WorldWideScience

Sample records for point standard nuclear

  1. Growth points in nuclear physics

    CERN Document Server

    Hodgson, Peter Edward

    1980-01-01

    Growth Points in Nuclear Physics, Volume 2 covers the progress in the fields of nuclear structure and nuclear reactions. This book is composed of three chapters. The first chapter is devoted to nuclear forces and potentials, in particular the optical model potential that enables the elastic scattering of many particles by nuclei to be calculated in a very simple manner. This chapter also deals with the three-body forces and the spin dependence of the nuclear potential. The second chapter describes higher order processes involving two or more stages, specifically their intrinsic interest and th

  2. Managing nuclear safety at Point Lepreau

    International Nuclear Information System (INIS)

    Paciga, J.

    1997-01-01

    Managing nuclear safety at Point Lepreau nuclear power plant is described, including technical issues (station aging, definition of the safe operating envelope, design configuration management, code validation, safety analysis and engineering standards); regulatory issues (action items, probabilistic safety assessment, event investigation, periodic safety review, prioritization of regulatory issues, cost benefit assessment); human performance issues (goals and measures, expectations and accountability, supervisory training, safety culture, configuration management, quality of operations and maintenance)

  3. 77 FR 70847 - Entergy Nuclear Indian Point 2, LLC; Entergy Nuclear Operations, Inc., Indian Point Nuclear...

    Science.gov (United States)

    2012-11-27

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Indian Point 2, LLC; Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit No. 2, Request for Action AGENCY: Nuclear Regulatory Commission. ACTION: Request for Action...

  4. Standards development for the nuclear industry

    International Nuclear Information System (INIS)

    Domondon, D.B.

    The ushering of nuclear era in the Philippines with the construction of the PNPP-I (Philippine Nuclear Power Plant) necessitates the evolvement and use of nuclear standards as a tool for safety evaluation in the licensing process. The Department of Nuclear Regulation and Safeguards under the Philippine Atomic Energy Commission has as one of its responsibilities the establishment of regulatory standards to ensure safe operation of nuclear facilities. This article points out the needs for nuclear standards and the steps in standard development which involve an enormous amount of resources in terms of manpower, expertise and money. The staff of the Department of Nuclear Regulations and Safeguards (DNRS) does not intend to engage in the original development of standards; rather, it reviews standards in use elsewhere, specifically in the U.S. and adopts to local conditions. (author)

  5. Technical standards in nuclear area

    International Nuclear Information System (INIS)

    Grimberg, M.

    1978-01-01

    The technical standardization in nuclear area is discussed. Also, the competence of CNEN in standardization pursuit is analysed. Moreover, the process of working up of technical standards is explained; in addition, some kinds of technical standards are discussed. (author) [pt

  6. Argentine nuclear energy standardization activities

    International Nuclear Information System (INIS)

    Boero, Norma; Corcuera, Roberto; Palacios, Tulio A.; Hey, Alfredo M.; Berte, G.; Trama, L.

    2004-01-01

    The International Organization for Standardization (ISO) has more than 200 Technical Committees that develop technical standards. During April 2004 took place in Buenos Aires the 14th Plenary of the ISO/TC 85 Nuclear Energy Committee. During this Plenary issues as Nuclear Terminology, Radiation Protection, Nuclear Fuels, Nuclear Reactors and Irradiation Dosimetry was dealt with. 105 International delegates and 45 National delegates (belonging to CNEA, ARN, NASA, INVAP, CONUAR, IONICS and other organizations) attended the meetings. During this meeting ISO/TC 85 changed its scope; the new scope of the Committee is 'Standardization in the fields of peaceful applications of nuclear energy and of the protection of individuals against all sources of ionizing radiations'. This work summarizes the most important advances and resolutions about the development of standards taken during this meeting as well as the main conclusions. (author) [es

  7. 76 FR 40945 - Entergy Nuclear Indian Point 2, LLC, Entergy Nuclear Indian Point 3, LLC, Entergy Nuclear...

    Science.gov (United States)

    2011-07-12

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY...] Entergy Nuclear Indian Point 2, LLC, Entergy Nuclear Indian Point 3, LLC, Entergy Nuclear Operations, Inc.... Schneiderman, Attorney General for the State of New York, the petitioner, has asked the U.S. Nuclear Regulatory...

  8. Nuclear Data Verification and Standardization

    Energy Technology Data Exchange (ETDEWEB)

    Karam, Lisa R.; Arif, Muhammad; Thompson, Alan K.

    2011-10-01

    The objective of this interagency program is to provide accurate neutron interaction verification and standardization data for the U.S. Department of Energy Division of Nuclear Physics programs which include astrophysics, radioactive beam studies, and heavy-ion reactions. The measurements made in this program are also useful to other programs that indirectly use the unique properties of the neutron for diagnostic and analytical purposes. These include homeland security, personnel health and safety, nuclear waste disposal, treaty verification, national defense, and nuclear based energy production. The work includes the verification of reference standard cross sections and related neutron data employing the unique facilities and capabilities at NIST and other laboratories as required; leadership and participation in international intercomparisons and collaborations; and the preservation of standard reference deposits. An essential element of the program is critical evaluation of neutron interaction data standards including international coordinations. Data testing of critical data for important applications is included. The program is jointly supported by the Department of Energy and the National Institute of Standards and Technology.

  9. IEEE Standard for Floating Point Numbers

    Indian Academy of Sciences (India)

    Home; Journals; Resonance – Journal of Science Education; Volume 21; Issue 1. IEEE Standard for Floating Point Numbers. V Rajaraman. General Article Volume 21 Issue 1 January 2016 pp 11-30. Fulltext. Click here to view fulltext PDF. Permanent link: http://www.ias.ac.in/article/fulltext/reso/021/01/0011-0030. Keywords.

  10. China's nuclear industry at a turning point

    International Nuclear Information System (INIS)

    Kubota, Hideo

    2009-01-01

    The China nuclear industry is coming at a turning point since the first Chinese nuclear power plant of Qinshan No.1 was started construction 24 years ago. At the end of year 2008, there are 11 nuclear power plants in operation in China. The total power capacity of the facilities has reached to 9068MW. It resulted in 11th position next to Sweden. Despite the nuclear power was reached to 68.4 billion KWh, it makes up only 2% of the total electric generation in China. The thermal power takes 81% of the total generation, in which the power by coal fuel takes for the most part and the total generation by both natural gas and oil fuel take only as small as a few percentage. In this situation, a nuclear power plant development is being accelerated. As of July 2009, China has 15 nuclear power plants currently under construction with a total capacity of 15260MW, that is more than 24000MW together with ones currently in operation. Furthermore, my research shows that China would have a plan to build 180 new nuclear power plants of 192770MW, though the progress varies widely. The construction speed of China nuclear power plant has become increasingly high since 2008. Starting with the construction of. Ningde unit 1 (PWR, 1110MW) in Fujian Province, February 2008, they continuously started constructions for five more nuclear power plants in year 2008 alone. China still holds momentum in a nuclear power plant construction even in 2009, and continues constructing new nuclear power plants. They include a Liaoning. Hongyanhe unit 3 in March, Sanmen Zhejiang April 19 which lead a construction first in the world for the third generation nuclear power plant of AP1000 (PWR, 1250MW) developed by Westinghouse, Fuqing unit 2 (PWR, 1000MW) June 17, and Fangjiashan unit 2 (PWR, 1000MW) on 17, July. Besides, Shidaowan, Rongcheng phase I (200MW), which is a demonstration reactor of HTGR in Shandong. They even said that China would start construction for approximately 7 to 9 nuclear power

  11. Management plan for the Nuclear Standards Program

    International Nuclear Information System (INIS)

    1979-11-01

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

  12. Management plan for the Nuclear Standards Program

    Energy Technology Data Exchange (ETDEWEB)

    1979-11-01

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

  13. Nuclear standards: current issues and future trends

    International Nuclear Information System (INIS)

    Landis, J.W.

    1985-01-01

    A summary of the important issues that currently face the nuclear standards field is presented and a discussion of how each of these issues is being resolved is given. The economic benefits that properly developed standards produce are listed

  14. The international dimensions of nuclear safety standards

    International Nuclear Information System (INIS)

    Reed, J.M.

    1992-01-01

    The paper reviews the activities of the major international organisations in the field of nuclear safety standards; the International Atomic Energy Agency (IAEA), the OECD's Nuclear Energy Agency (NEA) and the Commission of the European Communities. Each organisation encourages the concept of international nuclear safety standards. After Chernobyl, there were calls for some form of binding international nuclear safety standards. Many Member States of IAEA accepted these Codes as a suitable basis for formulating their national safety standards, but the prevailing view was that voluntary compliance with the Codes was the preferred path. With few reactor vendors in a limited international market, the time may be approaching when an internationally licensable nuclear reactor is needed. Commonly accepted safety standards would be a prerequisite. The paper discusses the issues involved and the complexities of standards making in the international arena. (author)

  15. Second nuclear reactor, Point Lepreau, New Brunswick

    International Nuclear Information System (INIS)

    Connelly, R.; Desjardins, L.

    1985-05-01

    This is a report of the findings, conclusions and recommendations of the Environmental Assessment Panel appointed by the Ministers of Environment of New Brunswick and Canada to review the proposal to build a seond nuclear unit at Point Lepreau, New Brunswick. The Panel's mandate was to assess the environmental and related social impacts of the proposal. The Panel concludes that the project can proceed without significant adverse effects provided certain recommendations are followed. In order to understand the impacts of Lepreau II, it was necessary to review, to the extent possible, the actual effects of Lepreau I before estimating the incremental effects of Lepreau II. In so doing, the Panel made a number of recommendations that should be implemented now. The information gathered and experience gained can be applied to Lepreau II to ensure that potential impacts are reduced to a minimum and existing concerns associated with Lepreau I can be corrected

  16. Nuclear standards index, January 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    This issue covers October through December 1980. An order form is included for making requests. Listings of discontinued or superseded NE(RDT) standards and of inactive standards are given as appendices. (DLC)

  17. 78 FR 39018 - Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating Unit Nos. 2 and 3

    Science.gov (United States)

    2013-06-28

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating Unit Nos. 2 and 3 AGENCY: Nuclear Regulatory Commission. ACTION: Supplement to Final Supplement 38 to the Generic Environmental...

  18. Standard test for nuclear waste materials

    International Nuclear Information System (INIS)

    Nelson, R.D.; Mendel, J.E.; Turcotte, R.P.

    1981-01-01

    The function of the Materials Characterization Center (MCC) is to provide the standardized materials data base and supporting documentation to help ensure safe disposal of nuclear waste. The methods and data are being published in a Nuclear Waste Materials Handbook DOE/TIC 11400. (DG)

  19. IEEE Standard for Floating Point Numbers

    Indian Academy of Sciences (India)

    IAS Admin

    is to decide how to represent real numbers using these bits. Normally, in ... numbers explained above, the largest floating point number which can be represented is. The number of bits to be used for the mantissa is determined by the number of significant decimal .... This is used to give an error message. When an operation.

  20. IEEE Standard for Floating Point Numbers

    Indian Academy of Sciences (India)

    IAS Admin

    This is a conservative definition used by industry. In MATLAB, machine epsilon is as defined above. However, academics define machine epsilon as the upper bound of the relative error when numbers are rounded. Thus, for 32-bit floating point numbers, the machine epsilon is 2–23/2. 5.96 ×10–8. The machine epsilon is ...

  1. Department of Energy Nuclear Energy Standards Program

    International Nuclear Information System (INIS)

    Silver, E.G.

    1980-01-01

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

  2. Nonreactor nuclear facilities: Standards and criteria guide

    International Nuclear Information System (INIS)

    Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

    1986-09-01

    This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

  3. Nonreactor nuclear facilities: standards and criteria guide

    International Nuclear Information System (INIS)

    Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

    1981-09-01

    This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

  4. 77 FR 40091 - Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating, Units 2 and 3

    Science.gov (United States)

    2012-07-06

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating, Units 2 and 3 AGENCY: Nuclear... statement for license renewal of nuclear plants; availability. SUMMARY: The U.S. Nuclear Regulatory...

  5. Standard terminology relating to nuclear materials

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This terminology standard contains terms, definitions, descriptions of terms, nomenclature, and explanations of acronyms and symbols specifically associated with standards under the jurisdiction of Committee C26 on Nuclear Fuel Cycle. This terminology may also be applicable to documents not under the jurisdiction of Committee C26, in which case this terminology may be referenced in those documents.

