulation of occupational radiation protection in nuclear facilities. The mission is a peer review based on the IAEA Safety Standards. Marta Ziakova, Chairperson of the Nuclear Regulatory Authority of Slovak Republic, declared that ''The IRRS mission has a great value for the future development and orientation of the UJD SR.'' ''Slovakia has established a regulatory framework for nuclear safety which is in line with international standards and practice,'' said Mission Team Leader Andrej Stritar, Director of the Slovenian Nuclear Safety Administration. The main observations of the IRRS Review team included: UJD SR operates with independence and transparency; UJD SR has developed and implemented a systematic training approach to meet its competence needs; and in response to the accident at TEPCO's Fukushima Daiichi Nuclear Power Station, UJD SR has reacted and communicated to interested parties, including the public. The good practices identified by the IRRS Review Team include: UJD SR has a comprehensive and well-formalized strategic approach to informing and consulting interested parties; UJD SR has developed and implemented a structured approach to training and developing its staff; and Detailed legal requirements provide a solid basis for on-site and off-site response in nuclear emergencies coordinated with local authorities. The IRRS Review team identified areas for further improvement and believes

Ground motion effects

Energy Technology Data Exchange (ETDEWEB)

Blume, J A [John A. Blume and Associates, San Francisco, CA (United States)

1969-07-01

Ground motion caused by natural earthquakes or by nuclear explosion causes buildings and other structures to respond in such manner as possibly to have high unit stresses and to be subject to damage or-in some cases-collapse. Even minor damage may constitute a hazard to persons within or adjacent to buildings. The risk of damage may well be the governing restraint on the uses of nuclear energy for peaceful purposes. Theory is advanced regarding structural-dynamic response but real buildings and structures are complex, highly variable, and often difficult to model realistically. This paper discusses the state of knowledge, the art of damage prediction and safety precautions, and shows ground motion effects from explosions of underground nuclear devices in the continental United States including events Salmon, Gasbuggy, Boxcar, Faultless and Benham. (author)

Ground motion effects

International Nuclear Information System (INIS)

Blume, J.A.

1969-01-01

Ground motion caused by natural earthquakes or by nuclear explosion causes buildings and other structures to respond in such manner as possibly to have high unit stresses and to be subject to damage or-in some cases-collapse. Even minor damage may constitute a hazard to persons within or adjacent to buildings. The risk of damage may well be the governing restraint on the uses of nuclear energy for peaceful purposes. Theory is advanced regarding structural-dynamic response but real buildings and structures are complex, highly variable, and often difficult to model realistically. This paper discusses the state of knowledge, the art of damage prediction and safety precautions, and shows ground motion effects from explosions of underground nuclear devices in the continental United States including events Salmon, Gasbuggy, Boxcar, Faultless and Benham. (author)

Nuclear safety and radiation protection report of the Tricastin operational hot base nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Safety experts complete second IAEA regulatory review of UK nuclear regulator

International Nuclear Information System (INIS)

2009-01-01

Full text: Nuclear safety experts today concluded a 10-day mission to peer-review the UK Nuclear Regulator: Health and Safety Executive (HSE), Nuclear Directorate (ND). At the request of the UK Government, the International Atomic Energy Agency assembled a team of ten high-level regulatory experts from eight nations to conduct the Integrated Regulatory Review Service (IRRS) mission. The mission was the second of three planned IRRS missions for the United Kingdom. The first was held in March 2006 to begin a process to assess the nation's readiness to regulate and license new reactor designs, considered as a result of the Energy Policy review initiated by the British Prime Minister and the Secretary of State for Trade and Industry (DTI) in 2005. The IRRS team leader Mr. William Borchardt, Executive Director of Operations from the US Nuclear Regulatory Commission, stated, ''The IAEA IRRS serves an important role in both benchmarking against its safety standards and in promoting dialogue between nuclear safety regulators from around the world.'' During the 2nd mission the IRRS the team reviewed HSE/ND progress since the first IRRS mission and recent regulatory developments, the regulation of operating power plants and fuel cycle facilities, the inspection and enforcement programme for nuclear power plants and fuel cycle facilities, and the emergency preparedness and response programme. The IAEA found that HSE/ND has made significant progress toward improving its effectiveness in regulating existing nuclear power plants and in preparing to license new nuclear reactors designs. Many of the findings identified in the 2006 report had been fully addressed and therefore could be considered closed, the others are being addressed in accordance with a comprehensive action plan. IRRS team members visited the Heysham 1 Nuclear Power Plant near Lancaster, the Sellafield site at Cumbria and the Strategic Control Centre at Hutton, and they met senior managers from HSE and a UK

Judith Perera: 'Nuclear Power in Europe'-A review

International Nuclear Information System (INIS)

Pavel, Eugeniu

2000-01-01

The book published by Financial Time Energy, London 1999, presents the history of nuclear power and its current status in both Eastern and Western Europe. The book extends on 370 pages and is structured in 8 chapters, annexes, a glossary of terms and references. Romanian nuclear power is represented by the Cernavoda NPP Unit 1 commissioned in December 1996. Till September 1999 the production of Cernavoda NPP amounted up to 15,271 TWh with a internal consumption lower than 8%, which covered 10-14% of the total electric energy demand of Romania, at a 12 to 14 USD/MWh production cost. The statistical data show that: - with the highest nuclear energy quota appears US, namely with 28.1% of world nuclear power production; - in a classification on countries, Lithuania and France appear on the first place, namely with 77.2% and 75.8%, respectively, as share of nuclear energy in the total national energy production. A review of the reactor types mostly used world wide show that the PWR is the most used technology in France, Japan, USA and several other countries. The chapter two presents the performances of different reactor types among which AGR, BWR and PWR, the load factor of which appears to be the highest. The problems of fuel cycles, fuel conversion, enrichment and production are treated in Chapter 3. The following chapter presents the economic aspects of nuclear power, the energy costs being a pro in the public debates on the future of nuclear energy. A detailed analysis on the environmental impact of nuclear power production is given in Chapter 6. The situation of nuclear sector throughout Europe is shown in the following chapter while the last one is devoted to the main European power companies implied in the nuclear industry. In conclusion, the prospects of nuclear energy in Europe are reviewed by taking into account factors like: public acceptance, costs, competition, waste management, fuel market, safety environmental issues, in-service life, personnel

Early site reviews for nuclear power facilities: procedures and possible technical review options. Draft

International Nuclear Information System (INIS)

1978-02-01

The document provides guidance for utility companies, State and other governmental agencies, and others who may request or may wish to participate in an early review of site suitability issues related to a site proposed for a nuclear power or test reactor. Although the emphasis of this document is on a nuclear electric generating station, the guidance provided can be used for a test reactor or other kinds of reactors. The procedures to be followed by applicants for construction permits and by others are described and the possible significant areas of technical review are delineated

A literature review of the cost-effectiveness of nuclear medicine

International Nuclear Information System (INIS)

Carter, J.

1995-01-01

Nuclear medicine is a medical speciality that uses tiny quantities of radioactivity to produce diagnostic images. It also has a role in therapy for some thyroid diseases and certain tumours. Surveys have shown that nuclear medicine procedures are used significantly less in the UK than in many other countries in Europe. One reason may be that there is inadequate information about the clinical utility of these techniques, particularly their cost-effectiveness in clinical management. To establish what evidence was currently available about the cost-effectiveness of nuclear medicine, the British Nuclear Medicine Society commissioned a worldwide literature review in diseases of the heart, kidney, lung, bone, brain, bowel and thyroid. This volume summarises the findings of the independent study and gives details of the background, clinical utility and limitations of the different nuclear medicine procedures used in the diagnosis and treatment of each disease reviewed. (author)

A web-based e-learning framework for public perception and acceptance on nuclear energy

International Nuclear Information System (INIS)

Zhou Yangping; Yoshikawa, Hidekazu; Liu Jingquan; Ouyang, Jun; Lu Daogang

2005-01-01

Now, public acceptance plays a central role in the nuclear energy. Public concerns on safety and sustainability of nuclear energy, ground nuclear power in many countries and territories to a stop or even a downfall. In this study, an e-learning framework by using Internet, is proposed for public education in order to boost public perception on nuclear energy, which will certainly affect public acceptance toward it. This study aims at investigating public perception and acceptance on nuclear energy in a continuous and accurate manner. In addition, this e-learning framework can promote public perception on nuclear energy by using teaching material with a graphical hierarchy about knowledge of nuclear energy. This web-based e-learning framework mainly consists of two components: (1) an e-learning support module which continuously investigates public perception and acceptance toward nuclear energy and teaches public knowledge about nuclear energy; (2) an updating module which may improve the education materials by analyzing the effect of education or proving the materials submitted by the visitors through Wiki pages. Advantages and future work of this study are also generally described. (author)

A Review of Ground Target Detection and Classification Techniques in Forward Scattering Radars

Directory of Open Access Journals (Sweden)

M. E. A. Kanona

2018-06-01

Full Text Available This paper presents a review of target detection and classification in forward scattering radar (FSR which is a special state of bistatic radars, designed to detect and track moving targets in the narrow region along the transmitter-receiver base line. FSR has advantages and incredible features over other types of radar configurations. All previous studies proved that FSR can be used as an alternative system for ground target detection and classification. The radar and FSR fundamentals were addressed and classification algorithms and techniques were debated. On the other hand, the current and future applications and the limitations of FSR were discussed.

On mean wind and turbulence profile measurements from ground-based wind lidars

DEFF Research Database (Denmark)

Mikkelsen, Torben

2009-01-01

Two types of wind lidar?s have become available for ground-based vertical mean wind and turbulence profiling. A continuous wave (CW) wind lidar, and a pulsed wind lidar. Although they both are build upon the same recent 1.55 μ telecom fibre technology, they possess fundamental differences between...... their temporal and spatial resolution capabilities. A literature review of the two lidar systems spatial and temporal resolution characteristics will be presented, and the implication for the two lidar types vertical profile measurements of mean wind and turbulence in the lower atmospheric boundary layer...

Neutrons in basic and applied nuclear research - a review

International Nuclear Information System (INIS)

Bhattacharya, Sailajananda

2013-01-01

Energetic neutron sources, both white and mono-energetic, are widely used In basic nuclear physics as well as various multidisciplinary research. Precise measurement of various neutron induced reaction cross-sections are crucial for the design and development of new generation of reactors, like accelerator driven subcritical systems, nuclear incinerators, etc. A review of some recent trends in neutron induced basic and applied nuclear research will be presented in this talk. (author)

Nuclear safety review for the year 2000

International Nuclear Information System (INIS)

2001-06-01

The nuclear safety review for the year 2000 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts: Part 1 describes those events in 2000 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety; Part 2 describes some of the IAEA efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2000. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2000; Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2000 was presented to the March 2001 session of the IAEA Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2001 that were considered pertinent to the discussion of events during 2000. In such cases, a note containing the more recent information has been provided in the form of a footnote

Movement of radionuclides from river to ground water in vicinity of location for nuclear power plant

International Nuclear Information System (INIS)

Knezevic, Lj.; Lazic, S.; Vukovic, Z.

1984-01-01

The possibility of ground water contamination caused by radionuclide from river water to which liquid effluents were released from a nuclear power station was estimated using one-dimensional transport model. This model is suitable for a homogeneous medium and takes into account hydraulic convection and dispersion as well as physical-chemical retardation for the various radionuclides. (author)

Foundation Investigation for Ground Based Radar Project-Kwajalein Island, Marshall Islands

Science.gov (United States)

1990-04-01

iL_ COPY MISCELLANEOUS PAPER GL-90-5 i iFOUNDATION INVESTIGATION FOR GROUND BASED RADAR PROJECT--KWAJALEIN ISLAND, MARSHALL ISLANDS by Donald E...C!assification) Foundatioa Investigation for Ground Based Radar Project -- Kwajalein Island, Marshall Islands 12. PERSONAL AUTHOR(S) Yule, Donald E...investigation for the Ground Based Radar Project -- Kwajalein Island, Marshall Islands , are presented.- eophysical tests comprised of surface refrac- tion

A review on the Warsaw Summit: nuclear aspects

International Nuclear Information System (INIS)

Grand, Camille

2016-01-01

Written at the time of the Ukrainian crisis, this article discusses the evolution of the international and nuclear deterrence context, notably for NATO due to Russia's attitudes and actions. The author questions the opportunity or possible need for reviewing Nato's posture in terms of nuclear defence and deterrence. More precisely, the role of nuclear weapons in Nato's defence and deterrence must be more precisely defined. The evolving context and a stronger deterrence also require conventional capacities, and the author outlines that Nato's determination must be better and more firmly stated

Review: Ina-Maria Greverus, Sharon MacDonald, Regina Romhild, Gisela Welz & Helena Wullf (Eds. (2002. Stability Upon Shifting Ground: Review Note of Shifting Grounds: Experiments in Doing Ethnography

Directory of Open Access Journals (Sweden)

Robin M. Boylorn

2005-09-01

Full Text Available This review is written in response to "Shifting Grounds: Experiments in Doing Ethno­graphy," a volume of the Anthropological Journal on European Cultures. This review cites the history and implications of ethnography as a methodology within various academic disciplines while praising the authors within this text for their contributions to various ways of "doing ethnography." By investi­gating and considering the body as an ethno­graphic site where life and stories are performed and em­bodied, this article considers the varying ways the authors respond to experimental and performative ethnography while applying it to relevant and current issues within anthropology. By engaging both the anthropological and historical turn of ethnography, this book thematically discusses the mobility of fieldwork, time, space, multi-locality, tour­ism, and tradition/culture. Shifting Grounds does not only offer experiments in doing ethnography, it also offers alternatives for doing ethnography. URN: urn:nbn:de:0114-fqs0503175

Proceedings of the 23rd Seismic Research Symposium: Worldwide Monitoring of Nuclear Explosions

International Nuclear Information System (INIS)

Warren, N. Jill; Chavez, Francesca C.