  6. Nuclear energy at the turning point

    International Nuclear Information System (INIS)

    Weinberg, A.M.

    1977-07-01

    In deciding the future course of nuclear energy, it is necessary to re-examine man's long-term energy options, in particular solar energy and the breeder reactor. Both systems pose difficultiies: energy from the sun is likely to be expensive as well as limited, whereas a massive world-wide deployment of nuclear breeders will create problems of safety and of proliferation. Nuclear energy's long-term success depends on resolving both of these problems. Collocation of nuclear facilities with a system of resident inspectors are measures that ought to help increase the proliferation-resistance as well as the safety of a large-scale, long-term nuclear system based on breeders. In such a long-term system a strengthened International Atomic Energy Agency (IAEA) is viewed as playing a central role

  7. Selecting safety standards for nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    Today, many thousands of documents are available describing the requirements, guidelines, and industrial standards which can be used as bases for a nuclear power plant programme. Many of these documents relate to nuclear safety which is currently the focus of world-wide attention. The multitude of documents available on the subject, and their varying status and emphasis, make the processes of selection and implementation very important. Because nuclear power plants are technically intricate and advanced, particularly in relation to the technological status of many developing countries, these processes are also complicated. These matters were the subject of a seminar held at the Agency's headquarters in Vienna last December. The IAEA Nuclear Safety Standards (NUSS) programme was outlined and explained at the Seminar. The five areas of the NUSS programme for nuclear power plants cover, governmental organization, siting, design; operation; quality assurance. In each area the Agency has issued Codes of Practice and is developing Safety Guides. These provide regulatory agencies with a framework for safety. The Seminar recognized that the NUSS programme should enable developing countries to identify priorities in their work, particularly the implementation of safety standards. The ISO activities in the nuclear field are carried out in the framework of its Technical Committee 85 (ISO/TC85). The work is distributed in sub-committees. Seminar on selection and implementation of safety standards for nuclear power plants, jointly organized by the IAEA and the International Organization for Standardization (ISO), and held in Vienna from 15 to 18 December 1980 concerned with: terminology, definitions, units and symbols (SC-1), radiation protection (SC-2), power reactor technology (SC-3), nuclear fuel technology (SC-5). There was general agreement that the ISO standards are complementary to the NUSS codes and guides. ISO has had close relations with the IAEA for several years

  8. Nuclear energy, a point for discussion

    International Nuclear Information System (INIS)

    Seibel, W.

    1977-01-01

    In a world no longer believing in a life after death, life on this world becomes an absolute value and death an absolute threat. The irrational parts of the resistence against nuclear energy, this worry for the saving of this value and the fear of this threat are seen. Such fears cannot be met with tables about accident frequency and risk factors. Therefore in the author's opinion, also the churches are requested to give a concerning answer to the question of the meaning of life, for these fears not to arise repeatedly, namely today in protests against technical development and nuclear energy, and tomorrow somewhere else. (GL) [de

  9. Standards: An international framework for nuclear safety

    International Nuclear Information System (INIS)

    Versteeg, J.

    2000-01-01

    The IAEA, uniquely among international organizations concerned with the use of radiation, radioactive materials and nuclear energy, has statutory functions to establish safety standards and to provide for their application in Member States. The IAEA also contributes towards another major element of the 'global safety culture', namely the establishment of legally binding international agreements on safety related issues. (author)

  10. Revision of the ASME nuclear quality assurance standard and its historical background

    International Nuclear Information System (INIS)

    Suzuki, Tetsuya

    2009-01-01

    ASME NQA-1-2008 'Quality Assurance Requirements for Nuclear Facility Applications' will be endorsed by US NRC by the end of 2009. This standard will apply to design, construction and operation of nuclear power plants newly erected in USA. It is important to Japanese vendors developing nuclear business in USA. Historical background, significance of revision and main revised points of the ASME nuclear quality assurance standard are described in the present paper. (T. Tanaka)

  11. International standards and quality control procedures applied to nuclear instruments

    International Nuclear Information System (INIS)

    Urbanski, P.

    2008-01-01

    The survey of international standards related to Nuclear Instrumentation and QC tests was presented. From among the 29'336 active international standards published by such organizations as ISO, IEC, CEN and CENELEC, only 582 are devoted to nuclear instruments. The international classification of standards (ICS) is shown. Also, the list of 582 international standards related to nuclear instruments is attached. (author)

  12. 75 FR 24997 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment...

    Science.gov (United States)

    2010-05-06

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment... Energy Point Beach, LLC (the licensee), for operation of the Point Beach Nuclear Plant, Units 1 and 2...

  13. Research on the management and endorsement of nuclear safety standards in the United States and its revelation for China

    Science.gov (United States)

    Liu, Ting; Tian, Yu; Yang, Lili; Gao, Siyi; Song, Dahu

    2018-01-01

    This paper introduces the American standard system, the Nuclear Regulatory Commission (NRC)’s responsibility, NRC nuclear safety regulations and standards system, studies on NRC’s standards management and endorsement mode, analyzes the characteristics of NRC standards endorsement management, and points out its disadvantages. This paper draws revelation from the standard management and endorsement model of NRC and points suggestion to China’s nuclear and radiation safety standards management.The issue of the “Nuclear Safety Law”plays an important role in China’s nuclear and radiation safety supervision. Nuclear and radiation safety regulations and standards are strong grips on the implementation of “Nuclear Safety Law”. This paper refers on the experience of international advanced countriy, will effectively promote the improvement of the endorsed management of China’s nuclear and radiation safety standards.

  14. 77 FR 36015 - Atomic Safety and Licensing Board; Entergy Nuclear Operations, Inc. (Indian Point Nuclear...

    Science.gov (United States)

    2012-06-15

    ... COMMISSION Atomic Safety and Licensing Board; Entergy Nuclear Operations, Inc. (Indian Point Nuclear... proceeding arises out of the April 23, 2007, application of Entergy Nuclear Operations, Inc. (Entergy) to.... (Riverkeeper). On October 18, 2007, this Atomic Safety and Licensing Board was established to conduct this...

  15. Globalization of ASME Nuclear Codes and Standards

    International Nuclear Information System (INIS)

    Swayne, Rick; Erler, Bryan A.

    2006-01-01

    With the globalization of the nuclear industry, it is clear that the reactor suppliers are based in many countries around the world (such as United States, France, Japan, Canada, South Korea, South Africa) and they will be marketing their reactors to many countries around the world (such as US, China, South Korea, France, Canada, Finland, Taiwan). They will also be fabricating their components in many different countries around the world. With this situation, it is clear that the requirements of ASME Nuclear Codes and Standards need to be adjusted to accommodate the regulations, fabricating processes, and technology of various countries around the world. It is also very important for the American Society of Mechanical Engineers (ASME) to be able to assure that products meeting the applicable ASME Code requirements will provide the same level of safety and quality assurance as those products currently fabricated under the ASME accreditation process. To do this, many countries are in the process of establishing or changing their regulations, and it is important for ASME to interface with the appropriate organizations in those countries, in order to ensure there is effective use of ASME Codes and standards around the world. (authors)

  16. Seismic design standardization of nuclear facilities

    International Nuclear Information System (INIS)

    Reddy, G.R.; Vaze, K.K.

    2011-01-01

    Full text: Structures, Systems and Components (SSCs) of Nuclear Facilities have to be designed for normal operating loads such as dead weight, pressure, temperature etc., and accidental loads such as earthquakes, floods, extreme, wind air craft impact, explosions etc. Man made accidents such as aircraft impact, explosions etc., some times may be considered as design basis event and some times taken care by providing administrative controls. This will not be possible in the case of natural events such as earthquakes, flooding, extreme winds etc. Among natural events earthquakes are considered as most devastating and need to be considered as design basis event. It is generally felt design of SSCs for earthquake loads is very time consuming and expensive. Conventional seismic design approaches demands for large number of supports for systems and components. This results in large space occupation and in turn creates difficulties for maintenance and in service inspection of systems and components. In addition, complete exercise of design need to be repeated for plants being located at different sites due to different seismic demands. However, advanced seismic response control methods will help to standardize the seismic design meeting the safety and economy. These methods adopt passive, semi active and active devices, and base isolators to control the seismic response. In nuclear industry, it is advisable to go for passive devices to control the seismic responses. Ideally speaking, these methods will make the designs made for normal loads can also satisfy the seismic demand without calling for change in material, geometry, layout etc. in the SSCs. This paper explain the basic ideas of seismic response control methods, demonstrate the effectiveness of control methods through case studies and eventually give the procedure to be adopted for seismic design standardization of nuclear facilities

  17. Analysis and suggestions on standard system for general nuclear instruments

    International Nuclear Information System (INIS)

    Xiong Zhenglong

    1999-08-01

    The standard system has been analyzed and researched for the general nuclear instruments and propounded following suggestions against the problems in standard's system: seriously adopting the international standards and recommending Chinese standards toward the world; appropriately regularizing the system's frame and the standard's configurations to make it more scientific, perfect and applicable; enhancing the construction of technical and basic standards, promoting the standardization of entire nuclear instruments; replenishing the standards of the testing methods and straightening out the standard's level, further completing the standard's system. In short, all of them are to enhance quality, readability and maneuverability of standards, to exert sufficiently the effects of standards

  18. Standardization of Nuclear Instrumentation Applied in the NPP and in other nuclear installations

    International Nuclear Information System (INIS)

    Kusnowo, Arlinah; Darmawati, Suzie

    2002-01-01

    Nuclear power plant (NPP) and other nuclear installations have been recognized as applications needing very sophisticated technologies. One of technologies used in this all nuclear facilities is nuclear instrumentation. In order that NPP and other nuclear installations be operated safely, nuclear instrumentation requires standardization from design to its operation. Internationally, standardizations of nuclear instrumentation have been issued by IEC (International Electrotechnical Commission). Formulation of standard in nuclear instrumentation in IEC is carried out by Technical Committee (TC) 45. This paper describes briefly the standardization of nuclear instrumentation applied in Indonesia as Indonesian National Standard (SNI, Standard National Indonesia), standardization of nuclear instrumentation developed by TC 45, SC 45A, and SC 45B, as well as the possibility to adopt and apply those IEC standard in Indonesia

  19. 77 FR 16278 - License Renewal Application for Indian Point Nuclear Generating Units 2 and 3; Entergy Nuclear...

    Science.gov (United States)

    2012-03-20

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION License Renewal Application for Indian Point Nuclear Generating Units 2 and 3; Entergy Nuclear Operations, Inc. AGENCY: Nuclear Regulatory Commission. ACTION: License renewal application; intent to...

  20. 78 FR 26662 - Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit No. 3 Extension of Public...

    Science.gov (United States)

    2013-05-07

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit No. 3 Extension of Public Comment Period AGENCY: Nuclear Regulatory Commission. ACTION: Draft environmental assessment and finding...

  1. Evaluation of correlative nuclear data at certain energy point

    International Nuclear Information System (INIS)

    Zhang Jianhua; Liu Tingjin.

    1993-01-01

    A method to process correlative nuclear data at certain energy point is presented. The corresponding processing code has also been developed. Using the code, the effects of the correlation have been discussed in detail for the cases of the two and three data. (3 figs.)

  2. Domestic and International Nuclear Energy Voluntary Consensus Standards Needs

    International Nuclear Information System (INIS)

    Hopper, Calvin Mitchell

    2013-01-01

    This report introduces the reader to the domestic and international standards development organizations (SDOs) and their structures and operations. It also identifies some of the support and subject matter needs for the development of standards on the subject of nuclear energy. The support needs are described with regard to organizational structure and subject-matter-expert (SME) participation that is required for producing voluntary consensus standards. The subject matter needs are described with regard to growing technologies and objectives that approach the boundaries of existing standards; implementation of knowledge; and safety of people, facilities, and the environment. Standards are proposed, developed, and produced by SMEs with the support of industry and government organizations. The voluntary consensus standards development process is, as its name implies, a voluntary effort. The problem in today's competitive market, impacted by global economic uncertainty, is that the voluntary participation is shifting from a collaborative industry and SME effort to a nearly SME-only one. This shift places a financial and/or time burden on the SMEs to the point that they are purposely withdrawing from the standards development process, both domestically and internationally. The standards development process desperately needs participation from more and younger SMEs. The report includes several suggestions on how this can be addressed.