2001-01-01

These proceedings contain papers prepared for the 23rd Seismic Research Review: Worldwide Monitoring of Nuclear Explosions, held 2-5 October, 2001 in Jackson Hole, Wyoming. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Technical Applications Center (AFTAC), the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

Nuclear reaction inputs based on effective interactions

Energy Technology Data Exchange (ETDEWEB)

Hilaire, S.; Peru, S.; Dubray, N.; Dupuis, M.; Bauge, E. [CEA, DAM, DIF, Arpajon (France); Goriely, S. [Universite Libre de Bruxelles, Institut d' Astronomie et d' Astrophysique, CP-226, Brussels (Belgium)

2016-11-15

Extensive nuclear structure studies have been performed for decades using effective interactions as sole input. They have shown a remarkable ability to describe rather accurately many types of nuclear properties. In the early 2000 s, a major effort has been engaged to produce nuclear reaction input data out of the Gogny interaction, in order to challenge its quality also with respect to nuclear reaction observables. The status of this project, well advanced today thanks to the use of modern computers as well as modern nuclear reaction codes, is reviewed and future developments are discussed. (orig.)

Organization and conduct of IAEA fire safety reviews at nuclear power plants

International Nuclear Information System (INIS)

1998-01-01

The importance of fire safety in the safe and productive operation of nuclear power plants is recognized worldwide. Lessons learned from experience in nuclear power plants indicate that fire poses a real threat to nuclear safety and that its significance extends far beyond the scope of a conventional fire hazard. With a growing understanding of the close correlation between the fire hazard in nuclear power plants and nuclear safety, backfitting for fire safety has become necessary for a number of operating plants. However, it has been recognized that the expertise necessary for a systematic independent assessment of fire safety of a NPP may not always be available to a number of Member States. In order to assist in enhancing fire safety, the IAEA has already started to offer various services to Member States in the area of fire safety. At the request of a Member State, the IAEA may provide a team of experts to conduct fire safety reviews of varying scope to evaluate the adequacy of fire safety at a specific nuclear power plant during various phases such as construction, operation and decommissioning. The IAEA nuclear safety publications related to fire protection and fire safety form a common basis for these reviews. This report provides guidance for the experts involved in the organization and conduct of fire safety review services to ensure consistency and comprehensiveness of the reviews

Oil and nuclear power: the dynamic interrelationship

International Nuclear Information System (INIS)

Stauffer, T.

1987-01-01

The impact of changing oil prices on the economic case for nuclear power and the political viability of the nuclear industry is reviewed. The case for nuclear energy is less obvious currently on the grounds of safety (following the Chernobyl accident), need (because of slower economic growth and energy conservation) and rationale (the cost advantage is no longer obvious). Nuclear power and oil prices are shown to be interrelated because the competitive economics of each is affected by the other. The competitive balance between the two changes. The use of nuclear power helps to keep oil prices down. However, if oil is cheap, nuclear power is less favourable economically. Some facts and figures are used to illustrate this paradox. (U.K.)

Nuclear Safety Review for the Year 2008

International Nuclear Information System (INIS)

2009-07-01

's Response Assistance Network. In July 2008, an emergency exercise, hosted by Mexico and known as ConvEx3 (2008), tested the international response to a simulated accident at a nuclear power plant. The Agency used its Incident and during the exercise. The importance of having effective civil liability mechanisms in place to insure against harm to human health and the environment, as well as actual economic loss caused by nuclear damage, receives continued attention among Member States. The deposit by the USA of its instrument of ratification of the Convention on Supplementary Compensation for Nuclear Damage (CSC) marked an important milestone towards bringing the entry into force of the CSC. The International Expert Group on Nuclear Liability (INLEX) continues to serve as the Agency's main forum dealing with questions related to nuclear liability. In 2008, INLEX discussed, inter alia, outreach activities and the ongoing European Commission's impact assessment on nuclear liability. Nuclear power plant operators continued to show strong safety performance in 2008, with no serious accidents or significant radiation exposure to workers or the public to report. During the Agency's International Conference on Topical Issues in Nuclear Installation Safety, held in Mumbai, India in November 2008, participants concluded that an integrated nuclear safety approach based on the defence in depth principle and deterministic criteria, when properly applied and complemented with probabilistic analyses and operational experience feedback, continues to be successful. The reevaluation of the integrity of existing nuclear installations, taking into account the increased magnitude observed during recent severe earthquakes and extreme natural events, has begun. At the request of Member States, the Agency has conducted generic reactor safety reviews to assess new nuclear power plant designs for consistency with the Agency's safety standards.

Nuclear Technology Review 2014

International Nuclear Information System (INIS)

2014-08-01

With 434 nuclear power reactors in operation worldwide at the end of 2013, nuclear energy had a global generating capacity of 371.7 GW(e). There were four new grid connections and ten construction starts on new reactors. Belarus became the second nuclear ‘newcomer’ State in three decades to start building its first nuclear power plant. Near and long term growth prospects remained centred in Asia, particularly in China. The 72 reactors under construction in 2013 represented the highest number since 1989. Of these, 48 were in Asia, as were 42 of the last 52 new reactors to have been connected to the grid since 2000. Thirty States currently use nuclear power and about the same number are considering including it as part of their energy mix. Of the 30 States already operating nuclear power plants, 13 are either constructing new plants or actively completing previously suspended constructions, and 12 are planning to either construct new plants or to complete suspended constructions. The IAEA Ministerial Conference on Nuclear Power in the 21st Century, held in June 2013, reaffirmed that nuclear power remains an important option for many States to improve energy security, reduce the impact of volatile fossil fuels prices and mitigate the effects of climate change. The Concluding Statement said that “nuclear power, as a stable base-load source of electricity in an era of ever increasing global energy demands, complements other energy sources including renewables.” In the IAEA’s 2013 projections, nuclear power is expected to grow by between 17% as the low projection and 94% as the high projection by 2030. These figures are slightly lower than projected in 2012, reflecting the continued impact of the Fukushima Daiichi accident, the low prices of natural gas and the increasing use of renewable energy. Additional information focuses on the linkages between nuclear power and climate change, as nuclear power, hydropower and wind energy have the lowest life cycle

Review of the environmental impact of nuclear energy

International Nuclear Information System (INIS)

El-Hinnawi, E.E.

1977-01-01

Nuclear power is one of the alternative sources for meeting the increasing world requirements for energy production. The world's nuclear electrical power production has been increasing at a rapid rate and is expected to reach about 620 GWe by 1985 and about 3300 GWe by the year 2000. This continuing increase would be impossible without an equivalent expansion of available fuel supplies, enrichment capacity, fuel fabrication capacity, irradiated fuel reprocessing capacity, and finally appropriate facilities for dealing with the nuclear wastes which will arise in due course. The present report reviews the environmental impacts encountered at each step of the nuclear fuel cycle which consists of the processes of mining and milling of uranium ores, conversion to fuel material and fabrication of fuel elements, reactor design and operation, reprocessing of spent fuel, and disposal of radioactive wastes. It also includes a review of the environmental impact of transportation of radioactive material between installations handling different steps of the cycle. Although the environmental impacts arising at certain stages in the nuclear fuel cycle are similar to some of those encountered in the fossil-fuel cycle (for example, the ecological effects of strip mining of ores and/or thermal discharges), there are some unique impacts related to nuclear power generation. Perhaps the most important of these is the radioactivity released from the decay products of nuclear fission. Although most of the radionuclides released into the environment are of local or regional concern, because their half-lives are short compared to the time involved in their dispersion, some radionuclides have long half-lives and can, therefore, become widely distributed. This has been the main focus of public concern and debate with respect to the expansion in nuclear power utilisation, in spite of the strict regulations and safety measures undertaken

Response of base-isolated nuclear structures to extreme earthquake shaking

Energy Technology Data Exchange (ETDEWEB)

Kumar, Manish, E-mail: mkumar2@buffalo.edu; Whittaker, Andrew S.; Constantinou, Michael C.

2015-12-15

Highlights: • Response-history analysis of nuclear structures base-isolated using lead–rubber bearings is performed. • Advanced numerical model of lead–rubber bearing is used to capture behavior under extreme earthquake shaking. • Results of response-history analysis obtained using simplified and advanced model of lead–rubber bearings are compared. • Heating of the lead core and variation in buckling load and axial stiffness affect the response. - Abstract: Seismic isolation using low damping rubber and lead–rubber bearings is a viable strategy for mitigating the effects of extreme earthquake shaking on safety-related nuclear structures. The mechanical properties of these bearings are not expected to change substantially in design basis shaking. However, under shaking more intense than design basis, the properties of the lead cores in lead–rubber bearings may degrade due to heating associated with energy dissipation, some bearings in an isolation system may experience net tension, and the compression and tension stiffness may be affected by the lateral displacement of the isolation system. The effects of intra-earthquake changes in mechanical properties on the response of base-isolated nuclear power plants (NPPs) are investigated using an advanced numerical model of a lead–rubber bearing that has been verified and validated, and implemented in OpenSees. A macro-model is used for response-history analysis of base-isolated NPPs. Ground motions are selected and scaled to be consistent with response spectra for design basis and beyond design basis earthquake shaking at the site of the Diablo Canyon Nuclear Generating Station. Ten isolation systems of two periods and five characteristic strengths are analyzed. The responses obtained using simplified and advanced isolator models are compared. Strength degradation due to heating of lead cores and changes in buckling load most significantly affect the response of the base-isolated NPP.

Response of base-isolated nuclear structures to extreme earthquake shaking

International Nuclear Information System (INIS)

Kumar, Manish; Whittaker, Andrew S.; Constantinou, Michael C.

2015-01-01

Highlights: • Response-history analysis of nuclear structures base-isolated using lead–rubber bearings is performed. • Advanced numerical model of lead–rubber bearing is used to capture behavior under extreme earthquake shaking. • Results of response-history analysis obtained using simplified and advanced model of lead–rubber bearings are compared. • Heating of the lead core and variation in buckling load and axial stiffness affect the response. - Abstract: Seismic isolation using low damping rubber and lead–rubber bearings is a viable strategy for mitigating the effects of extreme earthquake shaking on safety-related nuclear structures. The mechanical properties of these bearings are not expected to change substantially in design basis shaking. However, under shaking more intense than design basis, the properties of the lead cores in lead–rubber bearings may degrade due to heating associated with energy dissipation, some bearings in an isolation system may experience net tension, and the compression and tension stiffness may be affected by the lateral displacement of the isolation system. The effects of intra-earthquake changes in mechanical properties on the response of base-isolated nuclear power plants (NPPs) are investigated using an advanced numerical model of a lead–rubber bearing that has been verified and validated, and implemented in OpenSees. A macro-model is used for response-history analysis of base-isolated NPPs. Ground motions are selected and scaled to be consistent with response spectra for design basis and beyond design basis earthquake shaking at the site of the Diablo Canyon Nuclear Generating Station. Ten isolation systems of two periods and five characteristic strengths are analyzed. The responses obtained using simplified and advanced isolator models are compared. Strength degradation due to heating of lead cores and changes in buckling load most significantly affect the response of the base-isolated NPP.