  3. Korea-South Africa nuclear energy focal point

    International Nuclear Information System (INIS)

    Kim, Y. H.; Lee, K. H.; Park, M. K.; Chae, J. S.; Cheon, K. J.

    2007-09-01

    The major objective of the project is to hold Korea-S. Africa joint nuclear or workshop and establish a network of nuclear experts between the two countries. In addition, identification of the collaboration items is another objective of this project. the outcome of this program would be a cornerstone for the nuclear collaboration between Korea and S. Africa. African countries is usually very abundant in the natural resources and developed countries are trying to improve relationships with African countries to secure the natural resources, S. Africa is also very rich with some resources including uranium. Therefore, Korea depending on foreign resources needs to improve the relationship with S. Africa form the viewpoint of securing natural resources. S. Africa has two PWR-type nuclear power plants and is planning to deploy more PWRs to increase the nuclear capacity. In addition, S. Africa is a leading country in developing the PBMR, which is a type of Generation-IV VHTR (very high temperature reactor). In Korea, the VHTR technologies are also under development for the nuclear hydrogen. Although Korea has its own PWR brand, it is not well known to S. Africa. The focal point program would lay a cornerstone for mutually beneficial nuclear collaborations between two countries

  4. Brief overview of American Nuclear Society's research reactor standards

    International Nuclear Information System (INIS)

    Richards, Wade J.

    1984-01-01

    The American Nuclear Society (ANS) established the research reactor standards group in 1968. The standards group, known as ANS-15, was established for the purpose of developing, preparing, and maintaining standards for the design, construction, operation, maintenance, and decommissioning of nuclear reactors intended for research and training

  5. Skills renewal in nuclear an industrialist's point of view

    International Nuclear Information System (INIS)

    Bonnet, Michel; Louvel, Dominique

    2010-01-01

    Global energy needs are increasing and at the same time, the use of fossil fuels for energy is being questioned for several reasons: the possible shortage of resources; the volatility of their prices; the impact of their use on global warming, to name but a few. Focusing on the demand for electricity, forecasts from the World Nuclear Association show a dramatically growing trend and a necessity for massive investments in response to this. Over the 2000-2030 period, the needs for extra electricity generation in Europe are estimated at 660 GW, in North America the forecasted level of needs is 850 GW, in China, it is 1,300 GW. Given the current fossil fuel situation, nuclear energy is undoubtedly part of the answer to the growing demand for electricity generation, along with renewable energies and energy efficiency. In most countries, nuclear power plants were commissioned over a relatively short period (1970-1985). Except maybe in some regions, the Chernobyl accident put this technology on hold for twenty years, meaning that an ageing workforce is now an issue for the nuclear industry. The recruitment of a significant number of engineers is thus necessary, both to launch new nuclear projects and to replace employees about to retire. In France, 40% of all nuclear engineers will retire over the next decade. During this period, around 1,200 engineers per year will be recruited, including 600 per year by EDF (a fourfold increase). In many countries, the recruitment of engineers has remained at a very low level for the past 15 years and consequently education programs have been cut back. Furthermore, teaching positions have not been renewed and only a few qualified individuals remain, most of whom are nearing retirement age. The revival of nuclear education is a key point for the success of the nuclear renaissance. In 2007-2008, the High Commissioner for Atomic Energy conducted a census of existing French nuclear teaching programs. By this time, capacity in France was

  6. 75 FR 16201 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Exemption

    Science.gov (United States)

    2010-03-31

    ... From the Federal Register Online via the Government Publishing Office ] NUCLEAR REGULATORY COMMISSION FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Exemption 1.0 Background... letter from R. W. Borchardt (NRC) to M. S. Fertel (Nuclear Energy Institute) dated June 4, 2009. The...

  7. 75 FR 14206 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment...

    Science.gov (United States)

    2010-03-24

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-266 And 50-301; NRC-2010-0123 FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear...

  8. Free Release Standards Utilized at Big Rock Point

    International Nuclear Information System (INIS)

    Robert P. Wills

    2000-01-01

    The decommissioning of Consumers Energy's Big Rock Point (BRP) site involves decommissioning its 75-MW boiling water reactor and all of the associated facilities. Consumers Energy is committed to restoring the site to greenfield conditions. This commitment means that when the decommissioning is complete, all former structures will have been removed, and the site will be available for future use without radiological restrictions. BRP's radiation protection management staff determined that the typical methods used to comply with U.S Nuclear Regulatory Commission (NRC) regulations for analyzing volumetric material for radionuclides would not fulfill the demands of a facility undergoing decommissioning. The challenge at hand is to comply with regulatory requirements and put into production a large-scale bulk release production program. This report describes Consumers Energy's planned approach to the regulatory aspects of free release

  9. The training and assessment of operations engineers at Hinkley Point 'B' nuclear power station

    International Nuclear Information System (INIS)

    Walsey, B.A.; Howard, J.D.

    1986-01-01

    The Nuclear Power Training Centre at Oldbury-on-Severn was established to provide a common training of staff at all nuclear power stations operated by the Central Electricity Generating Board, following the ''Standard Specification for the Nuclear Training of Staff at CEGB Nuclear Power Stations''. The paper deals with the following aspects of AGR Stations: The Legislation applicable to these stations. The current training requirements for Operations Staff. The development of training for operations staff at Hinkley Point 'B' including training for career progression within the Operations Department. A detailed explanation of the training package developed for Reactor Desk Drivers at Hinkley 'B'. Revision training of Operations staff to ensure that they continue to run the plant in a safe and commercially viable manner. The training of Shift Operations Engineers for their duties under the Station Emergency Plan. (author)

  10. Top-k point of interest retrieval using standard indexes

    DEFF Research Database (Denmark)

    Skovsgaard, Anders; Jensen, Christian S.

    2014-01-01

    With the proliferation of Internet-connected, location-aware mobile devices, such as smartphones, we are also witnessing a proliferation and increased use of map-based services that serve information about relevant Points of Interest (PoIs) to their users. We provide an efficient and practical......I as a compact bit string. This technique extends an existing spatial encoding to also encode the textual aspect of a PoI in compressed form. The resulting bit strings may then be indexed using index structures such as B-trees or hashing that are standard in DBMSs and key-value stores. As a result......, it is straightforward to support the proposed functionality using existing data management systems. The paper also proposes a novel top-k query algorithm that merges partial results while providing an exact result. An empirical study with real-world data indicates that the proposed techniques enable excellent indexing...

  11. 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)

  12. List of foreio.n standards in nuclear technology

    International Nuclear Information System (INIS)

    Brabec, D.

    1984-01-01

    The bibliography comprises international standards of CMEA, ISO, IEC and national standards of the USSR, GDR, FRG, France, UK, USA and Austria in the field of nuclear power, nuclear engineering and the peaceful uses of ionizing radiation and radionuclides. Also included are standards covering other industrial sectors where the standardized object or activity is linked with ionizing radiation or radionuclides, as well as standards covering metrology, quality control and testing. The bibliography is complete with instructions for use, sources and a subject index and index of standard numbers. (Ha)

  13. The latest trend of nuclear standards

    International Nuclear Information System (INIS)

    Tobioka, Toshiaki

    2000-01-01

    In Japan, the Atomic Energy Fundamental Law is enacted as a fundamental law on application of atomic energy. According to provision of the Law, various regulations essential to prevent national disaster, to protect nuclear substances and to secure public safety are carried out. From a viewpoint of disaster prevention, 'the Law on Regulation of Nuclear Raw Materials, Nuclear Fuel Substances and Nuclear Reactors' is enacted for its main law. On countermeasure to an emergency of accident formation at a nuclear facility, 'the Disaster Countermeasure Fundamental Law' is enacted as a general law for disaster countermeasure and defined obligation, organization, and so on of government, local community, and so on for the disaster containing large scale natural disaster, and recently 'the Nuclear Disaster Special Measure Act' was enacted by receiving necessity of enforced cooperation between government and local community. However, for a general tendency, these regulation rules and now transferring from the conventional system where a means to establish an object in safety is regulated in a meaning to a form required to finish a concrete safe target. (G.K.)

  14. Nuclear Data Center International Standard Towards TSO Initiative

    International Nuclear Information System (INIS)

    Raja Murzaferi Raja Moktar; Mohd Fauzi Haris; Siti Nurbahyah Hamdan

    2011-01-01

    Nuclear Data Center is the main facility for Nuclear Malaysia Agency IT infrastructure comprising of main critical servers, research and operational data storage, HPC-clusters system and vital network core equipment. In recent years, international body such as TIA-Telecommunication Industry Association and Up time Institute have came out with proper international data center standards in order to ensure data center operation on achieving maximum operational up time and minimal downtime. The standard are currently being rated as tier level ranging from Data Center tier I up to tier IV, differentiate by facility standard and up time/ downtime percentage ratio. This paper will discuss Nuclear Data Center adopting international standards in supporting Nuclear Malaysia TSO initiative thus ensuring the critical core component of agency IT services availability and further more International standard recognitions. (author)

  15. Nuclear Knowledge Capture and IEC Standards

    International Nuclear Information System (INIS)

    Sheldon, J.

    2016-01-01

    Full text: An International Standard is a document, established by consensus and approved by a recognized body that provides, for common and repeated use, rules, guidelines or characteristics for activities or their results, aimed at the achievement of the optimum degree of order in a given context. As such, it is a mechanism for sharing knowledge in a particular field. The consensus process used to approve the content of standards ensures that the content is essentially peer-reviewed. This presentation will explain how International Standards are developed and used and their importance in the dissemination of scientific and engineering information. It will also explain the role of the IEC in ensuring that the process for developing standards meets the core principles of the Code of Good Practice of the WTO TBT agreement: transparency, openness, impartiality and consensus, effectiveness and relevance, coherence, and addressing the concerns of developing countries. (author

  16. Shell effects at the touching point of nuclear fragments

    International Nuclear Information System (INIS)

    Poenaru, D.N.; Gherghescu, R.A.; Greiner, W.

    1999-01-01

    Shell correction energy of the fission fragments remains practically unchanged when the separation distance increases from the sum of their radii up to infinity. The variation with mass asymmetry of the total deformation energy at the touching point configuration shows the valleys corresponding to different decay modes, which are produced when the two proton and/or the two neutron numbers are magic or almost magic. We present a potential energy surface of the proton-rich α-emitter 106 Te, showing the α-decay valley, obtained with a phenomenological shell correction. We discuss the difficulties to produce such a valley on a potential energy surface of 236 Pu, calculated with the macroscopic-microscopic method, in which the nuclear level scheme is found within the two center shell model. The valleys mainly due to the double magic nuclei 100,132 Sn, 208 Pb, and other magic numbers, are illustrated by plotting the deformation energy at the touching point versus the proton number of the fragment, for the following parent nuclei: 106 Te, 116 Ce, 212 Po, 238 Th, 258 Fm and 264 Fm. For ternary fission the gain in energy of compact configurations as compared to aligned ones is analysed. (authors)

  17. Standard leach tests for nuclear waste materials

    International Nuclear Information System (INIS)

    Strachan, D.M.; Barnes, B.O.; Turcotte, R.P.

    1980-01-01

    Five leach tests were conducted to study time-dependent leaching of waste forms (glass). The first four tests include temperature as a variable and the use of three standard leachants. Three of the tests are static and two are dynamic (flow). This paper discusses the waste-form leach tests and presents some representative data. 4 figures

  18. Standard specification for nuclear-grade hafnium oxide powder

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This specification defines the physical and chemical requirements for hafnium oxide powder intended for fabrication into shapes for use in a nuclear reactor core. 1.2 The material described herein shall be particulate in nature. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

  19. Status of ANSI standards on decommissioning of nuclear reprocessing facilities

    International Nuclear Information System (INIS)

    Graham, H.B.

    1975-01-01

    A definition of decommissioning is given, and the preparation of ANSI Standard, ''General Design Criteria for Nuclear Reprocessing Facilities'' (N101.3) is discussed. A Eurochemic report, entitled ''The Shutdown of Reprocessing Facilities--Results of Preliminary Studies on the Installations Belonging to Eurochemic,'' was used in the preparation of this standard. (U.S.)

  20. The IAEA safety standards for radiation, waste and nuclear safety

    International Nuclear Information System (INIS)

    Gonzalez, Abel J.