Review of underground siting of nuclear power plants

International Nuclear Information System (INIS)

1974-01-01

A review of the potential for the underground siting of nuclear power generating plants has been undertaken. The review comprised a survey and assessment of relevant published documents currently available, together with discussions with Government sponsored agencies and other bodies, to evaluate the current status of technology related to the design and construction of underground nuclear power plants. It includes a review of previous work related to the underground siting of power plants and other facilities; a preliminary evaluation of the relative merits of the various concepts of undergrounding which have been proposed or constructed; a review of current technology as it relates to the requirements for the design, construction and operation of underground nuclear power plants; an examination of the safety and environmental aspects; and the identification of areas of further study which will be required if the underground is to be established as a fully viable alternative to surface siting. No attempt has been made to draw final conclusions at this stage. Nothing has been found to suggest that the underground siting concept could not provide a viable alternative to the surface concept. It is also apparent that no major technological developments are required. It is not clear, however, whether the improvements in safety and containment postulated for the underground can be realized at an economic cost; or even whether any additional cost is in fact involved. The problem is essentially site dependent and requires further study for which recommendations are made. (auth)

Nuclear Technology Review 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-09-15

In 2009, construction started on 12 new nuclear power reactors, the largest number since 1985, and projections of future nuclear power growth were once again revised upwards. However, only two new reactors were connected to the grid, and, with three reactors retired during the year, the total nuclear power capacity around the world dropped slightly for the second year in a row. Current expansion, as well as near term and long term growth prospects, remain centred in Asia. Ten of the 12 construction starts were in Asia, as were both of the new grid connections. Although the global financial crisis that started in the second half of 2008 did not dampen overall projections for nuclear power, it was cited as a contributing factor in near-term delays or postponements affecting nuclear projects in some regions of the world. In some European countries where previously there were restrictions on the future use of nuclear power, there was a trend towards reconsidering these policies. Interest in starting new nuclear power programmes remained high. Over 60 Member States have expressed to the IAEA interest in considering the introduction of nuclear power, and, in 2009, the IAEA conducted its first Integrated Nuclear Infrastructure Review missions in Jordan, Indonesia and Vietnam. Estimates of identified conventional uranium resources (at less than $130/kg U) increased slightly, due mainly to increases reported by Australia, Canada and Namibia. Uranium spot prices declined, and final data for 2009 are expected to show a consequent decrease in uranium exploration and development. The Board of Governors has authorized the IAEA Director General to sign an agreement with the Russian Federation to establish an international reserve of low enriched uranium (LEU). It would contain 120 tonnes of LEU that could be made available to a country affected by a non-commercial interruption of its LEU supply. The agreement between the IAEA and the Russian Federation was signed in March 2010

Nuclear Technology Review 2010

International Nuclear Information System (INIS)

2010-09-01

In 2009, construction started on 12 new nuclear power reactors, the largest number since 1985, and projections of future nuclear power growth were once again revised upwards. However, only two new reactors were connected to the grid, and, with three reactors retired during the year, the total nuclear power capacity around the world dropped slightly for the second year in a row. Current expansion, as well as near term and long term growth prospects, remain centred in Asia. Ten of the 12 construction starts were in Asia, as were both of the new grid connections. Although the global financial crisis that started in the second half of 2008 did not dampen overall projections for nuclear power, it was cited as a contributing factor in near-term delays or postponements affecting nuclear projects in some regions of the world. In some European countries where previously there were restrictions on the future use of nuclear power, there was a trend towards reconsidering these policies. Interest in starting new nuclear power programmes remained high. Over 60 Member States have expressed to the IAEA interest in considering the introduction of nuclear power, and, in 2009, the IAEA conducted its first Integrated Nuclear Infrastructure Review missions in Jordan, Indonesia and Vietnam. Estimates of identified conventional uranium resources (at less than $130/kg U) increased slightly, due mainly to increases reported by Australia, Canada and Namibia. Uranium spot prices declined, and final data for 2009 are expected to show a consequent decrease in uranium exploration and development. The Board of Governors has authorized the IAEA Director General to sign an agreement with the Russian Federation to establish an international reserve of low enriched uranium (LEU). It would contain 120 tonnes of LEU that could be made available to a country affected by a non-commercial interruption of its LEU supply. The agreement between the IAEA and the Russian Federation was signed in March 2010

Effects on radionuclide concentrations by cement/ground-water interactions in support of performance assessment of low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Krupka, K.M.; Serne, R.J.

1998-05-01

The US Nuclear Regulatory Commission is developing a technical position document that provides guidance regarding the performance assessment of low-level radioactive waste disposal facilities. This guidance considers the effects that the chemistry of the vault disposal system may have on radionuclide release. The geochemistry of pore waters buffered by cementitious materials in the disposal system will be different from the local ground water. Therefore, the cement-buffered environment needs to be considered within the source term calculations if credit is taken for solubility limits and/or sorption of dissolved radionuclides within disposal units. A literature review was conducted on methods to model pore-water compositions resulting from reactions with cement, experimental studies of cement/water systems, natural analogue studies of cement and concrete, and radionuclide solubilities experimentally determined in cement pore waters. Based on this review, geochemical modeling was used to calculate maximum concentrations for americium, neptunium, nickel, plutonium, radium, strontium, thorium, and uranium for pore-water compositions buffered by cement and local ground-water. Another literature review was completed on radionuclide sorption behavior onto fresh cement/concrete where the pore water pH will be greater than or equal 10. Based on this review, a database was developed of preferred minimum distribution coefficient values for these radionuclides in cement/concrete environments

Effects on radionuclide concentrations by cement/ground-water interactions in support of performance assessment of low-level radioactive waste disposal facilities

Energy Technology Data Exchange (ETDEWEB)

Krupka, K.M.; Serne, R.J. [Pacific Northwest National Lab., Richland, WA (United States)

1998-05-01

The US Nuclear Regulatory Commission is developing a technical position document that provides guidance regarding the performance assessment of low-level radioactive waste disposal facilities. This guidance considers the effects that the chemistry of the vault disposal system may have on radionuclide release. The geochemistry of pore waters buffered by cementitious materials in the disposal system will be different from the local ground water. Therefore, the cement-buffered environment needs to be considered within the source term calculations if credit is taken for solubility limits and/or sorption of dissolved radionuclides within disposal units. A literature review was conducted on methods to model pore-water compositions resulting from reactions with cement, experimental studies of cement/water systems, natural analogue studies of cement and concrete, and radionuclide solubilities experimentally determined in cement pore waters. Based on this review, geochemical modeling was used to calculate maximum concentrations for americium, neptunium, nickel, plutonium, radium, strontium, thorium, and uranium for pore-water compositions buffered by cement and local ground-water. Another literature review was completed on radionuclide sorption behavior onto fresh cement/concrete where the pore water pH will be greater than or equal 10. Based on this review, a database was developed of preferred minimum distribution coefficient values for these radionuclides in cement/concrete environments.

Monitoring of natural revegetation of Semipalatinsk nuclear testing ground

International Nuclear Information System (INIS)

Sultanova, B.M.

2002-01-01

It is well known, that monitoring of natural revegetation of Semipalatinsk test site (STS) was carried out during period 1994-2002 at test areas (Experimental field, Balapan, Degelen). In this paper the peculiarities of vegetation cover of these test areas are observed. Thus, vegetation cover of Experimental field ground in the epicentre is completely destroyed. At present there are different stages of zonal steppe communities rehabilitation: in zones with γ-irradiation 11000-14000 μR/h the revegetation is not found; on the plots with γ-irradiation 8200-10000 μR/h rare species of Artemisia frigida are found; aggregation of plant (managed from 6000-7000 μR/h is observed; At the γ-irradiation 80-200 μR/h rarefied groups of bunch grass communities similar to the zonal steppe are formed and zonal bunch grass communities developed with 18-25 μR/h. Vegetation cover of Degelen hill tops and near-mouth ground in the results of underground nuclear expulsions are completely destroyed. Here there are three main kinds of vegetation: very stony gallery areas don't almost overgrow; at technogen tops near galleries the single plants, rare field groups and unclosed micro-phyto-biocenoses of weed and adventive species (Amaranthus retroflexus, Artemisia dracunculus, Laxctuca serriola, Chorispora sibirica etc.). On the Balapan are the revegetation is limited by high radiation pollution rate. Here cenose rehabilitation is presented by Artemisia marshalliana, Spita sareptana, Festuca valresiaca). In their paper florostic and phyrocoenitic diversity of STS's flora transformation is studied. Pattern distribution and migration of radionuclides in soils and vegetation cover is represented

The nuclear option in Canada - why it is gaining ground

International Nuclear Information System (INIS)

Hopwood, J.M.; Alizadeh, A.; Hedges, K.R.; Tighe, P.

2005-01-01

Over the last five years, the nuclear option in Canada has gone from 'off-the-radar' to an essential part of the energy debate. In Ontario, in particular, building new nuclear plants, along with life-extension of existing plants, has been recommended by government commissions as one of the vital energy-supply options to be pursued. Both life-extension and introduction of new nuclear power plants are complicated by uncertainties in the energy market, and by changes in the organizational and policy environment. Public and policy-maker recognition of the nuclear role are steadily growing, but commercial conditions to support nuclear projects are still difficult to define and obtain. In Canada, as in many OECD countries, the need to add to electricity infrastructure is becoming apparent. Life-extension of existing nuclear units, and projects to build new unit, are being planned. The key challenges, once energy policy issues have been addressed, are mainly commercial. Based on its successful experience with overseas projects such as Quinshan, and on its evolutionary approach to design of new, advanced power plants, AECL is well placed to meet these challenges and launch a new round of nuclear projects. Overall, the Canadian perspective is towards increasing support for the nuclear option. Canada is poised to join the vanguard of the broadening nuclear power expansion. (orig.)

Fundamental bases to implementation the specific national norm for nuclear gauges

International Nuclear Information System (INIS)

Ferreira, L.C.; Silva, E.R.; Ferreira, R.; Peixoto, J.G.P.

2017-01-01

The aims of this work is to provide grounds for creation a national standard practice security and responsibility in the use of nuclear gauges in accordance with the national recommendation already exist, following the basic security principles, responsibilities of these involved in the acquisition, operation, storage, maintenance and post-emergency on use of nuclear gauges. (author)

Systematic review of perceptive studies on nuclear risk; Revisao sistematica de estudos perceptivos sobre risco nuclear

Energy Technology Data Exchange (ETDEWEB)

Freitas, Mariana Gama de

2014-07-01

This present work contains the study of risk perception in different areas of interaction. For it was made an analysis using methodology previously recognized and tested: a systematic review in the search for better understanding of the perception of risk in the nuclear area. Through this study it was possible to understand the potential of the systematic review as a tool for information that encompass the perception of risk as a whole. Making it possible to trace parameters to find out why the world's people have an aversion to certain matters relating to nuclear energy. Considering that if you can understand what drives the people has disgust on nuclear area, it is probably possible to create alternatives to remedy this lack of information and knowledge about the area. Causing the population to realize the benefits that nuclear power brings to people. (author)

Laser-based analytical monitoring in nuclear-fuel processing plants

International Nuclear Information System (INIS)

Hohimer, J.P.

1978-09-01

The use of laser-based analytical methods in nuclear-fuel processing plants is considered. The species and locations for accountability, process control, and effluent control measurements in the Coprocessing, Thorex, and reference Purex fuel processing operations are identified and the conventional analytical methods used for these measurements are summarized. The laser analytical methods based upon Raman, absorption, fluorescence, and nonlinear spectroscopy are reviewed and evaluated for their use in fuel processing plants. After a comparison of the capabilities of the laser-based and conventional analytical methods, the promising areas of application of the laser-based methods in fuel processing plants are identified

Review of UCN 3,4 PSA model based on NEI PRA peer review process guidance, rev.0

International Nuclear Information System (INIS)

Yang, Joon Eon; Kang, D. I.; Kim, K. Y.; Lee, Y. H.; Jang, S. C.; Ha, J. J.; Han, S. H.; Han, S. J.; Hwang, M. J.

2003-05-01

Recently, under the de-regulation environment, nuclear industry has attempted various approaches to improve the economics of Nuclear Power Plants (NPP). One of these efforts is the Risk Informed/Performance-Based Operation (RIPBO). This approach uses the risk and performance information to manage the resources effectively and efficiently that are used in the operation of NPP. In RIPBO, PSA quality is one of the most important things. The nuclear industry and regulatory body of U.S.A have developed a measure to evaluate the quality of PSA. NEI (Nuclear Energy Institute) has developed a guidance called 'NEI PRA Peer Review Guidance,' and NRC (Nuclear Regulatory Committee) and ASME have developed the 'PRA Standard.' In Korea, several projects are on going now, such as the extension of AOT/STI of RPS/ESFAS, Risk-Informed In-Service Inspection (RI-ISI). However, in Korea, there have been no attempts to evaluate the quality of PSA model itself. Therefore, we cannot be sure about the quality of PSA whether or not the present PSA model can be used for the risk-informed applications such as mentioned above. We can say that the evaluation of PSA model quality is the basis for the RIPBO. In this report, we have evaluated the quality of PSA model for Ulchin 3 and 4 units based on the NEI guidance. We, also, have derived what items are to be improved to upgrade the quality of PSA model and how it can be improved. This report can be used as the base of RIPBO work in Korea. The review result based on ASME Standard is published as the separated technical report of KAERI

Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review

Energy Technology Data Exchange (ETDEWEB)

Thiel, Elizabeth Chilcote

2002-05-01

The Nuclear Materials Focus Area (NMFA) held its annual mid-year review on February 12 and 14, 2002, in Santa Fe, New Mexico. The purpose of this review was to examine both the technical aspects and the programmatic aspects of its technology development program. The focus area activities were reviewed by a panel consisting of personnel representing the end users of the technologies, and technical experts in nuclear materials. This year's review was somewhat different than in the past, as the stress was on how well the various projects being managed through the NMFA aligned with the two thrust areas and nine key goals and priorities recently issued by the Deputy Assistant Secretary for DOE's Office of Environmental Management (EM).

Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review

Energy Technology Data Exchange (ETDEWEB)

Thiel, E.C.; Fuhrman, P.W.

2002-05-30

The Nuclear Materials Focus Area (NMFA) held its annual mid-year review on February 12 and 14, 2002, in Santa Fe, New Mexico. The purpose of this review was to examine both the technical aspects and the programmatic aspects of its technology development program. The focus area activities were reviewed by a panel consisting of personnel representing the end users of the technologies, and technical experts in nuclear materials. This year's review was somewhat different than in the past, as the stress was on how well the various projects being managed through the NMFA aligned with the two thrust areas and nine key goals and priorities recently issued by the Deputy Assistant Secretary for DOE's Office of Environmental Management (EM).

Thorium-based nuclear fuel: current status and perspectives

International Nuclear Information System (INIS)

1987-03-01

Until the present time considerable efforts have already been made in the area of fabrication, utilization and reprocessing of Th-based fuels for different types of reactors, namely: by FRG and USA - for HTRs; FRG and Brazil, Italy - for LWRs; India - for HWRs and FBRs. Basic research of thorium fuels and thorium fuel cycles are also being undertaken by Australia, Canada, China, France, FRG, Romania, USSR and other countries. Main emphasis has been given to the utilization of thorium fuels in once-through nuclear fuel cycles, but in some projects closed thorium-uranium or thorium-plutonium fuel cycles are also considered. The purpose of the Technical Committee on the Utilization of Thorium-Based Nuclear Fuel: Current Status and Perspective was to review the world thorium resources, incentives for further exploration, obtained experience in the utilization of Th-based fuels in different types of reactors, basic research, fabrication and reprocessing of Th-based fuels. As a result of the panel discussion the recommendations on future Agency activities and list of major worldwide activities in the area of Th-based fuel were developed. A separate abstract was prepared for each of the 9 papers in this proceedings series

Practical Applications of Cosmic Ray Science: Spacecraft, Aircraft, Ground-Based Computation and Control Systems, and Human Health and Safety

Science.gov (United States)

Atwell, William; Koontz, Steve; Normand, Eugene

2012-01-01

Three twentieth century technological developments, 1) high altitude commercial and military aircraft; 2) manned and unmanned spacecraft; and 3) increasingly complex and sensitive solid state micro-electronics systems, have driven an ongoing evolution of basic cosmic ray science into a set of practical engineering tools needed to design, test, and verify the safety and reliability of modern complex technological systems. The effects of primary cosmic ray particles and secondary particle showers produced by nuclear reactions with the atmosphere, can determine the design and verification processes (as well as the total dollar cost) for manned and unmanned spacecraft avionics systems. Similar considerations apply to commercial and military aircraft operating at high latitudes and altitudes near the atmospheric Pfotzer maximum. Even ground based computational and controls systems can be negatively affected by secondary particle showers at the Earth s surface, especially if the net target area of the sensitive electronic system components is large. Finally, accumulation of both primary cosmic ray and secondary cosmic ray induced particle shower radiation dose is an important health and safety consideration for commercial or military air crews operating at high altitude/latitude and is also one of the most important factors presently limiting manned space flight operations beyond low-Earth orbit (LEO). In this paper we review the discovery of cosmic ray effects on the performance and reliability of microelectronic systems as well as human health and the development of the engineering and health science tools used to evaluate and mitigate cosmic ray effects in ground-based atmospheric flight, and space flight environments. Ground test methods applied to microelectronic components and systems are used in combinations with radiation transport and reaction codes to predict the performance of microelectronic systems in their operating environments. Similar radiation transport

The prospects for nuclear power in the UK. Conclusions of the Government's nuclear review

International Nuclear Information System (INIS)

1995-05-01

The conclusions of the United Kingdom government's review of the nuclear industry in Britain were presented to Parliament in May 1995. The provision of public sector support for a new nuclear power station is deemed unwarranted against the background of the current electricity market. In reaching this conclusion the government considered possible environmental and strategic advantages, the question of diversity of fuel sources, and wider economic benefits. It is intended to privatize parts of Nuclear Electric and Scottish Nuclear in 1996 as subsidiaries of a single holding company to take over the UK's AGR and PWR stations together with a significant level of their associated liabilities. A publicly owned company will continue to run the magnox stations and retain their liabilities. British Nuclear Fuels Ltd (BNFL) will continue to offer nuclear fuel services and to receive government support in developing business in overseas markets. Since their formation in 1990, Nuclear Electric and Scottish Nuclear have improved their financial performance significantly. At privatisation the nuclear component of the fossil fuel levy will cease to be paid to Nuclear Electric and Scottish Nuclear will no longer receive the current premium price paid under the Nuclear Energy Agreement. The current regulatory regime and rigorous safety standards for nuclear power will remain substantially unchanged. (UK)

IAEA Operational Safety Team Reviews Cattenom Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts led by the International Atomic Energy Agency (IAEA) has reviewed operational safety at France's Cattenom Nuclear Power Plant (NPP) noting a series of good practices as well as recommendations and suggestions to reinforce them. The IAEA assembled an international team of experts at the request of the Government of France to conduct an Operational Safety Review (OSART) of Cattenom NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review of the plant from 14 November to 1 December 2011. The team was made up of experts from Belgium, the Czech Republic, Finland, Germany, Hungary, Japan, Russia, Slovakia, South Africa, Sweden, Ukraine, the United Kingdom and the IAEA. The team at Cattenom conducted an in-depth review of the aspects essential to the safe operation of the NPP, which is largely under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. Cattenom is the first plant in Europe to voluntarily undertake a Severe Accident Management review during an OSART review. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: Sheets are displayed in storage areas where combustible material is present - these sheets are updated readily and accurately by the area owner to ensure that the fire limits are complied with; A simple container is attached to the neutron source handling device to ensure ease and safety of operations and reduce possible radiation exposure during use

The development of regulatory expectations for computer-based safety systems for the UK nuclear programme

Energy Technology Data Exchange (ETDEWEB)

Hughes, P. J. [HM Nuclear Installations Inspectorate Marine Engineering Submarines Defence Nuclear Safety Regulator Serco Assurance Redgrave Court, Merton Road, Bootle L20 7HS (United Kingdom); Westwood, R.N; Mark, R. T. [FLEET HQ, Leach Building, Whale Island, Portsmouth, PO2 8BY (United Kingdom); Tapping, K. [Serco Assurance,Thomson House, Risley, Warrington, WA3 6GA (United Kingdom)

2006-07-01

The Nuclear Installations Inspectorate (NII) of the UK's Health and Safety Executive (HSE) has completed a review of their Safety Assessment Principles (SAPs) for Nuclear Installations recently. During the period of the SAPs review in 2004-2005 the designers of future UK naval reactor plant were optioneering the control and protection systems that might be implemented. Because there was insufficient regulatory guidance available in the naval sector to support this activity the Defence Nuclear Safety Regulator (DNSR) invited the NII to collaborate with the production of a guidance document that provides clarity of regulatory expectations for the production of safety cases for computer based safety systems. A key part of producing regulatory expectations was identifying the relevant extant standards and sector guidance that reflect good practice. The three principal sources of such good practice were: IAEA Safety Guide NS-G-1.1 (Software for Computer Based Systems Important to Safety in Nuclear Power Plants), European Commission consensus document (Common Position of European Nuclear Regulators for the Licensing of Safety Critical Software for Nuclear Reactors) and IEC nuclear sector standards such as IEC60880. A common understanding has been achieved between the NII and DNSR and regulatory guidance developed which will be used by both NII and DNSR in the assessment of computer-based safety systems and in the further development of more detailed joint technical assessment guidance for both regulatory organisations. (authors)

BigBOSS: The Ground-Based Stage IV BAO Experiment

Energy Technology Data Exchange (ETDEWEB)

Schlegel, David; Bebek, Chris; Heetderks, Henry; Ho, Shirley; Lampton, Michael; Levi, Michael; Mostek, Nick; Padmanabhan, Nikhil; Perlmutter, Saul; Roe, Natalie; Sholl, Michael; Smoot, George; White, Martin; Dey, Arjun; Abraham, Tony; Jannuzi, Buell; Joyce, Dick; Liang, Ming; Merrill, Mike; Olsen, Knut; Salim, Samir

2009-04-01

The BigBOSS experiment is a proposed DOE-NSF Stage IV ground-based dark energy experiment to study baryon acoustic oscillations (BAO) and the growth of structure with an all-sky galaxy redshift survey. The project is designed to unlock the mystery of dark energy using existing ground-based facilities operated by NOAO. A new 4000-fiber R=5000 spectrograph covering a 3-degree diameter field will measure BAO and redshift space distortions in the distribution of galaxies and hydrogen gas spanning redshifts from 0.2< z< 3.5. The Dark Energy Task Force figure of merit (DETF FoM) for this experiment is expected to be equal to that of a JDEM mission for BAO with the lower risk and cost typical of a ground-based experiment.

International nuclear safety experts conclude IAEA peer review of China's regulatory system

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of senior experts on nuclear safety regulation today completed a two-week International Atomic Energy Agency (IAEA) review of the governmental and regulatory framework for nuclear safety in the People's Republic of China. The team identified good practices within the system and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of the People's Republic of China. The final report will be submitted to China by Autumn 2010. At the request of Chinese authorities, the IAEA assembled a team of 22 experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This mission is a peer review based on the IAEA Safety Standards . It is not an inspection, nor an audit. The experts came from 15 different countries: Australia, Canada, the Czech Republic, Finland, France, Hungary, Japan, Pakistan, the Republic of Korea, Slovenia, South Africa, Sweden, the United Kingdom, Ukraine and the United States. Mike Weightman, the United Kingdom's Head of Nuclear Directorate, HSE and HM Chief Inspector of Nuclear Installations said: ''I was honoured and pleased to lead such a team of senior regulatory experts from around the world, and I was impressed by their commitment, experience and hard work to provide their best advice possible. We had very constructive interactions with the Chinese authority to maximize the beneficial impact of the mission.'' The scope of the mission included the regulation of nuclear and radiation safety of the facilities and activities regulated by the Ministry of Environmental Protection (MEP) National Nuclear Safety Administration (NNSA). The mission was conducted from 18 to 30 July, mainly in Beijing. To observe Chinese regulatory activities, the IRRS team visited several nuclear facilities, including a nuclear power plant, a manufacturer of safety components for nuclear power plants, a research reactor, a fuel cycle facility, a waste management facility

Nuclear Technology Review 2007

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-08-15

The year 2006 saw increasing activities in the field of nuclear power. Significant plans for expansion were announced in some countries and plans for introducing nuclear power in some others. The year began with announcements by both the Russian Federation and the United States of America of international fuel cycle proposals in anticipation of a substantial expansion of nuclear power worldwide. In January, Russian President Vladimir Putin outlined a proposal to create 'a system of international centres providing nuclear fuel cycle services, including enrichment, on a non-discriminatory basis and under the control of the IAEA'. In February, the USA proposed a Global Nuclear Energy Partnership to develop advanced recycling technologies that would not separate pure plutonium; international collaboration in supplying fuel for States which agree not to pursue enrichment and reprocessing; advanced reactors to consume recycled spent fuel while providing energy; and safe and secure small reactors suited to the needs of developing countries. New medium-term projections by the IAEA and the International Energy Agency present a picture with opportunities for substantial nuclear expansion, but still with notable uncertainty. A number of countries have announced plans for significant expansion: China, India, Japan, Pakistan, the Russian Federation and the Republic of Korea. Announcements of planned license applications by US companies and consortia mentioned approximately 25 new reactors. Two site preparation applications were submitted in Canada. A major energy review by the United Kingdom concluded that new nuclear power stations would make a significant contribution to meeting the UK's energy policy goals. Utilities from Estonia, Lithuania and Latvia launched a joint feasibility study of a new nuclear power plant to serve all three countries, and Belarus, Egypt, Indonesia, Nigeria and Turkey made announcements of steps they are taking toward their first nuclear power plants

Nuclear Technology Review 2007

International Nuclear Information System (INIS)

2007-08-01

The year 2006 saw increasing activities in the field of nuclear power. Significant plans for expansion were announced in some countries and plans for introducing nuclear power in some others. The year began with announcements by both the Russian Federation and the United States of America of international fuel cycle proposals in anticipation of a substantial expansion of nuclear power worldwide. In January, Russian President Vladimir Putin outlined a proposal to create 'a system of international centres providing nuclear fuel cycle services, including enrichment, on a non-discriminatory basis and under the control of the IAEA'. In February, the USA proposed a Global Nuclear Energy Partnership to develop advanced recycling technologies that would not separate pure plutonium; international collaboration in supplying fuel for States which agree not to pursue enrichment and reprocessing; advanced reactors to consume recycled spent fuel while providing energy; and safe and secure small reactors suited to the needs of developing countries. New medium-term projections by the IAEA and the International Energy Agency present a picture with opportunities for substantial nuclear expansion, but still with notable uncertainty. A number of countries have announced plans for significant expansion: China, India, Japan, Pakistan, the Russian Federation and the Republic of Korea. Announcements of planned license applications by US companies and consortia mentioned approximately 25 new reactors. Two site preparation applications were submitted in Canada. A major energy review by the United Kingdom concluded that new nuclear power stations would make a significant contribution to meeting the UK's energy policy goals. Utilities from Estonia, Lithuania and Latvia launched a joint feasibility study of a new nuclear power plant to serve all three countries, and Belarus, Egypt, Indonesia, Nigeria and Turkey made announcements of steps they are taking toward their first nuclear power plants

Effect of earthquake and tsunami. Ground motion and tsunami observed at nuclear power station

International Nuclear Information System (INIS)

Hijikata, Katsuichirou

2012-01-01

Fukushima Daiichi and Daini Nuclear Power Stations (NPSs) were struck by the earthquake off the pacific coast in the Tohoku District, which occurred at 14:46 on March 11, 2011. Afterwards, tsunamis struck the Tohoku District. In terms of the earthquake observed at the Fukushima NPSs, the acceleration response spectra of the earthquake movement observed on the basic board of reactor buildings exceeded the acceleration response spectra of the response acceleration to the standard seismic ground motion Ss for partial periodic bands at the Fukushima Daiichi NPS. As for the Fukushima Daini NPS, the acceleration response spectra of the earthquake movement observed on the basic board of the reactor buildings was below the acceleration response spectra of the response acceleration to the standard seismic ground motion Ss. Areas inundated by Tsunami at each NPS were investigated and tsunami inversion analysis was made to build tsunami source model to reproduce tide record, tsunami height, crustal movement and inundated area, based on tsunami observation records in the wide areas from Hokkaido to Chiba prefectures. Tsunami heights of Fukushima Daiichi and Daini NPSs were recalculated as O.P. +13m and +9m respectively and tsunami peak height difference was attributed to the extent of superposition of tsunami waves of tsunami earthquake type of wave source in the area along interplane trench off the coast in the Fukushima prefecture and interplane earthquake type of wave source in rather deep interplate area off the coast in the Miyagi prefecture. (T. Tanaka)

Reviews of the Comprehensive Nuclear-Test-Ban Treaty and U.S. security

Science.gov (United States)

Jeanloz, Raymond

2017-11-01

Reviews of the Comprehensive Nuclear-Test-Ban Treaty (CTBT) by the National Academy of Sciences concluded that the United States has the technical expertise and physical means to i) maintain a safe, secure and reliable nuclear-weapons stockpile without nuclear-explosion testing, and ii) effectively monitor global compliance once the Treaty enters into force. Moreover, the CTBT is judged to help constrain proliferation of nuclear-weapons technology, so it is considered favorable to U.S. security. Review of developments since the studies were published, in 2002 and 2012, show that the study conclusions remain valid and that technical capabilities are better than anticipated.

Ground-water contamination at Wurtsmith Air Force Base, Michigan

Science.gov (United States)

Stark, J.R.; Cummings, T.R.; Twenter, F.R.

1983-01-01

A sand and gravel aquifer of glacial origin underlies Wurtsmith Air Force Base in northeastern lower Michigan. The aquifer overlies a thick clay layer at an average depth of 65 feet. The water table is about 10 feet below land surface in the western part of the Base and about 25 feet below land surface in the eastern part. A ground-water divide cuts diagonally across the Base from northwest to southeast. South of the divide, ground water flows to the Au Sable River; north of the divide, it flows to Van Etten Creek and Van Etten Lake. Mathematical models were used to aid in calculating rates of groundwater flow. Rates range from about 0.8 feet per day in the eastern part of the Base to about 0.3 feet per day in the western part. Models also were used as an aid in making decisions regarding purging of contaminated water from the aquifer. In 1977, trichloroethylene was detected in the Air Force Base water-supply system. It had leaked from a buried storage tank near Building 43 in the southeastern part of the Base and moved northeastward under the influence of the natural ground-water gradient and the pumping of Base water-supply wells. In the most highly contaminated part of the plume, concentrations are greater than 1,000 micrograms per liter. Current purge pumping is removing some of the trichloroethylene, and seems to have arrested its eastward movement. Pumping of additional purge wells could increase the rate of removal. Trichloroethylene has also been detected in ground water in the vicinity of the Base alert apron, where a plume from an unknown source extends northeastward off Base. A smaller, less well-defined area of contamination also occurs just north of the larger plume. Trichloroethylene, identified near the waste-treatment plant, seepage lagoons, and the northern landfill area, is related to activities and operations in these areas. Dichloroethylene and trichloroethylene occur in significant quantities westward of Building 43, upgradient from the major

Seismic fragility analysis of a CANDU containment structure for near-fault ground motions

International Nuclear Information System (INIS)

Choi, In Kil; Choun, Young Sun; Seo, Jeong Moon; Ahn, Seong Moon

2005-01-01

The R. G. 1.60 spectrum used for the seismic design of Korean nuclear power plants provides a generally conservative design basis due to its broadband nature. A survey on some of the Quaternary fault segments near Korean nuclear power plants is ongoing. It is likely that these faults will be identified as active ones. If the faults are confirmed as active ones, it will be necessary to reevaluate the seismic safety of the nuclear power plants located near these faults. The probability based scenario earthquakes were identified as near-field earthquakes. In general, the near-fault ground motion records exhibit a distinctive long period pulse like time history with very high peak velocities. These features are induced by the slip of the earthquake fault. Near-fault ground motions, which have caused much of the damage in recent major earthquakes, can be characterized by a pulse-like motion that exposes the structure to a high input energy at the beginning of the motion. It is necessary to estimate the near-fault ground motion effects on the nuclear power plant structures and components located near the faults. In this study, the seismic fragility analysis of a CANDU containment structure was performed based on the results of nonlinear dynamic time-history analyses

Enhanced-safety underground nuclear power plants based on the use of proven ship-building equipment and technology

International Nuclear Information System (INIS)

Pashin, V.M.; Petrov, E.L.; Khazov, B.S.

1995-01-01

Investigations performed in the last few years by the State Science Center of the Russian Federation - Academician A. N. Krylov Central Scientific-Research Institute, together with specialized enterprises of the Ministry of Atomic Energy of the Russian Federation, Sudprom, and other agencies of Russia, have shown the promise of marine nuclear power plants for producing underground nuclear power plants with a higher degree of protection from external and internal actions of different intensity. The concept was developed on the basis of an analysis of the energy supply in different regions of Russia and the near-abroad using fossil fuels (lignite, oil, natural gas). The change in the international environment, which makes it possible to convert the military technology, frees the industrial potential and skilled workers in Russia for development of products for the national economy. Stricter international standards and rules for increased safety and protection of nuclear power plants made it necessary to develop a new generation of reactors for ground-based power plants, which under the modern economic conditions cannot be implemented within the time periods acceptable for economics for most of the countries surrounding Russia. In the development of a new generation of ground-based nuclear power plants, the intense improvement of the aviation and space technology must be taken into account. This is connected with the increase in the catastrophes and the threat they present to the safety of unprotected power plants. This article is an abstract of the entire report

Grounded Theory as a "Family of Methods": A Genealogical Analysis to Guide Research

Science.gov (United States)

Babchuk, Wayne A.

2011-01-01

This study traces the evolution of grounded theory from a nuclear to an extended family of methods and considers the implications that decision-making based on informed choices throughout all phases of the research process has for realizing the potential of grounded theory for advancing adult education theory and practice. [This paper was…

IAEA Operational Safety Team Reviews Saint-Alban Nuclear Power Plant, France

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed safety practices at France's Saint-Alban Nuclear Power Plant (NPP) and has highlighted a set of strong practices as well as a series of recommendations to reinforce them. The IAEA assembled the team at the request of the Government of France to conduct an Operational Safety Review (OSART) of the Saint-Alban NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review from 20 September to 6 October 2010. The team was made up of experts from Belgium, Canada, the Czech Republic, Germany, Lithuania, the Netherlands, Slovakia, Sweden and the USA. An OSART mission is designed to review programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at Saint-Alban conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely are under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; and Emergency Planning and Preparedness. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: A safety guideline for outages; The use of remote video surveillance of fuel inspection and handling activities; A motivational tool for plant staff regarding the benefits of operating experience and associated corrective actions; and Use of a sophisticated key control system

IAEA Operational Safety Team Review Bohunice Nuclear Power Plant, Slovak Republic

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed Slovakia's Bohunice Nuclear Power Plant (BNPP) for its safety practices and has noted a series of good practices as well as recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of Slovak Republic to conduct an Operational Safety Review (OSART) of Bohunice NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 1 to 18 November 2010. The team was made up of experts from Belgium, Canada, China, the Czech Republic, France, Sweden, the United Kingdom and the IAEA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at BNPP conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely is under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry and Emergency Planning and Preparedness. Long Term Operation assessment has been requested by the plant in addition to the standard OSART program. The OSART team has identified good plant practices which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: BNPP has implemented a comprehensive set of technical and organizational measures which have significantly reduced the production of liquid radioactive waste; BNPP has developed an automatic transfer of dosimetry data

Random matrices and chaos in nuclear physics: Nuclear structure

International Nuclear Information System (INIS)

Weidenmueller, H. A.; Mitchell, G. E.

2009-01-01

Evidence for the applicability of random-matrix theory to nuclear spectra is reviewed. In analogy to systems with few degrees of freedom, one speaks of chaos (more accurately, quantum chaos) in nuclei whenever random-matrix predictions are fulfilled. An introduction into the basic concepts of random-matrix theory is followed by a survey over the extant experimental information on spectral fluctuations, including a discussion of the violation of a symmetry or invariance property. Chaos in nuclear models is discussed for the spherical shell model, for the deformed shell model, and for the interacting boson model. Evidence for chaos also comes from random-matrix ensembles patterned after the shell model such as the embedded two-body ensemble, the two-body random ensemble, and the constrained ensembles. All this evidence points to the fact that chaos is a generic property of nuclear spectra, except for the ground-state regions of strongly deformed nuclei.

Review of psychological consequences of nuclear accidents and empirical study on peoples reactions to radiation protection activities in an imagined situation

International Nuclear Information System (INIS)

Haukkala, A.; Eraenen, L.

1994-10-01

The report consist of two parts: a review of studies on psychological consequences of nuclear and radiation accidents in population and an empirical study of peoples reactions to protection actions in an event of hypothetical accident. Review is based on research results from two nuclear reactor accidents (Three Mile Island 1979, Chernobyl 1986) and a radiation accident in Goiania, Brazil 1987. (53 refs, 2 figs.,7 tabs.)

In Situ Production of Chlorine-36 in the Eastern Snake River Plain Aquifer, Idaho: Implications for Describing Ground-Water Contamination Near a Nuclear Facility

International Nuclear Information System (INIS)

Cecil, L. D.; Knobel, L. L.; Green, J. R.; Frape, S. K.

2000-01-01

The purpose of this report is to describe the calculated contribution to ground water of natural, in situ produced 36Cl in the eastern Snake River Plain aquifer and to compare these concentrations in ground water with measured concentrations near a nuclear facility in southeastern Idaho. The scope focused on isotopic and chemical analyses and associated 36Cl in situ production calculations on 25 whole-rock samples from 6 major water-bearing rock types present in the eastern Snake River Plain. The rock types investigated were basalt, rhyolite, limestone, dolomite, shale, and quartzite. Determining the contribution of in situ production to 36Cl inventories in ground water facilitated the identification of the source for this radionuclide in environmental samples. On the basis of calculations reported here, in situ production of 36Cl was determined to be insignificant compared to concentrations measured in ground water near buried and injected nuclear waste at the INEEL. Maximum estimated 36Cl concentrations in ground water from in situ production are on the same order of magnitude as natural concentrations in meteoric water

Quality verification at Arkansas Nuclear One using performance-based concepts

International Nuclear Information System (INIS)

Cooper, R.M.