    1997-01-01

    This paper presents a brief description of the standards for radiation, waste and nuclear safety established by the International Atomic Energy Agency (IAEA). It provides a historical overview of their development and also summarizes the standards' current preparation and review process. The final paragraphs offer an outlook on future developments. (author)

  1. ASME nuclear codes and standards risk management strategic planning

    International Nuclear Information System (INIS)

    Hill, Ralph S. III; Balkey, Kenneth R.; Erler, Bryan A.; Wesley Rowley, C.

    2007-01-01

    This paper is prepared in honor and in memory of the late Professor Emeritus Yasuhide Asada to recognize his contributions to ASME Nuclear Codes and Standards initiatives, particularly those related to risk-informed technology and System Based Code developments. For nearly two decades, numerous risk-informed initiatives have been completed or are under development within the ASME Nuclear Codes and Standards organization. In order to properly manage the numerous initiatives currently underway or planned for the future, the ASME Board on Nuclear Codes and Standards (BNCS) has an established Risk Management Strategic Plan (Plan) that is maintained and updated by the ASME BNCS Risk Management Task Group. This paper presents the latest approved version of the plan beginning with a background of applications completed to date, including the recent probabilistic risk assessment (PRA) standards developments for nuclear power plant applications. The paper discusses planned applications within ASME Nuclear Codes and Standards that will require expansion of the ASME PRA Standard to support new advanced light water reactor and next generation reactor developments, such as for high temperature gas-cooled reactors. Emerging regulatory developments related to risk-informed, performance- based approaches are summarized. A long-term vision for the potential development and evolution to a nuclear systems code that adopts a risk-informed approach across a facility life-cycle (design, construction, operation, maintenance, and closure) is also summarized. Finally, near term and long term actions are defined across the ASME Nuclear Codes and Standards organizations related to risk management, including related U.S. regulatory activities. (author)

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

    Science.gov (United States)

    2013-09-24

    ... Assessment; Entergy Nuclear Operations, Inc., Big Rock Point AGENCY: Nuclear Regulatory Commission. ACTION... applicant or the licensee), for the Big Rock Point (BRP) Independent Spent Fuel Storage Installation (ISFSI... Rock Point (BRP) Independent Spent Fuel Storage Installation (ISFSI). II. Environmental Assessment (EA...

  3. American National Standard: nuclear data sets for reactor design calculations

    International Nuclear Information System (INIS)

    1983-01-01

    This standard identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include criteria for acceptance of evaluated nuclear data sets, criteria for processing evaluated data and preparation of processed continuous data and averaged data sets, and identification of specific evaluated, processed continuous, and averaged data sets which meet these criteria for specific reactor types

  4. American National Standard nuclear data sets for reactor design calculations

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    A standard is presented which identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include (a) criteria for acceptance of evaluated nuclear data sets, (b) criteria for processing evaluated data and preparation of processed continuous data and averaged data sets, and (c) identification of specific evaluated, processed continuous, and averaged data sets which meet these criteria for specific reactor types

  5. The U.S. EPR: a standardized nuclear power plant

    International Nuclear Information System (INIS)

    Hudson, F.G.

    2007-01-01

    The U.S. EPR is an evolutionary 1600 MW PWR design that represents the U.S. element of AREVA-NP's global EPR fleet. Simply stated, AREVA-NP's business strategy is to launch a global fleet of standardized EPRs. The EPR's standardisation process addresses the following topics: 1) standardized utility requirements, 2) standardized licensing, 3) commercial standardization, and 4) life-cycle standardization. AREVA-NP's approach for EPR design standardization is achieved via a hierarchical configuration management process that is applied both globally and regionally. A key element of this standardization process is the EPR Configuration Management Board (ECMB) whose purpose is twofold: manage the configuration of the EPR generic design and ensure the orderly identification and transfer of lessons learned among global EPR projects. The project management process established by ECMB consists of 3 major elements. First, the U.S. EPR Steering Committee that was established to oversee U.S. EPR project execution in the context of AREVA-NP's other EPR projects. Secondly, the U.S. EPR Standardization Committee whose primary role is to maintain U.S. EPR standardization as well as global standardization as directed by ECMB. Thirdly, the U.S. EPR Change Control Review that will determine the relevancy of issues or any proposed change. UniStar Nuclear is a joint venture between Constellation Generation and AREVA-NP that provides a flexible business model for new nuclear generation. Standardized operation of U.S. EPR units is a fundamental tenet of UniStar Nuclear that will complete the U.S. EPR approach for life-cycle commitment to standardization

  6. Revision of AESJ standard 'the code of implemnetation of periodic safety review of nuclear power plants'

    International Nuclear Information System (INIS)

    Hirano, Masashi; Narumiya, Yoshiyuki

    2010-01-01

    The Periodic Safety Review (PSR) was launched in June 1992, when the Agency for Natural Resources and Energy issued a notification that required licensees to conduct comprehensive review on the safety of each existing nuclear power plant (NPP) once approximately every ten years based on the latest technical findings for the purpose of improving the safety of the NPP. In 2006, the Standard Committee of the Atomic Energy Society of Japan established the first version of 'The Standard of Implementation for Periodic Safety Review of Nuclear Power Plants: 2006'. Taking into account developments in safety regulation of PSR after the issuance of the first version, the Standard Committee has revised the Standard. This paper summarizes background on PSR, such developments are major contents of the Standard as well as the focal points of the revision. (author)

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

    International Nuclear Information System (INIS)

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

    1981-07-01

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

  8. Standard specification for nuclear-grade zirconium oxide powder

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This specification defines the physical and chemical requirements for zirconium oxide powder intended for fabrication into shapes, either entirely or partially of zirconia, for use in a nuclear reactor core. 1.2 The material described herein shall be particulate in nature. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

  9. Point DCT VLSI Architecture for Emerging HEVC Standard

    OpenAIRE

    Ahmed, Ashfaq; Shahid, Muhammad Usman; Rehman, Ata ur

    2012-01-01

    This work presents a flexible VLSI architecture to compute the -point DCT. Since HEVC supports different block sizes for the computation of the DCT, that is, 4 × 4 up to 3 2 × 3 2 , the design of a flexible architecture to support them helps reducing the area overhead of hardware implementations. The hardware proposed in this work is partially folded to save area and to get speed for large video sequences sizes. The proposed architecture relies on the decomposition of the DCT matrices into ...

  10. Merits and difficulties in adopting codes, standards and nuclear regulations

    International Nuclear Information System (INIS)

    El-Saiedi, A.F.; Morsy, S.; Mariy, A.

    1978-01-01

    Developing countries planning for introducing nuclear power plants as a source of energy have to develop or adopt sound regulatory practices. These are necessary to help governmental authorities to assess the safety of nuclear power plants and to perform inspections needed to confirm the established safe and sound limits. The first requirement is to form an independent regulatory body capable of setting up and enforcing proper safety regulations. The formation of this body is governed by several considerations related to local conditions in the developing countries, which may not always be favourable. It is quite impractical for countries with limited experience in the nuclear power field to develop their own codes, standards and regulations required for the nuclear regulatory body to perform its tasks. A practical way is to adopt codes, standards and regulations of a well-developed country. This has merits as well as drawbacks. The latter are related to problems of personnel, software, equipment and facilities. The difficulties involved in forming a nuclear regulatory body, and the merits and difficulties in adopting foreign codes, standards and regulations required for such body to perform its tasks, are discussed in this paper. Discussions are applicable to many developing countries and particular emphasis is given to the conditions and practices in Egypt. (author)

  11. Personnel involved in nuclear standards development: 1980 directory

    International Nuclear Information System (INIS)

    Carr, S.J.

    1980-03-01

    The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development

  12. Personnel involved in nuclear standards development: 1980 directory

    Energy Technology Data Exchange (ETDEWEB)

    Carr, S.J. (ed.)

    1980-03-01

    The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development.

  13. Standard specification for nuclear-Grade boron carbide pellets

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2007-01-01

    1.1 This specification applies to boron carbide pellets for use as a control material in nuclear reactors. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

  14. Standard Specification for Nuclear Grade Zirconium Oxide Pellets

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

  15. Standard hazard analysis, critical control point and hotel management

    Directory of Open Access Journals (Sweden)

    Vujačić Vesna

    2017-01-01

    Full Text Available Tourism is a dynamic category which is continuously evolving in the world. Specificities that have to be respected in the execution in relation to the food industry are connected with the fact that the main differences which exist regarding the food serving procedure in catering, numerous complex recipes and production technologies, staff fluctuation, old equipment. For an effective and permanent implementation, the HACCP concept is very important for building a serious base. In this case, the base is represented by the people handling the food. This paper presents international ISO standards, the concept of HACCP and the importance of its application in the tourism and hospitality industry. The concept of HACCP is a food safety management system through the analysis and control of biological, chemical and physical hazards in the entire process, from raw material production, procurement, handling, to manufacturing, distribution and consumption of the finished product. The aim of this paper is to present the importance of the application of HACCP concept in tourism and hotel management as a recognizable international standard.

  16. Formation of research group for standard nuclear engineering software development

    International Nuclear Information System (INIS)

    Okajima, Shigeaki; Sakamoto, Yukio

    2011-01-01

    JAEA has set up a new research group for Standard Nuclear Engineering Software Development in the Nuclear Science and Engineering Directorate in April, 2011. The paper introduces the aim and role of this new group in the computer simulation technology important in nuclear science and industrial development. Hitherto, they made efforts mainly to develop new computer codes and database in Japan. The new group is expected to maintain and modify the developed codes and database in accordance to the users needs. Evaluated Nuclear Data Library, Monte Carlo N-Particle Transport Code System, Evaluated Actinide Data, Heavy Ion Transport code System, Monte Carlo Codes for Neutron and Photon Transport Calculation and others are included for explanation. (S. Ohno)

  17. Point DCT VLSI Architecture for Emerging HEVC Standard

    Directory of Open Access Journals (Sweden)

    Ashfaq Ahmed

    2012-01-01

    Full Text Available This work presents a flexible VLSI architecture to compute the -point DCT. Since HEVC supports different block sizes for the computation of the DCT, that is, 4×4 up to 32×32, the design of a flexible architecture to support them helps reducing the area overhead of hardware implementations. The hardware proposed in this work is partially folded to save area and to get speed for large video sequences sizes. The proposed architecture relies on the decomposition of the DCT matrices into sparse submatrices in order to reduce the multiplications. Finally, multiplications are completely eliminated using the lifting scheme. The proposed architecture sustains real-time processing of 1080P HD video codec running at 150 MHz.

  18. International standardization of nuclear reactor designs - the way forward

    International Nuclear Information System (INIS)

    Raetzke, Christian

    2010-01-01

    The concept of 'International Standardization of Nuclear Reactor Designs' means that vendors could build their designs in every country without having to adapt it specifically to national safety requirements. Such standardization would have two main effects. It would greatly facilitate nuclear new build worldwide by giving greater efficiency and certainty to the national licensing procedures; by taking into account the fact that vendors, and nowadays also utilities, are active across borders; by helping developing countries to establish their nuclear new build programmes; and by reducing the strain on human resources on both the regulators' and the industry's side. The second valuable effect of standardization would be to further enhance safety by improving the exchange of construction and operating experience among a number of reactors belonging to fleets of the same design. The World Nuclear Association's CORDEL (Cooperation in Reactor Design Evaluation and Licensing) Group has developed a concept for implementation of international standardization of reactor designs. It has defined a number of steps to be taken by industry. At the same time, possibilities offered by national and international regulatory mechanisms would have to be fully made use of, and some changes in regulatory frameworks might be necessary. Some steps especially towards greater cooperation of regulators have already been taken; however, much still remains to be done. The concept of deploying standardized reactor designs across a number of countries supposes an alignment and, if possible, harmonization of national safety standards; a streamlining of national licensing procedures, making them more efficient and predictable; and the willingness of national regulators to take into account licensing done in other countries. In the end, this should lead to a mutual acceptance of design approvals or, in a more distant future, even to a multinational design approval process. All in all, the concept

  19. Nuclear energy from the point of view of the population

    International Nuclear Information System (INIS)

    Renn, O.

    1977-12-01

    The present study refers mainly to an empirical attitude investigation carried out in 1975 and 1976 in a suburb of Cologne. In order to remain up-to-date, new research results have been included in the analysis. The aim of the publication at hand is to deal with the nuclear controversy in its sociological and social-psychological dimensions, and also to elucidate motives and reasons behind the protests against nuclear energy. The report has been written for sociologists, nuclear engineers and scientists, journalists, political decision-finding authorities and interested laymen alike, and is to offer a general orientation in contradicting statements as regards the stance of the population. The central statement of this very detailed investigation is, that the population has a mainly positive attitude towards the construction of a nuclear power plant - even then when antipathy and uneasiness towards a new energy source prevent emotional identification. (orig./HP) [de

  20. International implications of nuclear Q.A. standards

    International Nuclear Information System (INIS)

    Stoddart, D.E.

    1976-01-01

    The work of the International Atomic Energy Agency (I.A.E.A.) in the field of Quality Assurance is aimed at preparing a Code of Practice covering recommendations on safety aspects only which is designed to be usable by all nations. This Code is followed up by a series of Safety Guides as aids to developing nations faced with the need to regulate and assure safety, reliability and quality. The I.A.E.A. Code is not written as a mandatory document and it can only recommend and therefore the term 'should' is used throughout. The International Organization for Standardization (I.S.O.) is concerned with producing standards and as such the proposed I.S.O. draft standard on 'Quality Assurance for Nuclear Power Plants' is written in mandatory language, it uses the word 'shall'. The I.S.O. standard will also cover not only safety aspects but also those of a successfully operating nuclear power plant. The I.S.O. Working Group is charged with producing standards on quality assurance covering the design, procurement, fabrication, construction, operation, maintenance and decommissioning of structure, systems and components of nuclear power plants. The work of both organizations is discussed briefly. (author)

  1. Issues and possible solutions of nuclear power standard system in china

    International Nuclear Information System (INIS)

    Li Xiaoyan; Pu Jilong

    2008-01-01

    The construction of nuclear power standard system shall follow the development state of the nuclear power in China, and shall be taken as one of the important support for the self-reliance in the development of nuclear industry. However, there is no national nuclear power standard systems that is matched to the industrial system and technology base in China. It is widely recognized in nuclear industry that the nuclear power standard system must be established. This paper discusses various problems of the current national nuclear power standard system and suggests the possible solutions. Electricity industry standard system can be referenced to set up nuclear power standard system in China. Considering the need to construct a lot of PWR nuclear power stations in China, the design and construction standard system for PWR NPP shall be established. The nuclear safety guides in China shall be incorporated into the nuclear power standards. (authors)

  2. Report on ANSI/ASME nuclear air and gas treatment standards for nuclear power plants

    International Nuclear Information System (INIS)

    Fish, J.F.

    1979-01-01

    Original N Committee, N45-8, has completed and published through the approved American National Standards Institute process two Standards, N-509 and N-510. This committee has been dissolved and replaced by ASME Committee on Nuclear Air and Gas Treatment with expanded scope to cover not only air cleaning, but thermal treatment equipment. Current efforts are directed to produce Code documents rather than Standards type publications. This report summarizes changed scope, current organization and sub-committee coverage areas

  3. Recent Progress on the Standardized DOE Spent Nuclear Fuel Canister

    International Nuclear Information System (INIS)

    Morton, D.K.; Snow, S.D.; Rahl, T.E.; Hill, T.J.; Morissette, R.P.

    2002-01-01

    The Department of Energy (DOE) has developed a set of containers for the handling, interim storage, transportation, and disposal in the national repository of DOE spent nuclear fuel (SNF). This container design, referred to as the standardized DOE SNF canister or standardized canister, was developed by the Department's National Spent Nuclear Fuel Storage Program (NSNFP) working in conjunction with the Office of Civilian Radioactive Waste Management (OCRWM) and the DOE spent fuel sites. This canister had to have a standardized design yet be capable of accepting virtually all of the DOE SNF, be placed in a variety of storage and transportation systems, and still be acceptable to the repository. Since specific design details regarding the storage, transportation, and repository disposal of DOE SNF were not finalized, the NSNFP recognized the necessity to specify a complete DOE SNF canister design. This allowed other evaluations of canister performance and design to proceed as well as providing standardized canister users adequate information to proceed with their work. This paper is an update of a paper presented to the 1999 American Nuclear Society of Mechanical Engineers (ASME) Pressure Vessels and Piping (PVP) Conference. It discusses recent progress achieved in various areas to enhance acceptance of this canister not only by the DOE complex but also fabricators and regulatory agencies

  4. Regulatory practices and safety standards for nuclear power plants

    International Nuclear Information System (INIS)

    1989-01-01

    The International Symposium on Regulatory Practices and Safety Standards for Nuclear Power Plants was jointly organized by the International Atomic Energy Agency (IAEA), for Nuclear Energy Agency of the OECD and the Government of the Federal Republic of Germany with the objective of providing an international forum for the exchange of information on regulatory practices and safety standards for nuclear power plants. The Symposium was held in Munich, Federal Republic of Germany, from 7 to 10 November 1988. It was attended by 201 experts from some 32 Member States and 4 international organizations. Fifty-one papers from 19 Member States and 2 international organizations were presented and discussed in 5 technical sessions covering the following subjects: National Regulatory Practices and Safety Standards (14 papers); Implementation of Regulatory Practices - Technical Issues (8 papers); Implementation of Regulatory Practices - Operational Aspects (8 papers); Developments and Trends in Safety Standards and Practices (11 papers); International Aspects (10 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  5. Nuclear Astrophysics from View Point of Few-Body Problems

    International Nuclear Information System (INIS)

    Tumino, A.; Spitaleri, C.; Bertulani, C.; Mukhamedzhanov, A.M.

    2013-01-01

    Few-body systems provide very useful tools to solve different problems for nuclear astrophysics. This is the case of indirect techniques, developed to overcome some of the limits of direct measurements at astrophysical energies. Here the Coulomb dissociation, the asymptotic normalization coefficient and the Trojan Horse method are discussed. (author)

  6. Standard reference and other important nuclear data by the Cross Section Evaluation Working Group

    International Nuclear Information System (INIS)

    1979-12-01

    This report is a current review of the status of standard reference and other important nuclear data pointing out data discrepancies, recommending new measurements, and comparing the current version of ENDF/B with data. Neutron reactions with 1 H, 3 H, 6 Li, 10 B, 12 C, 59 Co, 80 Kr, 136 Xe, 153 Eu, and 197 Au are included, along with reaction and other data for the actinide nuclei. Cross sections, spectra, etc., are given for some of the nuclides considered

  7. Standard rules for liability and cover for nuclear installations

    International Nuclear Information System (INIS)

    Pfaffelhuber, J.K.; Kuckuck, B.

    1980-01-01

    To afford full protection for possible victims, the authors of this article are in favour of doing away with the limitation of liability of nuclear operators presently provided under the German Atomic Energy Act, the principle of which is based on the Paris Convention and the Brussels Supplementary Convention. In support of this argument reference is made to the recent accident at Three Mile Island, trends in other national legislation towards unlimited liability as well as high safety standards in German nuclear plants. Finally, possible ways of providing unlimited liability are proposed, in particular increased insurance cover and the constitution of an interest-bearing fund in addition to State intervention in case of a major nuclear incident. (NEA) [fr

  8. A complete analysis of a nuclear building to nuclear safety standards

    International Nuclear Information System (INIS)

    Bergeretto, G.; Giuliano, V.; Lazzeri, L.

    1975-01-01

    The nuclear standards impose on the designer the necessity of examining the loads, stresses and strains in a nuclear building even under extreme loading conditions, both due to plant malfunctions and environmental accidents. It is necessary then to generate, combine and examine a tremendous amount of data; really the lack of symmetry and general complication of the structures and the large number of loading combinations make an automatic analysis quite necessary. A largely automatized procedure is presented in view of solving the problem by a series of computer programs linked together as follows. After the seismic analysis has been performed by (SADE CODE) these data together with the data coming from thermal specifications, weight, accident descriptions etc. are fed into a finite element computer code (SAP4) for analysis. They are processed and combined by a computer code (COMBIN) according to the loading conditions (the usual list in Italy is given and briefly discussed), so that for each point (or each selected zone) under each loading condition the applied loads are listed. These data are fed to another computer code (DTP), which determines the amount of reinforcing bars necessary to accommodate the most severe of the loading conditions. The Aci 318/71 and Italian regulation procedures are followed; the characteristics of the program are briefly described and discussed. Some particular problems are discussed, e.g. the thermal stresses due to normal and accident conditions, the inelastic behavior of some frame elements (due to concrete cracking) is considered by means of an 'ad hoc' code. Typical examples are presented and the results are discussed showing a relatively large benefit in considering this inelastic effect

  9. Standardization of Administered Activities in Pediatric Nuclear Medicine: A Report of the First Nuclear Medicine Global Initiative Project, Part 2-Current Standards and the Path Toward Global Standardization.

    Science.gov (United States)

    Fahey, Frederic H; Bom, Henry Hee-Seung; Chiti, Arturo; Choi, Yun Young; Huang, Gang; Lassmann, Michael; Laurin, Norman; Mut, Fernando; Nuñez-Miller, Rodolfo; O'Keeffe, Darin; Pradhan, Prasanta; Scott, Andrew M; Song, Shaoli; Soni, Nischal; Uchiyama, Mayuki; Vargas, Luis

    2016-07-01

    The Nuclear Medicine Global Initiative (NMGI) was formed in 2012 and consists of 13 international organizations with direct involvement in nuclear medicine. The underlying objectives of the NMGI are to promote human health by advancing the field of nuclear medicine and molecular imaging, encourage global collaboration in education, and harmonize procedure guidelines and other policies that ultimately lead to improvements in quality and safety in the field throughout the world. For its first project, the NMGI decided to consider the issues involved in the standardization of administered activities in pediatric nuclear medicine. It was decided to divide the final report of this project into 2 parts. Part 1 was published in this journal in the spring of 2015. This article presents part 2 of the final report. It discusses current standards for administered activities in children and adolescents that have been developed by various professional organizations. It also presents an evaluation of the current practice of pediatric nuclear medicine specifically with regard to administered activities as determined by an international survey of 313 nuclear medicine clinics and centers from 29 countries. Lastly, it provides recommendations for a path toward global standardization of the administration of radiopharmaceuticals in children. © 2016 by the Society of Nuclear Medicine and Molecular Imaging, Inc.

  10. Harmonization of nuclear codes and standards, pacific nuclear council working and task group report

    International Nuclear Information System (INIS)

    Dua, S.S.

    2006-01-01

    Full text: The codes and standards, both at the national and international level, have had a major impact on the industry worldwide and served it well in maintaining the performance and safety of the nuclear reactors and facilities. The codes and standards, in general, are consensus documents and do seek public input at various levels before they are finalized and rolled out for use by the nuclear vendors, consultants, utilities and regulatory bodies. However, the extensive development of prescriptive national standards if unchecked against the global environment and trade agreements (NAFTA, WTO, etc.) can also become barriers and cause difficulties to compete in the world market. During the last decade, the national and international writing standards writing bodies have recognized these issues and are moving more towards the rationalization and harmonization of their standards with the more widely accepted generic standards. The Pacific Nuclear Council (PNC) recognized the need for harmonization of the nuclear codes and standards for its member countries and formed a Task Group to achieve its objectives. The Task Group has a number of members from the PNC member countries. In 2005 PNC further raised the importance of this activity and formed a Working Group to cover a broader scope. The Working Group (WG) mandate is to identify and analyze the different codes and standards introduced to the Pacific Basin region, in order to achieve mutual understanding, harmonization and application in each country. This o requires the WG to develop and encourage the use of reasonably consistent criteria for the design and development, engineering, procurement, fabrication, construction, testing, operations, maintenance, waste management, decommissioning and the management of the commercial nuclear power plants in the Pacific Basin so as to: Promote consistent safety, quality, environmental and management standards for nuclear energy and other peaceful applications of nuclear

  11. ASME Section XI trends in developing nuclear codes and standards

    International Nuclear Information System (INIS)

    Hedden, O.F.