1990-01-01

Performance-based auditing is beginning to make an impact within the nuclear industry. Its use provides performance assessments of the operating plant. In the past, this company along with most other nuclear utilities, performed compliance-based audits. These audits focused on paper reviews of past activities that were completed in weeks or months. This type of audit did not provide a comprehensive assessment of the effectiveness of an activity's performance, nor was it able to identify any performance problems that may have occurred. To respond to this discrepancy, a comprehensive overhaul of quality assurance (QA) assessment programs was developed. The first major change was to develop a technical specification (tech spec) audit program, with the objective of auditing each tech spec line item every 5 yr. To achieve performance-based results within the tech spec audit program, a tech spec surveillance program was implemented whose goal is to observe 75% of the tech-spec required tests every 5 yr. The next major change was to develop a QA surveillance program that would provide surveillance coverage for the remainder of the plant not covered by the tech spec surveillance program. One other improvement was to merge the QA/quality control (QC) functions into one nuclear quality group. The final part of the quality verification effort is trending of the quality performance-based data (including US Nuclear Regulatory Commission (NRC) violations)

Independent peer review of nuclear safety computer codes

International Nuclear Information System (INIS)

Boyack, B.E.; Jenks, R.P.

1993-01-01

A structured, independent computer code peer-review process has been developed to assist the US Nuclear Regulatory Commission (NRC) and the US Department of Energy in their nuclear safety missions. This paper describes a structured process of independent code peer review, benefits associated with a code-independent peer review, as well as the authors' recent peer-review experience. The NRC adheres to the principle that safety of plant design, construction, and operation are the responsibility of the licensee. Nevertheless, NRC staff must have the ability to independently assess plant designs and safety analyses submitted by license applicants. According to Ref. 1, open-quotes this requires that a sound understanding be obtained of the important physical phenomena that may occur during transients in operating power plants.close quotes The NRC concluded that computer codes are the principal products to open-quotes understand and predict plant response to deviations from normal operating conditionsclose quotes and has developed several codes for that purpose. However, codes cannot be used blindly; they must be assessed and found adequate for the purposes they are intended. A key part of the qualification process can be accomplished through code peer reviews; this approach has been adopted by the NRC

Seismic Hazards in Site Evaluation for Nuclear Installations. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-08-15

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear installations. It supplements the Safety Requirements publication on Site Evaluation for Nuclear Installations. The present publication provides guidance and recommends procedures for the evaluation of seismic hazards for nuclear power plants and other nuclear installations. It supersedes Evaluation of Seismic Hazards for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.3 (2002). In this publication, the following was taken into account: the need for seismic hazard curves and ground motion spectra for the probabilistic safety assessment of external events for new and existing nuclear installations; feedback of information from IAEA reviews of seismic safety studies for nuclear installations performed over the previous decade; collective knowledge gained from recent significant earthquakes; and new approaches in methods of analysis, particularly in the areas of probabilistic seismic hazard analysis and strong motion simulation. In the evaluation of a site for a nuclear installation, engineering solutions will generally be available to mitigate, by means of certain design features, the potential vibratory effects of earthquakes. However, such solutions cannot always be demonstrated to be adequate for mitigating the effects of phenomena of significant permanent ground displacement such as surface faulting, subsidence, ground collapse or fault creep. The objective of this Safety Guide is to provide recommendations and guidance on evaluating seismic hazards at a nuclear installation site and, in particular, on how to determine: (a) the vibratory ground motion hazards, in order to establish the design basis ground motions and other relevant parameters for both new and existing nuclear installations; and (b) the potential for fault displacement and the rate of fault displacement that could affect the feasibility of the site or the safe operation of the installation at

IAEA Mission Concludes Peer Review of Jordan's Nuclear Regulatory Framework

International Nuclear Information System (INIS)

2014-01-01

Senior international nuclear safety and radiation protection experts today concluded an 11-day International Atomic Energy Agency (IAEA) Integrated Regulatory Review Service (IRRS) mission to review the regulatory framework for nuclear and radiation safety in Jordan. The mission team said in its preliminary findings that Jordan's nuclear regulator, the Energy and Minerals Regulatory Commission (EMRC), faces challenges because it is a relatively new body that handles a high workload while also working to recruit, train and keep competent staff. The team also noted that a recent merger provided the regulator with more of the resources it needs to perform its duty. The team made recommendations and suggestions to the regulatory body and the Government to help them strengthen the effectiveness of Jordan's regulatory framework and functions in line with IAEA Safety Standards. The main observations of the IRRS Review team comprised the following: The regulatory body, founded in 2007 and merged with other regulators in April 2014 to form EMRC, faces large challenges in terms of its regulatory workload, management system building and staff recruitment and training; The new EMRC structure and revision of the radiation and nuclear safety law represents an important opportunity to strengthen Jordan's radiation and nuclear safety infrastructure; The Government has shown commitment to radiation and nuclear safety through measures including becoming party to international conventions. It could further demonstrate its commitment by adopting a formal national policy and strategy for safety that defines the role of the Minister of Energy in relation to EMRC and protects the independence of regulatory decision-making

Clinical TVA-based studies: a general review

Directory of Open Access Journals (Sweden)

Thomas eHabekost

2015-03-01

Full Text Available In combination with whole report and partial report tasks, the Theory of Visual Attention (TVA can be used to estimate individual differences in five basic attentional parameters: The visual processing speed, the storage capacity of visual short-term memory, the perceptual threshold, the efficiency of top-down selectivity, and the spatial bias of attentional weighting. TVA-based assessment has been used in about 30 studies to investigate attentional deficits in a range of neurological and psychiatric conditions: (a neglect and simultanagnosia, (b reading disturbances, (c aging and neurodegenerative diseases, and most recently (d neurodevelopmental disorders. The article introduces TVA based assessment, discusses its methodology and psychometric properties, and reviews the progress made in each of the four research fields. The empirical results demonstrate the general usefulness of TVA-based assessment for many types of clinical neuropsychological research. The method’s most important qualities are cognitive specificity and theoretical grounding, but it is also characterized by good reliability and sensitivity to minor deficits. The review concludes by pointing to promising new areas for clinical TVA-based research.

Nuclear reactions video (knowledge base on low energy nuclear physics)

International Nuclear Information System (INIS)

Zagrebaev, V.; Kozhin, A.

1999-01-01

The NRV (nuclear reactions video) is an open and permanently extended global system of management and graphical representation of nuclear data and video-graphic computer simulation of low energy nuclear dynamics. It consists of a complete and renewed nuclear database and well known theoretical models of low energy nuclear reactions altogether forming the 'low energy nuclear knowledge base'. The NRV solves two main problems: 1) fast and visualized obtaining and processing experimental data on nuclear structure and nuclear reactions; 2) possibility for any inexperienced user to analyze experimental data within reliable commonly used models of nuclear dynamics. The system is based on the realization of the following principal things: the net and code compatibility with the main existing nuclear databases; maximal simplicity in handling: extended menu, friendly graphical interface, hypertext description of the models, and so on; maximal visualization of input data, dynamics of studied processes and final results by means of real three-dimensional images, plots, tables and formulas and a three-dimensional animation. All the codes are composed as the real Windows applications and work under Windows 95/NT

Russian MINATOM nuclear safety research strategic plan. An international review

International Nuclear Information System (INIS)

1999-03-01

The 'Safety Research Strategic Plan for Russian Nuclear Power Plants' was published in draft form at the Russian International Nuclear Safety Centre (RINSC) by a working group of fifteen senior Russian experts. The Plan consists of 12 chapters, each addressing a specific technical area and containing a number of proposed research programmes and projects to advance the state-of-knowledge in that area. In part because a strong Recommendation to undertake such a Plan was made by the 1998 OECD/NEA study, the OECD Nuclear Energy Agency was asked by the Director of RINSC and the Director of USINSC to organize an international review of the Plan when the English-language version became available in October, 1998. This report represents the results of that review. (R.P.)

Fundamental bases to implementation the specific national norm for nuclear gauges; Bases fundamentais para a implantação de norma nacional específica para medidores nucleares

Energy Technology Data Exchange (ETDEWEB)

Ferreira, L.C.; Silva, E.R.; Ferreira, R.; Peixoto, J.G.P., E-mail: luizxiii@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2017-07-01

The aims of this work is to provide grounds for creation a national standard practice security and responsibility in the use of nuclear gauges in accordance with the national recommendation already exist, following the basic security principles, responsibilities of these involved in the acquisition, operation, storage, maintenance and post-emergency on use of nuclear gauges. (author)

Response analysis of a nuclear containment structure with nonlinear soil-structure interaction under bi-directional ground motion

Science.gov (United States)

Kumar, Santosh; Raychowdhury, Prishati; Gundlapalli, Prabhakar

2015-06-01

Design of critical facilities such as nuclear power plant requires an accurate and precise evaluation of seismic demands, as any failure of these facilities poses immense threat to the community. Design complexity of these structures reinforces the necessity of a robust 3D modeling and analysis of the structure and the soil-foundation interface. Moreover, it is important to consider the multiple components of ground motion during time history analysis for a realistic simulation. Present study is focused on investigating the seismic response of a nuclear containment structure considering nonlinear Winkler-based approach to model the soil-foundation interface using a distributed array of inelastic springs, dashpots and gap elements. It is observed from this study that the natural period of the structure increases about 10 %, whereas the force demands decreases up to 24 % by considering the soil-structure interaction. Further, it is observed that foundation deformations, such as rotation and sliding are affected by the embedment ratio, indicating an increase of up to 56 % in these responses for a reduction of embedment from 0.5 to 0.05× the width of the footing.

IAEA Expert Team Completes Mission to Review Japan's Nuclear Power Plant Safety Assessment Process, 31 January 2012, Tokyo, Japan

International Nuclear Information System (INIS)

2012-01-01

Full text: A team of international nuclear safety experts today completed a review of Japan's two-stage process for assessing nuclear safety at the nation's nuclear power plants. The team began its work on 23 January and delivered a Preliminary Summary Report to Japanese officials today and plans to finish the final report by the end of February. National safety assessments and their peer review by the IAEA are a key component of the IAEA's Action Plan on Nuclear Safety, which was approved by the Agency's 152 Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. At the request of the Government of Japan, the International Atomic Energy Agency (IAEA) organized a 10-person team to review the Japanese Nuclear and Industrial Safety Agency's (NISA) approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. The IAEA safety review mission consisted of five IAEA and three international nuclear safety experts. To help its review, the team held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety (JNES) Organization, and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. 'We concluded that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, director of the IAEA's Nuclear Installation Safety Division. In its Preliminary Summary Report delivered today, the team highlighted a number of good practices and identified some improvements that would enhance the overall effectiveness of the Comprehensive Safety Assessment process. Good practices identified by the mission team include: Based on NISA instructions and commitments of the

Physical bases of nuclear medicine

International Nuclear Information System (INIS)

Isabelle, D.B.; Ducassou, D.

1975-01-01

The physical bases of nuclear medicine are outlined in several chapters devoted successively to: atomic and nuclear structures; nuclear reactions; radioactiity laws; a study of different types of disintegration; the interactions of radiations with matter [fr

Actinide separation chemistry in nuclear waste streams, an OECD Nuclear Energy Agency review

International Nuclear Information System (INIS)

Madic, C.

1997-01-01

The separation of actinide elements from various waste materials, either produced in nuclear fuel cycle or in the past during nuclear weapon production, represent a significant issue facing developed countries. Improvements in the efficiencies of the separation processes can be expected from a better knowledge of the chemistry of these elements in these complex matrices. The Nuclear Science Committee of the OECD/NEA has established a task force of experts in actinide chemistry to review the current and developing separation techniques and chemical processes. Recommendations were made for future research and development programs. This article presents briefly the work of the Task Force which will be published soon as an OECD/NEA/NSC Report. (author)

Correlation of horizontal and vertical components of strong ground motion for response-history analysis of safety-related nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Huang, Yin-Nan, E-mail: ynhuang@ntu.edu.tw [Dept. of Civil Engineering, National Taiwan University, No. 1, Sec. 4, Roosevelt Rd., Taipei 10617, Taiwan (China); Yen, Wen-Yi, E-mail: b01501059@ntu.edu.tw [Dept. of Civil Engineering, National Taiwan University, No. 1, Sec. 4, Roosevelt Rd., Taipei 10617, Taiwan (China); Whittaker, Andrew S., E-mail: awhittak@buffalo.edu [Dept. of Civil, Structural and Environmental Engineering, MCEER, State University of New York at Buffalo, Buffalo, NY 14260 (United States)

2016-12-15

Highlights: • The correlation of components of ground motion is studied using 1689 sets of records. • The data support an upper bound of 0.3 on the correlation coefficient. • The data support the related requirement in the upcoming edition of ASCE Standard 4. - Abstract: Design standards for safety-related nuclear facilities such as ASCE Standard 4-98 and ASCE Standard 43-05 require the correlation coefficient for two orthogonal components of ground motions for response-history analysis to be less than 0.3. The technical basis of this requirement was developed by Hadjian three decades ago using 50 pairs of recorded ground motions that were available at that time. In this study, correlation coefficients for (1) two horizontal components, and (2) the vertical component and one horizontal component, of a set of ground motions are computed using records from a ground-motion database compiled recently for large-magnitude shallow crustal earthquakes. The impact of the orientation of the orthogonal horizontal components on the correlation coefficient of ground motions is discussed. The rules in the forthcoming edition of ASCE Standard 4 for the correlation of components in a set of ground motions are shown to be reasonable.