    1995-01-01

    When the author began working on nuclear power many years ago, he knew that perfection was the only acceptable technical standard. Unfortunately, this became an obsession with perfection that has had unfavorable consequences in some of the non-technical areas of work in ASME nuclear power Codes and Standards. However, the economic problems of the nuclear power industry now demand a more pragmatic approach if the industry is to continue. Not only does each item considered for action need to be evaluated to criteria that may in some cases be less than perfection, but one needs to consider whether it contributes tangibly to either safety or to reduction in technical or administrative burden. These should be the governing, criteria. The introduction of risk-based inspection methodologies will certainly be an important element in doing this successfully. One needs to consider these criteria collectively, as one discusses each item at the committee level, and individually, as one votes on each item. In the past, the author has been concerned that the industry was not acting quickly enough in taking advantage of opportunities offered by the Code to increase safety or to reduce cost. While he still has some concern, he thinks communication channels have been greatly improved. Now he is becoming more concerned with both the collective and individual actions that delay beneficial changes. The second part of the author's talk has to do with the relevance of the code committees in the nuclear power industry regulatory process

  12. Harmonization of nuclear codes and standards. Pacific nuclear council working and task group report

    International Nuclear Information System (INIS)

    Dua, Shami

    2008-01-01

    Nuclear codes and standards have been an integral part of the nuclear industry since its inception. As the industry came into the main stream over the 2nd half of the 20th century, a number of national and international standards were developed to support a specific nuclear reactor concept. These codes and standards have been a key component of the industry to maintain its focus on nuclear safety, reliability and quality. Both national and international standards have served the industry well in obtaining public, shareholder and regulatory acceptance. The existing suite of national and international standards is required to support the emerging nuclear renaissance. However as noted above under Pacific Nuclear Council (PNC), Manufacturing Design Evaluation Program (MDEP) and SMiRT discussions, the time has come now for the codes and standards writing bodies and the industry to take the next step to examine the relevance of existing suite in view of current needs and challenges. This review must account for the changing global environment including global supply chain and regulatory framework, resources, deregulation, free trade, and industry need for competitiveness and performance excellence. The Task Group (TG) has made limited progress in this review period as no additional information on the listing of codes and standards have been received from the members. However, TG Chair has been successful in obtaining considerable interest from some additional individuals from the member countries. It is important that PNC management seek additional participation from the member countries and asks for their active engagement in the Working Group (WG) TG activities to achieve its mandate and deliverables. The harmonization of codes and standards is a key area for the emerging nuclear renaissance and as noted by a number of international organizations (refer to MDEP action noted above) that these tasks can not be completed unless we have the right level of resources and

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  14. Fundaments for creation of national radiation protection standard for nuclear gauges

    International Nuclear Information System (INIS)

    Ferreira, Luiz Cavalcante

    2016-01-01

    The present work It aims to provide fundaments for the creation of a national standard of practice, safety and responsible use of nuclear gauges in accordance with the recommendations already existing national and international. The work deals with the protection against ionizing radiation, an outline of a proposal for a standard that discriminates in its articles and paragraphs, the basic principles of a proposal for a standard that discriminates in its articles and paragraphs, the basic principles of safety and security, and some pointes that are also relevant such as the responsibilities of those involved in acquisition and nuclear gauge operation, storage, maintenance, testing and emergency situations. The result is to provide a means to limit the dose of operators and people from the public and maintain these limits within the recommended by CNEN, reducing exposure do ionizing radiation, and having greater control in operating the equipment. (author)

  15. 76 FR 73721 - Nine Mile Point Nuclear Station, LLC, Nine Mile Point Nuclear Station, Unit No. 2, Environmental...

    Science.gov (United States)

    2011-11-29

    ... without modification. Therefore, the impact from the increased volume of solid radioactive waste generated... environmental effects generated from activities at NMP2. Environmental Justice Impact Analysis The NRC staff.... Radiological Impacts Radioactive Gaseous and Liquid Effluents, Direct Radiation Shine, and Solid Waste Nuclear...

  16. 75 FR 13600 - Nine Mile Point Nuclear Station, LLC, Nine Mile Point Nuclear Station, Unit No. 2; Draft...

    Science.gov (United States)

    2010-03-22

    ... modification. Therefore, the impact from the increased volume of solid radioactive waste generated under... health and environmental effects generated from activities at NMP2. Environmental Justice Impact Analysis.... Radiological Impacts Radioactive Gaseous and Liquid Effluents, Direct Radiation Shine, and Solid Waste Nuclear...

  17. The FEROL40, a microTCA card interfacing custom point-to-point links and standard TCP/IP

    CERN Document Server

    Gigi, Dominique; Behrens, Ulf; Branson, James; Chaze, Olivier; Cittolin, Sergio; Contescu, Cristian; da Silva Gomes, Diego; Darlea, Georgiana-Lavinia; Deldicque, Christian; Demiragli, Zeynep; Dobson, Marc; Doualot, Nicolas; Erhan, Samim; Fulcher, Jonathan Richard; Gladki, Maciej; Glege, Frank; Gomez-Ceballos, Guillelmo; Hegeman, Jeroen; Holzner, Andre; Janulis, Mindaugas; Lettrich, Michael; Meijers, Frans; Meschi, Emilio; Mommsen, Remigius K; Morovic, Srecko; O'Dell, Vivian; Orn, Samuel Johan; Orsini, Luciano; Papakrivopoulos, Ioannis; Paus, Christoph; Petrova, Petia; Petrucci, Andrea; Pieri, Marco; Rabady, Dinyar; Racz, Attila; Reis, Thomas; Sakulin, Hannes; Schwick, Christoph; Simelevicius, Dainius; Vazquez Velez, Cristina; Vougioukas, Michail; Zejdl, Petr

    2017-01-01

    In order to accommodate new back-end electronics of upgraded CMS sub-detectors, a new FEROL40 card in the microTCA standard has been developed. The main function of the FEROL40 is to acquire event data over multiple point-to-point serial optical links, provide buffering, perform protocol conversion, and transmit multiple TCP/IP streams (4x10Gbps) to the Ethernet network of the aggregation layer of the CMS DAQ (data acquisition) event builder. This contribution discusses the design of the FEROL40 and experience from operation.

  18. Update to nuclear data standards for nuclear measurements. Summary report of a consultants' meeting

    International Nuclear Information System (INIS)

    Wienke, H.; Chiba, S.; Hambsch, F.J.; Olsson, N.; Smirnov, A.N.

    1997-05-01

    This document is an update of the 1991 NEANDC/INDC Nuclear Standards File (INDC(SEC)-101) to indicate the status and extension of cross section standards for the 10 B(n,α) reaction in the energy region below 20 Mev; and the H(n,n), 235 U9(n,f), 238 U(n,f), and 209 Bi(n,f) reactions for selected energy regions above 20 Mev. Refs, figs, tabs

  19. Shell closure at the touching point of nuclear fragments

    International Nuclear Information System (INIS)

    Poenaru, D.N.; Greiner, W.; Gherghescu, R.A.

    1998-01-01

    Shell correction energy of the fission fragments remains practically unchanged when the separation distance increases from the sum of their radii up to infinity. The variation with mass asymmetry of the total deformation energy at the touching point configuration shows the valleys corresponding to different decay modes, which are produced when the two proton and/or the two neutron numbers are magic or almost magic. We present a contour plot of the deformation energy of the proton-rich α-emitter 106 Te, showing for the first time the α-decay valley. Different valleys mainly due to the doubly magic nuclei 100,132 Sn, 208 Pb, and other magic numbers, are illustrated by plotting the deformation energy at the touching point versus the proton number of the fragment, for the following parent nuclei: 106 Te; 116 Ce; 212 Po; 228 Th; 258 Fm, and 264 Fm. (author). Letter-to-the-editor

  20. Standardized System of Nuclear Safety Information for the Promotion of Transparency and Openness

    International Nuclear Information System (INIS)

    Lee, Gihyung; Kim, Sanghyun; Lee, Gyehwi; Yoon, Yeonhwa; Song, Song Hyerim; Jeong, Jina; Byun, Jaehyung; Seo, Jonghwan

    2013-01-01

    There has been an increasing emphasis on the need for increased disclosure of information through the home page of the Korea Institute of Nuclear Safety (KINS), responsible for nuclear safety regulations, and the Nuclear Safety Information Center (NSIC) to enhance public understanding of nuclear safety. However, due to the dazzled structure of the existing KINS and NSIC home pages, improvements in accessibility and convenience are necessary. At the same time, content standardization is required to increase operational efficiency and provide coherent information. In this study, the Delphi method was used to select the major contents to make available on the home page as well as the main user base definition for the home page layout development. Also, internal and external expert groups were created to conduct AHP (Analytic Hierarchy Process) analysis and develop the comparative analysis items for the U. S. Nuclear Regulatory Commission(NRC)/KINS/NSIC home pages. Afterwards, problems and points of improvements for the home page system, design, and profile were derived using heuristic analysis. The implications arising from the Delphi analysis results were applied to the home page layout. In the nuclear safety information standardized system construction process, the comparative analysis conducted using the AHP and heuristic analyses of the NRC home page resulted in deriving improvements for the Guidance, Organization, and Trustworthy items of the KINS/NSIC home page. Furthermore, through the Delphi analysis, a clear purpose and core values were set for the KINS web site, and the needs of the main user base were identified. By developing the home page layout, user interest and utility were raised to improve the organization method and layout. Through this study, KINS was able to construct a nuclear safety information standardized system and increase transparency and openness by providing feature enhancements in information provision as well as user accessibility and

  1. The necessity of exploitation of nuclear energy in China from the environmental protection point of view

    International Nuclear Information System (INIS)

    Pan Ziqiang; Jiang Xiwen; Song Shaoyi; Liu Shutian; Bai Guang

    1984-01-01

    The article proves the necessity of development of nuclear energy in China from the enviromental protection point of view. The development of nuclear energy would be decrease environmental contamination due to energy power production. The prediction of collective dose equivalent commitment from the nuclear power plant in year 2000 would only amount to 0.013% of annual collective dose equivalent from natural radiation sources

  2. Standardized safety management of AP1000 nuclear power plant

    International Nuclear Information System (INIS)

    Li Xingwen; Cao Zhiqiang; Cong Jiuyuan

    2011-01-01

    In 2002, China published and implemented the Law of the People's Republic of China on Work Safety and promulgated a series of guidelines and policies, which strengthened the safety management supervision. Standardization of safety, as another important step on safety supervision, comes after safety assesment and safety production licensing system, is also a permanent solution. Standardization of safety is a strategic, long term and fundamental work, which is also the basic access to achieving scientific safety management and increasing the inherent safety of an enterprise. Haiyang AP1000 nuclear power plant, adopting the modularized, 'open-top' and parallel construction means, overturned the traditional construction theory of installation work comes after the civil work and greatly shorten the construction period. At the same time, the notable increase of oversize module transportation and lifting and parallel construction raises higher demands for safety management. This article combines the characteristics and difficulties of safety management for Haiyang AP1000 nuclear power plant, puts forward ideas and methods for standardized safety management, and could also serve as reference to the safety management for other AP1000 projects. (authors)

  3. Comparison of ISO 9000 and recent software life cycle standards to nuclear regulatory review guidance

    Energy Technology Data Exchange (ETDEWEB)

    Preckshot, G.G.; Scott, J.A.

    1998-01-20

    Lawrence Livermore National Laboratory is assisting the Nuclear Regulatory Commission with the assessment of certain quality and software life cycle standards to determine whether additional guidance for the U.S. nuclear regulatory context should be derived from the standards. This report describes the nature of the standards and compares the guidance of the standards to that of the recently updated Standard Review Plan.

  4. Comparison of ISO 9000 and recent software life cycle standards to nuclear regulatory review guidance

    International Nuclear Information System (INIS)

    Preckshot, G.G.; Scott, J.A.

    1998-01-01

    Lawrence Livermore National Laboratory is assisting the Nuclear Regulatory Commission with the assessment of certain quality and software life cycle standards to determine whether additional guidance for the U.S. nuclear regulatory context should be derived from the standards. This report describes the nature of the standards and compares the guidance of the standards to that of the recently updated Standard Review Plan

  5. Nuclear Regulatory Commission and its role in environmental standards

    International Nuclear Information System (INIS)

    Mattson, R.J.

    1976-01-01

    The NRC and its predecessors in the Atomic Energy Commission represent considerable experience in environmental standards setting. The Atomic Energy Act of 1954, the 1970 Supreme Court decision on Federal pre-emption of radiation standards, the Calvert Cliffs decision of 1971, the Energy Reorganization Act of 1974, and the Appendix I ''as low as reasonably achievable'' decision of 1975, to name a few of our landmarks, are representative of the scars and the achievements of being in a role of national leadership in radiation protection. The NRC, through a variety of legislative authorities, administrative regulations, regulatory guides, and national consensus standards regulates the commercial applications of nuclear energy. The purposes of regulation are the protection of the environment, public health and safety, and national security. To understand NRC's responsibilities relative to those of other Federal and state agencies concerned with environmental protection, we will briefly review the legislative authorities which underlie our regulatory program. Then we will examine the intent or the spirit of that program as embodied in our system of regulations, guides, and standards. Finally we will speak to what's happening today and what we see in the future for environmental standards

  6. Advanced passive technology: A global standard for nuclear plant requirements

    International Nuclear Information System (INIS)

    Novak, V.

    1994-01-01

    Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy' (DOE). The preliminary design was cornpleved in 1989. AP6OO's Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance

  7. SiC-CMC-Zircaloy-4 Nuclear Fuel Cladding Performance during 4-Point Tubular Bend Testing

    Energy Technology Data Exchange (ETDEWEB)

    IJ van Rooyen; WR Lloyd; TL Trowbridge; SR Novascone; KM Wendt; SM Bragg-Sitton

    2013-09-01

    The U.S. Department of Energy Office of Nuclear Energy (DOE NE) established the Light Water Reactor Sustainability (LWRS) program to develop technologies and other solutions to improve the reliability, sustain the safety, and extend the life of current reactors. The Advanced LWR Nuclear Fuel Development Pathway in the LWRS program encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. Recent investigations of potential options for “accident tolerant” nuclear fuel systems point to the potential benefits of silicon carbide (SiC) cladding. One of the proposed SiC-based fuel cladding designs being investigated incorporates a SiC ceramic matrix composite (CMC) as a structural material supplementing an internal Zircaloy-4 (Zr-4) liner tube, referred to as the hybrid clad design. Characterization of the advanced cladding designs will include a number of out-of-pile (nonnuclear) tests, followed by in-pile irradiation testing of the most promising designs. One of the out-of-pile characterization tests provides measurement of the mechanical properties of the cladding tube using four point bend testing. Although the material properties of the different subsystems (materials) will be determined separately, in this paper we present results of 4-point bending tests performed on fully assembled hybrid cladding tube mock-ups, an assembled Zr-4 cladding tube mock-up as a standard and initial testing results on bare SiC-CMC sleeves to assist in defining design parameters. The hybrid mock-up samples incorporated SiC-CMC sleeves fabricated with 7 polymer impregnation and pyrolysis (PIP) cycles. To provide comparative information; both 1- and 2-ply braided SiC-CMC sleeves were used in this development study. Preliminary stress simulations were performed using the BISON nuclear fuel performance code to show the stress distribution differences for varying lengths between loading points

  8. Standard specification for nuclear-grade boron carbide powder

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This specification defines the chemical and physical requirements for boron carbide powder intended for a variety of nuclear applications. Because each application has a different need for impurity and boron requirements, three different chemical compositions of powder are specified. In using this specification, it is necessary to dictate which type of powder is intended to be used. In general, the intended applications for the various powder types are as follows: 1.1.1 Type 1—For use as particulate material in nuclear reactor core applications. 1.1.2 Type 2—Powder that will be further processed into a fabricated shape for use in a nuclear reactor core or used in non-core applications when the powder directly or indirectly may cause adverse effects on structural components, such as halide stress corrosion of stainless steel. 1.1.3 Type 3—Powder that will be used for non-core applications or special in-core applications. 1.2 The values stated in SI units are to be regarded as standard. No other ...

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

    International Nuclear Information System (INIS)

    2006-03-01

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

  10. Method of nuclear reactor control using a variable temperature load dependent set point

    International Nuclear Information System (INIS)

    Kelly, J.J.; Rambo, G.E.

    1982-01-01

    A method and apparatus for controlling a nuclear reactor in response to a variable average reactor coolant temperature set point is disclosed. The set point is dependent upon percent of full power load demand. A manually-actuated ''droop mode'' of control is provided whereby the reactor coolant temperature is allowed to drop below the set point temperature a predetermined amount wherein the control is switched from reactor control rods exclusively to feedwater flow

  11. Los Alamos National Laboratory standard nuclear material container

    Energy Technology Data Exchange (ETDEWEB)

    Stone, Timothy A [Los Alamos National Laboratory

    2009-01-01

    The shut down of United States (U.S.) nuclear-weapons production activities in the early 1990s left large quantities of nuclear materials throughout the U.S. Department of Energy (DOE) complex in forms not intended for long-term storage. In May 1994, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 94-1, which called for the stabilization and disposition of 'thousands of containers of plutonium-bearing liquids and solids' in the DOE complex, including LANL in the nuclear-weapons-manufacturing pipeline when manufacturing ended. This resulted in the development of the 3013 standard with container requirements for long term storage (up to 50 years). A follow on was the Criteria For Interim Storage of Plutonium Bearing Materials, Charles B. Curtis, in 1996 to address storage other than the 3013 standard for shorter time frames. In January 2000, the DNFSB issued Recommendation 2000-1, which stated the need for LANL to repackage 'about one ton of plutonium metal and oxide,' declared excess to Defense Program (DP) needs. The DNFSB recommended that LANL 'stabilize and seal within welded containers with an inert atmosphere the plutonium oxides ... which are not yet in states conforming to the long-term storage envisaged by DOE-STD-3013,' and that they '... enclose existing and newly-generated legacy plutonium metal in sealed containers with an inert atmosphere,' and 'remediate and/or safely store the various residues.' Recommendation 2000-1, while adding to the number of items needing remediation, also reiterated the need to address remaining items from 1994-1 in a timely fashion. Since timetables slipped, the DNFSB recommended that the Complex 'prioritize and schedule tasks according to the consideration of risks.' In March 2005, the DNFSB issued Recommendation 2005-1. This recommendation addresses the need for a consistent set of criteria across the DOE complex for the interim storage of

  12. 78 FR 52987 - Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit 3

    Science.gov (United States)

    2013-08-27

    ... concludes that the proposed action will not have a significant effect on the quality of the human... Commission. Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor...

  13. Nuclear microprobe analysis of the standard reference materials

    International Nuclear Information System (INIS)

    Jaksic, M.; Fazinic, S.; Bogdanovic, I.; Tadic, T.

    2002-01-01

    Most of the presently existing Standard Reference Materials (SRM) for nuclear analytical methods are certified for the analyzed mass of the order of few hundred mg. Typical mass of sample which is analyzed by PIXE or XRF methods is very often below 1 mg. By the development of focused proton or x-ray beams, masses which can be typically analyzed go down to μg or even ng level. It is difficult to make biological or environmental SRMs which can give desired homogeneity at such low scale. However, use of fundamental parameter quantitative evaluation procedures (absolute method), minimize needs for SRMs. In PIXE and micro PIXE setup at our Institute, fundamental parameter approach is used. For exact calibration of the quantitative analysis procedure just one standard sample is needed. In our case glass standards which showed homogeneity down to micron scale were used. Of course, it is desirable to use SRMs for quality assurance, and therefore need for homogenous materials can be justified even for micro PIXE method. In this presentation, brief overview of PIXE setup calibration is given, along with some recent results of tests of several SRMs

  14. Application of Pressure Equipment Standard at nuclear power plants; Aplicacion del Reglamento de Equipos a Presion a las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Mostaza, J. M.

    2011-07-01

    Regarding with the paper presented on 9{sup t}h June 2011 referred to the Industrial Security standard in Nuclear Plants, it was about the application of Pressure Equipment standard to mentioned Nuclear Plants, this article is an extract of the paper going to be exposed. (Author)

  15. 76 FR 14437 - Economic Simplified Boiling Water Reactor Standard Design: GE Hitachi Nuclear Energy; Issuance of...

    Science.gov (United States)

    2011-03-16

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0055] Economic Simplified Boiling Water Reactor Standard Design: GE Hitachi Nuclear Energy; Issuance of Final Design Approval The U.S. Nuclear Regulatory Commission has issued a final design approval (FDA) to GE Hitachi Nuclear Energy (GEH) for the economic...

  16. View points on a not well known law, the nuclear law

    International Nuclear Information System (INIS)

    Arbousset, Herve; Lahorgue, Marie-Beatrice; Rambour, Muriel; Schellenberger, Thomas

    2018-01-01

    While indicating the relevant French decrees and laws which have been building up what can be called the nuclear law, this article first proposes a discussed overview of the evolution of this law between a decree published in 1963 and the law on energy transition, while noticing what went in the USA in this respect. Based on the example of the project of geological storage of nuclear wastes, the authors outline that this nuclear law is evolving out of standards as it is evolves in order to fit with the project, and not the other way. Therefore democratic anchoring is rather fragile. The author outlines the influence of new threats related to terrorism and their influence on the nuclear law. They also comment the issue of compensation for victims of French nuclear tests in Algeria and in French Polynesia, and notice that hope has been followed by disillusion and questions

  17. STANDARDIZATION OF CUPPING THERAPY POINTS AND MECHANISM OF ACTION IN THE LIGHT OF SCIENCE

    OpenAIRE

    Dr. Izharul Hasan

    2018-01-01

    Now a day’s cupping therapy is an established therapeutic modality among Indian system of medicine as well as worldwide. Inspite of that, standard operative procedure (SOPs) for cupping therapy is yet to develop. In this paper author comprises the possible indications of cupping therapy along with procedures, application points, safety concerns, historical perspective, surgical operative standards described in traditional system of medicine as well as in the light of science. Cupping may be d...

  18. Licensing procedure, nuclear codes and standards in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Schultheiss, G.F.

    1980-01-01

    The present paper deals with legal background of licensing in nuclear technology and atomic energy use, licensing procedures for nuclear power plants and with codes, standards and guidelines in the Federal Republic of Germany. (orig./RW)

  19. Quality as an element of nuclear safety; considerations from the point of view of the authorities

    International Nuclear Information System (INIS)

    Weehuizen, F.

    1992-01-01

    After introductory considerations on the terms 'Quality' and 'Quality Assurance' as well as on the significance of quality for nuclear safety, the definition of quality requirements and evidence of meeting them form the first major points. Several points concerning the maintenance of quality in a power station are followed by details of the duties and requirements of the safety authorities. The conclusion of the paper is taken up by several thoughts on safety culture, some of them of a personal nature. 20 refs

  20. Principles and foundation: national standards on quantities and units in nuclear science field

    International Nuclear Information System (INIS)

    Chen Lishu

    1993-11-01

    The main contents of National Standards on Quantities and units of atomic and nuclear physics (GB 3102.9) and Quantities and Units of nuclear reactions and ionizing radiations (GB 310.10) are presented in which most important quantities with their symbols and definitions in the nuclear scientific field are given. The principles and foundation, including the International System of Units (SI) and its application to the nuclear scientific field, in the setting of the National Standards are explained

  1. The status and prospects of the development of nuclear industries codes and standards in Korea

    International Nuclear Information System (INIS)

    Kim Namha; Kyoo Kun Koh; Chan Kun Lee

    1994-01-01

    Since the late 1980s, self-reliance program for nuclear technology development has been pursued by the Korean nuclear industry, and local entities have been charged with the design, manufacturing, and construction of nuclear power plants. Accordingly, the development of suitable codes and standards for the nuclear industry was initiated. The conceptual picture of the nuclear industry's codes and standards is reviewed in relation to the current prevailing legal structure. Then a phase-by-phase development program for codes and standards is described in detail. 4 refs., 2 tabs., 2 figs

  2. "Nuclear" medicine physicians as communicators: their point of view on the aftermath of "nuclear" disaster.

    Science.gov (United States)

    Staudenherz, Anton; Sinzinger, Helmut

    2012-02-01

    On March 11th, 2011 earthquakes and a subsequent tsunami devastated northern Japan. The consecutive technical catastrophe in the Fukushima Daiichi nuclear power plant was not only an additional local tragedy, it also turned out to be a global disaster. In this review we intend to discuss emerging problems and enlighten a way to communicate in such events, tell people how to react in such scenarios and prevent panic by providing rational information.

  3. Matrix solution of point kinetic equation in a fluidized bed nuclear reactor

    International Nuclear Information System (INIS)

    Vilhena, M.T. de; Claeyssen, J.R.

    1990-01-01

    The purpose of this work is to solve the point kinetic equation for a Fluidized Bed Nuclear Reactor by matrix series formulation, showing it is a simple and accurate method, observing this is a scale problem of Stiff type for small time. (author)

  4. Managing medical treatment waste and effluent: the point of view of a nuclear medicine practitioner

    International Nuclear Information System (INIS)

    Karcher, G.