Review of the ISTC innovative nuclear programs (information review)

Energy Technology Data Exchange (ETDEWEB)

Tocheny, L. V. [ISTC - International Science and Technology Center, Moscow (Russian Federation)

2006-07-01

The information will be included in the review, with special attention on details of corresponding experimental programs: Novel reactor concepts, fit with GIF and INPRO: Supercritical Pressure Water aspects, Heavy metals (Lead, Lead-Bismuth) technology, HTGR critical modeling, engineering. Molten salts. Reactor data benchmarking, Accelerator Driven Systems (experimental modelling), Nuclear data measurements, Severe accident study (corium modelling, QUENCH, Chernobyl), Experimental Analysis of Hydraulically Induced Vibrations in Compact Curling Tube Steam Generators. (authors)

Calibration of Ground -based Lidar instrument

DEFF Research Database (Denmark)

Villanueva, Héctor; Yordanova, Ginka

This report presents the result of the lidar calibration performed for the given Ground-based Lidar at DTU’s test site for large wind turbines at Høvsøre, Denmark. Calibration is here understood as the establishment of a relation between the reference wind speed measurements with measurement...

Discussion of management review in nuclear power plants

International Nuclear Information System (INIS)

Duan Hongwei; Li Juan; Wang Jing; Zhang Hui; Wang Yanqi; Tian Feng

2015-01-01

According to the nuclear safety regulations and guidelines in China, the information of the IAEA and the NRC, this paper discusses the origin, purpose, method and report of the management review, the basic concepts and requirements. In order to identify the difference between the management review and the internal quality assurance audit, the paper also compares their purpose, nature, the pursuant documents, and etc. (authors)

Review of recent experiments in intermediate energy nuclear physics

Energy Technology Data Exchange (ETDEWEB)

Barnes, P D [Carnegie-Mellon Univ., Pittsburgh, PA (USA)

1978-01-01

The data generated at intermediate-energy accelerator facilities has expanded rapidly over the past few years. A number of recent experiments chosen for their impact on nuclear structure questions are reviewed. Proton scattering together with pionic and muonic atom X-ray measurements are shown to be giving very precise determinations of gross nuclear properties. Pion scattering and reaction data although less precise, are starting to generate a new understanding of wave functions of specific nuclear states. Specific examples where new unpublished data are now available are emphasized. In addition, other medium-energy experiments that are starting to contribute to nuclear structure physics are summarized.

The settlement of foundation of existing large structure on soft ground and investigation of its allowable settlement

International Nuclear Information System (INIS)

Okamoto, Toshiro

1987-01-01

In our laboratory a study of siting on quarternary ground is followed to make possible to construct a nuclear power plant on soil ground in Japan, a important subject is to understand bearing capacity, settlement and seismic responce of foundation. So measured data are collected about relation between ground and type of foundation, total settlement and differential settlement of already constructed large structures, and it is done to investigate the real condition and to examine allowable settlement. Investigated structures are mainly foreign nuclear power plant and domestic and foreign high buildings. The higher buildings are, the more raft foundation are for type of foundation and the higher contact pressure are to similar to a nuclear power plant. So discussion is done about mainly raft foundation. It is found that some measured maximum total settlements are larger than already proposed allowable values. So empirical allowable settlement is derived from measured values considering the effect of the width of base slab, contact pressure and foundation ground. Differential settlement is investigated about relation to maximum total settlement, and is formulated considering the width and the rigidity of base slab. Beside the limit of differential settlement is obtained as foundation is damaged, and the limit of maximum total settlement is obtained by combining this and above mentioned relation. Obtained allowable value is largely influenced by the width of base slab, and becomes less severe than some already proposed values. So it is expected that deformation of foundation is rationaly investigated when large structure as nuclear power plant is constructed on soft ground. (author)

Transitions in midwestern ground water law

International Nuclear Information System (INIS)

Bowman, J.A.; Clark, G.R.

1989-01-01

The evolution of ground-water law in eight states in the Midwest (Illinois, Indiana, Iowa, Michigan, Minnesota, Missouri, Ohio, and Wisconsin) is examined, and a review of transitions in ground-water doctrines is presented. Two underlying themes in changing ground-water management are communicated. First, ground-water law is evolving from private property rules of capture based on the absolute ownership doctrines to rules requiring conservation and sharing of ground water as a public resource. Second, in both courts and state legislatures, a proactive role of ground-water management is emerging, again, with an emphasis on sharing. Both of these trends are apparent in the Midwest. In the last decade midwestern states have (1) seen significant shifts in court decisions on ground-water use with greater recognition of the reciprocal or mutually dependent nature of ground-water rights, and (2) seen increased legislative development of comprehensive ground-water management statutes that emphasize the reciprocal liabilities of ground-water use. These trends are examined and ground-water management programs discussed for eight states in the Midwest

Settlement mechanism of the backfilled ground around nuclear power plant buildings. Part 1. A series of 1G shaking table tests

International Nuclear Information System (INIS)

Ishimaru, Makoto; Kawai, Tadashi

2008-01-01

The large ground settlement locally occurred at the backfilled ground around the Kashiwazaki-Kariwa Nuclear Power Plant buildings during the Niigataken Chuetsu-oki Earthquake in 2007. The purposes of this study are to verify the assumed mechanism of the settlement and to discuss the influence factors on the settlement. For these purposes, we conducted a series of 1G shaking table tests using a rigid structure and sand. In the tests, parameters, which were variously changed, are related to two factors; one is the horizontal ground displacement relative to the structure, the other is the ground strength against the sliding failure. The following results were obtained: (1) All the results showed that the ground settlement sizes near the structure were larger than the ground settlement sizes far from the structure, (2) From the video observed at the ground near the structure, it was found that the settlement locally occurred due to the sliding failure after the ground was separated from the structure, (3) The ground settlement sizes near the structure were large as the horizontal ground displacement sizes were large, and the soil strength arising from fines affected the ground settlement sizes near the structure. (author)

Nuclear Magnetic Resonance: new applications in the quantification and assessment of polysaccharide-based vaccine intermediates

International Nuclear Information System (INIS)

Garrido, Raine; Velez, Herman; Verez, Vicente

2013-01-01

Nuclear Magnetic Resonance has become the choice for structural studies, identity assays and simultaneous quantification of active pharmaceutical ingredient of different polysaccharide-based vaccine. In the last two decades, the application of quantitative Nuclear Magnetic Resonance had an increasing impact to support several quantification necessities. The technique involves experiments with several modified parameters in order to obtain spectra with quantifiable signals. The present review is supported by some recent relevant reports and it discusses several applications of NMR in carbohydrate-based vaccines. Moreover, it emphasizes and describes several parameters and applications of quantitative Nuclear Magnetic Resonance

Safety Experts Complete IAEA Nuclear Regulatory Review of the United States

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of senior nuclear safety experts today completed a two-week International Atomic Energy Agency (IAEA) review of the governmental and regulatory framework for nuclear safety in the United States. The team identified good practices within the U.S. system and offered suggestions for ways the U.S. Nuclear Regulatory Commission (NRC) could improve. The IAEA has conveyed the team's main conclusions to the NRC, and a final report will be submitted to the NRC in about two months. At the request of the United States, the IAEA assembled a team of 19 international experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This mission was a peer review based on the IAEA Safety Standards. It was not an inspection, nor an audit. The experts came from 14 different countries: Canada, China, the Czech Republic, Finland, France, Italy, Japan, Mexico, the Republic of Korea, Slovenia, Spain, Sweden, Switzerland, and the United Kingdom. Team leader Jukka Laaksonen of Finland said: ''We found a comprehensive, consistent, and mature regulatory system run by the NRC, which has a strong drive for continuous improvement.' The scope of the mission included the U.S. regulatory framework and the regulation of the nuclear plant operation. The mission was conducted from 18 to 29 October, mainly at NRC headquarters outside of Washington, D.C. To study U.S. regulatory activities, the mission conducted a series of interviews and discussions with NRC staff and other organizations to help assess the effectiveness of the regulatory system. In addition, the team observed regulatory activities at two operating nuclear power reactors and an emergency preparedness exercise. The IAEA's IRRS coordinator Gustavo Caruso said, ''This mission represents a milestone for the IRRS program because the U.S. regulatory system is the largest in the world and many nations look to it. The IRRS is a useful tool that allows host nations to gain guidance from experienced

Accommodating ground water velocity uncertainties in the advection-dispersion approach to geologic nuclear waste migration

International Nuclear Information System (INIS)

Thomas, G.F.

1994-01-01

This note shows how uncertainties in nearfield and farfield ground water velocities affect the inventory that migrates from a geologic nuclear waste repository within the classical advection-dispersion approach and manifest themselves through both the finite variances and covariances in the activities of transported nuclides and in the apparent scale dependence of the host rock's dispersivity. Included is a demonstration of these effects for an actinide chain released from used CANDU fuel buried in a hypothetical repository. (Author)

Nuclear thermal rocket workshop reference system Rover/NERVA

International Nuclear Information System (INIS)

Borowski, S.K.

1991-01-01

The Rover/NERVA engine system is to be used as a reference, against which each of the other concepts presented in the workshop will be compared. The following topics are reviewed: the operational characteristics of the nuclear thermal rocket (NTR); the accomplishments of the Rover/NERVA programs; and performance characteristics of the NERVA-type systems for both Mars and lunar mission applications. Also, the issues of ground testing, NTR safety, NASA's nuclear propulsion project plans, and NTR development cost estimates are briefly discussed

Gravitational-Wave Tests of General Relativity with Ground-Based Detectors and Pulsar-Timing Arrays

Directory of Open Access Journals (Sweden)

Nicolás Yunes

2013-11-01

Full Text Available This review is focused on tests of Einstein's theory of general relativity with gravitational waves that are detectable by ground-based interferometers and pulsar-timing experiments. Einstein’s theory has been greatly constrained in the quasi-linear, quasi-stationary regime, where gravity is weak and velocities are small. Gravitational waves will allow us to probe a complimentary, yet previously unexplored regime: the non-linear and dynamical strong-field regime. Such a regime is, for example, applicable to compact binaries coalescing, where characteristic velocities can reach fifty percent the speed of light and gravitational fields are large and dynamical. This review begins with the theoretical basis and the predicted gravitational-wave observables of modified gravity theories. The review continues with a brief description of the detectors, including both gravitational-wave interferometers and pulsar-timing arrays, leading to a discussion of the data analysis formalism that is applicable for such tests. The review ends with a discussion of gravitational-wave tests for compact binary systems.

Gravitational-Wave Tests of General Relativity with Ground-Based Detectors and Pulsar-Timing Arrays.

Science.gov (United States)

Yunes, Nicolás; Siemens, Xavier

2013-01-01

This review is focused on tests of Einstein's theory of general relativity with gravitational waves that are detectable by ground-based interferometers and pulsar-timing experiments. Einstein's theory has been greatly constrained in the quasi-linear, quasi-stationary regime, where gravity is weak and velocities are small. Gravitational waves will allow us to probe a complimentary, yet previously unexplored regime: the non-linear and dynamical strong-field regime . Such a regime is, for example, applicable to compact binaries coalescing, where characteristic velocities can reach fifty percent the speed of light and gravitational fields are large and dynamical. This review begins with the theoretical basis and the predicted gravitational-wave observables of modified gravity theories. The review continues with a brief description of the detectors, including both gravitational-wave interferometers and pulsar-timing arrays, leading to a discussion of the data analysis formalism that is applicable for such tests. The review ends with a discussion of gravitational-wave tests for compact binary systems.

Nuclear safety and radiation protection report of EdF's Tricastin operational hot base nuclear facilities (BCOT) - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

IAEA Issues Report on Mission to Review Japan's Nuclear Power Plant Safety Assessment Process

International Nuclear Information System (INIS)

2012-01-01

Full text: A team of international nuclear safety experts has delivered its report on a mission it conducted from 21-31 January 2012 to review Japan's process for assessing nuclear safety at the nation's nuclear power plants. International Atomic Energy Agency (IAEA) officials delivered the IAEA Mission Report to Japanese officials yesterday and made it publicly available today. Following the 11 March 2011 accident at TEPCO's Fukushima Daiichi Nuclear Power Station, Japan's Nuclear and Industrial Safety Agency (NISA) announced the development of a revised safety assessment process for the nation's nuclear power reactors. At the request of the Government of Japan, the IAEA organized a team of five IAEA and three international nuclear safety experts and visited Japan to review NISA's approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. A Preliminary Summary Report was issued on 31 January. 'The mission report provides additional information regarding the team's recommendations and overall finding that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, Director of the IAEA's Nuclear Installation Safety Division. National safety assessments and their peer review by the IAEA are a key component of the IAEA Action Plan on Nuclear Safety, which was approved by the Agency's Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. The IAEA safety review mission held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety Organization (JNES), and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. In its report delivered today

Structural Health Monitoring of Piping in Nuclear Power Plants - A Review of Efficiency of Existing Methods

International Nuclear Information System (INIS)

Stepinski, Tadeusz

2011-05-01

In the first part of the report, we review various efforts that have been recently performed in the USA in the field of reactor health monitoring. They were carried out by different organizations and they addressed different issues related to the safety of nuclear reactors. Among other aspects, we present technical issues related to the design of a self-diagnostic monitoring system for the next generation of nuclear reactors. We also give a brief review of the international experience of such systems in today's reactors. In the second part of the report we focus on long range ultrasonic techniques that can be used for monitoring piping in nuclear reactors. Common strategy used in the Swedish nuclear plants is leak before break (LBB), which relies on monitoring leaks from the pipelines as indications of possible pipe break. Significant parts of piping systems are partly or entirely inaccessible for the NDE inspectors, which complicates the use of proactive strategies. One solution to the problem could be implementing monitoring systems capable of monitoring pipelines over a long range. The method, which has shown much promise in such applications is the UT based on guided waves (GW) referred to as long range ultrasound testing (LRUT). In the report we give a brief review of the GW theory followed by the presentation the commercial GW instruments and transducers designed for the LRUT of piping. We also present examples of the baseline based systems using permanently installed transducers. In the final part we report capacity tests of the LRUT instruments performed in collaboration with two different manufactures

Nuclear Technology Review 2009

International Nuclear Information System (INIS)

2009-08-01

The year 2008 was paradoxical for nuclear power. Projections of future growth were revised upwards, but no new reactors were connected to the grid. It was the first year since 1955 without at least one new reactor coming on-line. There were, however, ten construction starts, the most since 1985. At least until the global financial crisis, cost estimates reported for new nuclear reactors were often higher than those in previous years, particularly in regions with less recent experience in new construction. However, growth targets for nuclear power were raised in the Russian Federation, and similar considerations were under review in China. India negotiated a safeguards agreement with the Agency in August, and the Nuclear Suppliers Group subsequently exempted India from previous restrictions on nuclear trade, which should allow India to accelerate its planned expansion of nuclear power. In the USA, the Nuclear Regulatory Commission (NRC) received combined licence (COL) applications for 26 new reactors. The US Department of Energy (USDOE) received 19 'Part I applications' for Federal loan guarantees to build 21 new reactors. Nonetheless, current expansion, as well as near term and long term growth prospects, remain centred in Asia. Of the ten construction starts in 2008, eight were in Asia. Twenty-eight of the 44 reactors under construction at the end of the year were in Asia, as were 28 of the last 39 new reactors to have been connected to the grid. Armenia joined the Russian Federation and Kazakhstan as members of the International Uranium Enrichment Centre in Angarsk, Siberia. The Ukrainian Government announced that Ukraine would also join. AREVA and USEC applied to the USDOE for loan guarantees for the construction of AREVA's proposed Eagle Rock Enrichment Facility and USEC's American Centrifuge Plant. Construction of an underground repository for low and medium level radioactive waste began at the former Konrad iron mine in Germany. The USDOE submitted a formal

Nuclear Technology Review 2009

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-08-15

The year 2008 was paradoxical for nuclear power. Projections of future growth were revised upwards, but no new reactors were connected to the grid. It was the first year since 1955 without at least one new reactor coming on-line. There were, however, ten construction starts, the most since 1985. At least until the global financial crisis, cost estimates reported for new nuclear reactors were often higher than those in previous years, particularly in regions with less recent experience in new construction. However, growth targets for nuclear power were raised in the Russian Federation, and similar considerations were under review in China. India negotiated a safeguards agreement with the Agency in August, and the Nuclear Suppliers Group subsequently exempted India from previous restrictions on nuclear trade, which should allow India to accelerate its planned expansion of nuclear power. In the USA, the Nuclear Regulatory Commission (NRC) received combined licence (COL) applications for 26 new reactors. The US Department of Energy (USDOE) received 19 'Part I applications' for Federal loan guarantees to build 21 new reactors. Nonetheless, current expansion, as well as near term and long term growth prospects, remain centred in Asia. Of the ten construction starts in 2008, eight were in Asia. Twenty-eight of the 44 reactors under construction at the end of the year were in Asia, as were 28 of the last 39 new reactors to have been connected to the grid. Armenia joined the Russian Federation and Kazakhstan as members of the International Uranium Enrichment Centre in Angarsk, Siberia. The Ukrainian Government announced that Ukraine would also join. AREVA and USEC applied to the USDOE for loan guarantees for the construction of AREVA's proposed Eagle Rock Enrichment Facility and USEC's American Centrifuge Plant. Construction of an underground repository for low and medium level radioactive waste began at the former Konrad iron mine in Germany. The USDOE submitted a formal

Hydrogen energy based on nuclear energy

International Nuclear Information System (INIS)

2002-06-01

A concept to produce hydrogen of an energy carrier using nuclear energy was proposed since 1970s, and a number of process based on thermochemical method has been investigated after petroleum shock. As this method is used high temperature based on nuclear reactors, these researches are mainly carried out as a part of application of high temperature reactors, which has been carried out at an aim of the high temperature reactor application in the Japan Atomic Energy Research Institute. On October, 2000, the 'First International Conference for Information Exchange on Hydrogen Production based on Nuclear Energy' was held by auspice of OECD/NEA, where hydrogen energy at energy view in the 21st Century, technology on hydrogen production using nuclear energy, and so on, were published. This commentary was summarized surveys and researches on hydrogen production using nuclear energy carried out by the Nuclear Hydrogen Research Group established on January, 2001 for one year. They contains, views on energy and hydrogen/nuclear energy, hydrogen production using nuclear energy and already finished researches, methods of hydrogen production using nuclear energy and their present conditions, concepts on production plants of nuclear hydrogen, resources on nuclear hydrogen production and effect on global environment, requests from market and acceptability of society, and its future process. (G.K.)

Review of Investigations on Site Selection for Nuclear Power Plants in Croatia

Energy Technology Data Exchange (ETDEWEB)

Malbasa, N [Ekonerg, Zagreb (Croatia)

2008-07-01

A review of site investigation for nuclear facilities in the Republic of Croatia that had been performed from 1964, when investigation started for the first nuclear power plant, to 1994 when the activities were stopped, is presented therein. Brief results of the main investigation were presented including the Tanja site on the Danube upstream of Vukovar. It is the best of all the investigated locations for nuclear power plant in Croatia. The review of results for site selection of low and intermediate level of radioactive waste disposal is also given. The position of nuclear power plants in the strategic documents of the Republic of Croatia was analysed. It is concluded that the status of nuclear facilities in the main strategic documents must be improved because the energy future in Croatia - as almost in all European countries - could hardly be successful without any further development of nuclear energy.(author)

Review of Investigations on Site Selection for Nuclear Power Plants in Croatia

International Nuclear Information System (INIS)

Malbasa, N.

2008-01-01

A review of site investigation for nuclear facilities in the Republic of Croatia that had been performed from 1964, when investigation started for the first nuclear power plant, to 1994 when the activities were stopped, is presented therein. Brief results of the main investigation were presented including the Tanja site on the Danube upstream of Vukovar. It is the best of all the investigated locations for nuclear power plant in Croatia. The review of results for site selection of low and intermediate level of radioactive waste disposal is also given. The position of nuclear power plants in the strategic documents of the Republic of Croatia was analysed. It is concluded that the status of nuclear facilities in the main strategic documents must be improved because the energy future in Croatia - as almost in all European countries - could hardly be successful without any further development of nuclear energy.(author)

Nuclear safety policy working group recommendations on nuclear propulsion safety for the space exploration initiative

Science.gov (United States)

Marshall, Albert C.; Lee, James H.; Mcculloch, William H.; Sawyer, J. Charles, Jr.; Bari, Robert A.; Cullingford, Hatice S.; Hardy, Alva C.; Niederauer, George F.; Remp, Kerry; Rice, John W.

1993-01-01

An interagency Nuclear Safety Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program. These recommendations, which are contained in this report, should facilitate the implementation of mission planning and conceptual design studies. The NSPWG has recommended a top-level policy to provide the guiding principles for the development and implementation of the SEI nuclear propulsion safety program. In addition, the NSPWG has reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. These recommendations should be useful for the development of the program's top-level requirements for safety functions (referred to as Safety Functional Requirements). The safety requirements and guidelines address the following topics: reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations.

Application and development of peer review in China's nuclear power industry

International Nuclear Information System (INIS)

Huang Ping

2014-01-01

Peer review is one of the scientific methods and tools in management, which plays an active role in promoting and improving the performance of safe operation and management level of nuclear power plants. Peer review of nuclear power is not only comprehensively popularized and applied in China, but it is also innovated and developed in industry at all levels in recent years. In this paper, with the CNNC's relevant practice as main line, a variety of accepted peer review methods both at home and abroad were compared and analyzed, and the current application and development of peer review in China's nuclear power industry were described, as well as some suggestions for improvement were put forward to share with our craft brothers. (author)

Nuclear safety aspects of exported replicate nuclear power plants and associated problems

International Nuclear Information System (INIS)

Kern, H.G.

1978-01-01

The standardization of the export nuclear power plant is being pursued with the concept of replication. This concept entails using another exported Nuclear Power Plant (NPP) as the base design and adapting it to a new site. The general ground rule applied to this concept is upgrading the design where necessary and duplicating the design where it is superior. Such continuous improvement will result in a standard export NPP that incorporates design features which will make it essentially acceptable for any suitable site. The advantages of replication are, therefore, boundless. However, the replication mode requires superior design control by the engineer to assure that only improvements alter the base design. With this concept, the replicating engineer is essentially assigned the responsiblity of safeguarding the standard export plant design. He is delegated the task of filtering the design such that only the conservative aspects prevail. Tight control of design changes via properly administered procedures is necessary to assure that no unforeseen compromises are made in designs which have already achieved optimization. Techniques to accomplish successful replication include, among others, the use of PCNs, system cognizant engineers, design verfication review, and the participation of all engineering disciplines in the development of the project schedule. (author)

International Nuclear and Radiation Safety Experts Conclude IAEA Peer Review of Slovenia's Regulatory System

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of senior nuclear safety experts today concluded a 10-day mission to review the regulatory framework for nuclear and radiation safety in Slovenia. The team identified good practices and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of Slovenia and a final report will be submitted by the end of 2011. At the request of the Slovenian Government, the IAEA assembled a team of 10 senior regulatory experts from nine nations to conduct the Integrated Regulatory Review Service (IRRS) mission involving the Slovenian Nuclear Safety Administration (SNSA). The mission is a peer review based on the IAEA Safety Standards. Andrej Stritar, Director of Slovenian Nuclear Safety Administration, stressed ''how important it is for a small country like Slovenia to tightly follow international standards in the area of nuclear safety.'' He also expressed his gratitude to the IAEA, and the countries from which team members came, for their support and for their intensive work during the last ten days. Mission Team Leader Colin Patchett, Deputy Chief Inspector from the UK's Office for Nuclear Regulation commended ''the Slovenian authorities for their commitment to nuclear and radiation safety regulation and for sharing their experience.'' The IRRS team reviewed Slovenia's current regulatory framework and all SNSA-regulated facilities and activities, as well as the regulatory implications of the TEPCO Fukushima Daiichi accident. The IRRS team identified particular strengths in the Slovenian regulatory system, including: Through its legal framework, the Slovenian government has appointed SNSA to regulate its nuclear safety program and SNSA has in place an effective process for carrying out this responsibility; and Slovenia's response to the accident at the TEPCO Fukushima Daiichi power plant has been prompt and effective. Communications with the public, development of actions for improvement

Overview of Boundary Layer Clouds Using Satellite and Ground-Based Measurements

Science.gov (United States)

Xi, B.; Dong, X.; Wu, P.; Qiu, S.

2017-12-01

A comprehensive summary of boundary layer clouds properties based on our few recently studies will be presented. The analyses include the global cloud fractions and cloud macro/micro- physical properties based on satellite measurements using both CERES-MODIS and CloudSat/Caliposo data products,; the annual/seasonal/diurnal variations of stratocumulus clouds over different climate regions (mid-latitude land, mid-latitude ocean, and Arctic region) using DOE ARM ground-based measurements over Southern great plain (SGP), Azores (GRW), and North slope of Alaska (NSA) sites; the impact of environmental conditions to the formation and dissipation process of marine boundary layer clouds over Azores site; characterizing Arctice mixed-phase cloud structure and favorable environmental conditions for the formation/maintainess of mixed-phase clouds over NSA site. Though the presentation has widely spread topics, we will focus on the representation of the ground-based measurements over different climate regions; evaluation of satellite retrieved cloud properties using these ground-based measurements, and understanding the uncertainties of both satellite and ground-based retrievals and measurements.