    2011-01-01

    The nuclear medicine department of the Nancy CHU hospital is one of the largest in France: 16.000 patients are welcomed each year and 4.000 persons undergo a tomography there. 5 shielded and isolated rooms, dedicated to Iodine 131 treatment, allow the care of 150 to 200 patients each year. The head of the nuclear medicine department gives his meaning about the new regulation on the management of radioactive effluents. According to him, regulations are necessary but the values of the imposed thresholds have to be scientifically justified. Another point is that a lot of money is spent on radiation protection issues while the radioactive risks are almost null, which leads to wasting money. The elaboration of the radioprotection regulations must be made not as a whole but on a specific basis according to the domain: nuclear power plants, research reactors or nuclear medicine, it applies. (A.C.)

  5. A preliminary study on the design in architecture of nuclear and radiation safety standard system

    International Nuclear Information System (INIS)

    Song Dahu; Zhang Chi; Yang Lili; Li Bin; Liu Yingwei; An Hongzhen; Gao Siyi; Liu Ting; Meng De

    2014-01-01

    The connotation and function of nuclear and radiation safety standards are analyzed, and their relationships with the relevant laws and regulations are discussed in the paper. Some suggestions and blue print of overall architecture to build nuclear and radiation safety standard system are proposed, on the basis of researching the application status quo, existing problems and needs for nuclear and radiation safety standards in China. This work is a beneficial exploration and attempt to establish China's nuclear and radiation safety standards. (authors)

  6. Standard of Nuclear Medicine Protocols. The 3rd revision, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    This document is designed to provide `Standard of Nuclear Medicine Protocols` revised in 1994. The present revision is aimed at providing new imaging agents (e.g, Tc-99m-HMPAO, Tc-99m-ECD, Tc-99m-technegas, Tc-99m MIBI, Tc-99m-tetrofosmin, I-123-BMIPP, and I-123-MIBG) and at introducing new application of conventional imaging agents. The descriptions are given under two sections: (I) standardization of imaging and (II) protocols for imaging of various organs. Section I covers static imaging, dynamic imaging, radioisotope angiography, SPECT, and collimators. In Section II, various imaging procedures are described as follows: (1) brain imaging, (2) brain perfusion imaging, (3) cistern imaging, (4) thyroid imaging, (5) imaging for metastatic foci from thyroid carcinoma, (6) parathyroid imaging, (7) lung perfusion imaging, (8) lung inhalation imaging, (9) lung ventilation imaging, (10) myocardial imaging, (11) myocardial metabolism imaging, (12) myocardial sympathetic functional imaging, (13) imaging for acute myocardial infarction, (14) blood pool imaging of the cardiac aorta, (15) RI venography, (16) hepato-splenic imaging, (17) hepato-biliary imaging, (18) imaging for the hepatic receptor, (19) hepatic RI angiography, (20) measurement of the portal-systemic shunt, (21) splenic imaging, (22) renal imaging, (23) vesicoureteral reflux imaging, (24) adrenal cortex imaging, (25) adrenal medulla imaging, (26) bone imaging, (27) bone joint imaging, (28) bone marrow imaging, (29) tumor imaging, (30) inflammatory imaging, (31) indium-labeled blood platelet imaging, (32) salivary imaging, (33) imaging of the Meckel`s diverticulum and ectopic gastric mucosa, (34) lymph node imaging, (35) lymphatic imaging, (36) imaging of the gastrointestinal hemorrhage, (37) testiclar imaging, (38) abdominal imaging, and (39) gastrointestinal movement imaging. (N.K.).

  7. Will nuclear power plant standardization reduce the licensing impact on construction

    International Nuclear Information System (INIS)

    Allen, J.M.; Bingham, W.G.; Keith, D.G.

    1976-01-01

    The NRC and the nuclear industry have been pursuing standardization quite vigorously in an effort to reduce the cost and schedule for the design and construction of nuclear power plants. The NRC is currently reviewing standard plant applications submitted under each of four standardization options. In addition, the NRC has published Standard Review Plans and Standard Technical Specifications. Although problems exist in the implementation of standardization and in areas unaffected by standardization, each of these standardization methods has the potential to reduce the licensing impact on construction

  8. Legal status of minister's notices and technology standards of 'Korea institute of nuclear safety'(KINS) to regulate nuclear safety

    International Nuclear Information System (INIS)

    Jung, S. K.; Jung, M. M.; Kim, S. W.; Jang, K. H.; Oh, B. J.

    2003-01-01

    Concerning nuclear safety or technology standards, each of 'notices' issued by minister of science and technology(MOST) empowered by law of its regulation is obviously forceful as a law, if not all. But the standards made by the chief of Korea institute of nuclear safety(KINS) to meet the tasks entrusted to KINS by MOST is only conditionally forceful as a law, that is, on the condition that law or regulation empowered the chief of KINS to make nuclear safety and/or technology standards

  9. AP1000 - the new standard for nuclear power

    International Nuclear Information System (INIS)

    Lipman, Daniel S.

    2006-01-01

    Full text of publication follows: The AP1000 is the only Generation III+ reactor to receive Final Design Approval (FDA) from the Nuclear Regulatory Commission, and is expected to receive its Design Certification by the end of the year. Building on the proven features of current generation nuclear plants, the AP1000 combines experience with innovation into a design that surpasses current standards of safety and reliability. Use of passive safety features results in a simpler and more compact design that enhances safety, simplifies O and M requirements, and reduces capital and operating costs. At 1117 Mwe, the AP1000 is well suited for almost any grid system and will be fully competitive with combined-cycle gas and comparable fossil fuel plants. The AP1000 is ready to help launch a renaissance in new nuclear plant construction throughout the world. Maturity of Design: In excess of 1300 man-years and $400 million in development funding have been expended on the AP1000. It has undergone extensive, part scale testing at the system, sub-system and component level, in addition to a series of part scale integrated tests. The AP1000 is the most analyzed of the next generation reactors. Simplicity of Design/Economics: The AP1000 uses simplified and innovative passive safety systems to an unprecedented extent. Simplified passive safety systems provide reliable operation, reduced capital costs, and enhanced plant safety with large plant operating margins. The AP1000 features improved reliability through simplicity rather than addition of redundant safety trains. This simpler design is easier and less costly to operate and maintain than larger, more complex plants, while less equipment and smaller buildings translate into lower capital costs and shorter construction durations. After construction, economic benefit will be found in reduced operating and maintenance costs, largely due to reduced operating and maintenance staffing requirements. Construction aspects

  10. Measurement standards and the general problem of reference points in chemical analysis

    International Nuclear Information System (INIS)

    Richter, W.; Dube, G.

    2002-01-01

    Besides the measurement standards available in general metrology in the form of the realisations of the units of measurement, measurement standards of chemical composition are needed for the vast field of chemical measurement (measurements of the chemical composition), because it is the main aim of such measurements to quantify non-isolated substances, often in complicated matrices, to which the 'classical' measurement standards and their lower- level derivatives are not directly applicable. At present, material artefacts as well as standard measurement devices serve as chemical measurement standards. These are measurement standards in the full metrological sense only, however, if they are firmly linked to the SI unit in which the composition represented by the standard is expressed. This requirement has the consequence that only a very restricted number of really reliable chemical measurement standards exist at present. Since it is very difficult and time consuming to increase this number substantially and, on the other hand, reliable reference points are increasingly needed for all kinds of chemical measurements, primary methods of measurement and high-level reference measurements will play an increasingly important role for the establishment of worldwide comparability and hence mutual acceptance of chemical measurement results. (author)

  11. Share point 2013 Implementation Strategy for Supporting KM System Requirements in Nuclear Malaysia

    International Nuclear Information System (INIS)

    Mohamad Safuan Sulaiman; Siti Nurbahyah Hamdan; Abdul Muin Abdul Rahman

    2015-01-01

    Knowledge Management system (KMS or KM System) is an important tool for knowledge intensive organization such as Nuclear Malaysia. In June 2010, MS Share Point 2007 was deployed as a tool for KM System in Nuclear Malaysia and was functioning correctly until the end of 2013, whereby the system failed due to software malfunction and inability of the infrastructure to support its continuous operation and usage expansion. This led to difficulties for users to access their operational data and information, hence hampering access to one of the most important tool for KM System in Nuclear Malaysia. However, recently a newer and updated version of the system for example Share point 2013 was deployed to meet the same objectives. Learning from previous failures, the tool has been analyzed at various stages of technical and management reviews. The implementation of this newer version has been designed to overcome most of the deficiencies faced by the older version, both from the software and infrastructure point of views. The tool has performed very well ever since its commissioning from December 2014 till today. As it is still under warranty till March 2016, minimum maintenance issues have been experienced and any problems have been rectified promptly. This paper describes the implementation strategy in preparing the design information of software and hardware architecture of the new tool to overcome the problems of older version, in order to provide a better platform for KM System in Nuclear Malaysia. (author)

  12. American National Standards and the DOE - A cooperative effort to promote nuclear criticality safety

    International Nuclear Information System (INIS)

    Rothleder, B.M.

    1996-01-01

    The U.S. Department of Energy's (DOE's) new criticality safety order, DOE Order 420.1 (open-quotes Facility Safety,close quotes October 13, 1995), Sec. 4.3 (open-quotes Nuclear Criticality Safetyclose quotes), invokes, as an integral part, 12 appropriate American National Standards Institute/American Nuclear Society (ANSI/ANS) Series-8 standards for nuclear criticality safety, but with modifications. (The order that 420.1/4.3 replaced also invoked some ANSI/ANS Series-8 standards.) These modifications include DOE operation-specific exceptions to the standards and elaborations on some of the wording in the standards

  13. Standard map in magnetized relativistic systems: fixed points and regular acceleration.

    Science.gov (United States)

    de Sousa, M C; Steffens, F M; Pakter, R; Rizzato, F B

    2010-08-01

    We investigate the concept of a standard map for the interaction of relativistic particles and electrostatic waves of arbitrary amplitudes, under the action of external magnetic fields. The map is adequate for physical settings where waves and particles interact impulsively, and allows for a series of analytical result to be exactly obtained. Unlike the traditional form of the standard map, the present map is nonlinear in the wave amplitude and displays a series of peculiar properties. Among these properties we discuss the relation involving fixed points of the maps and accelerator regimes.

  14. Criteria, standards and policies regarding decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Detilleux, E.; Lennemann, W.

    1977-01-01

    The paper discusses the decontamination and decommissioning experiences encountered at the Eurochemic fuel reprocessing plant, their implications and the knowledge gained from these experiences. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The conlusions which are presented should weigh heavily in the considerations of the national authorities involved in regulating nuclear power programmes. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who jointly should make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities [fr

  15. 78 FR 37325 - License Renewal of Nuclear Power Plants; Generic Environmental Impact Statement and Standard...

    Science.gov (United States)

    2013-06-20

    ... Nuclear Power Plants; Generic Environmental Impact Statement and Standard Review Plans for Environmental... for Nuclear Power Plants, Supplement 1: Operating License Renewal'' (ESRP). The ESRP serves as a guide... published a final rule, ``Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating...

  16. AECB staff annual assessment of the Point Lepreau Nuclear Generating Station

    International Nuclear Information System (INIS)

    1997-06-01

    The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of reactor safety at the Point Lepreau Generating Station in 1996. Point Lepreau operated safely but the worsening trends in NB Power's safety performance leads to the conclusion that urgent action is required. NB Power is required to report formally to the AECB on progress with measures to improve safety management every six months. Further licensing action will be taken on NB Power if it fails to make the improvements

  17. Numerical simulation of stochastic point kinetic equation in the dynamical system of nuclear reactor

    International Nuclear Information System (INIS)

    Saha Ray, S.

    2012-01-01

    Highlights: ► In this paper stochastic neutron point kinetic equations have been analyzed. ► Euler–Maruyama method and Strong Taylor 1.5 order method have been discussed. ► These methods are applied for the solution of stochastic point kinetic equations. ► Comparison between the results of these methods and others are presented in tables. ► Graphs for neutron and precursor sample paths are also presented. -- Abstract: In the present paper, the numerical approximation methods, applied to efficiently calculate the solution for stochastic point kinetic equations () in nuclear reactor dynamics, are investigated. A system of Itô stochastic differential equations has been analyzed to model the neutron density and the delayed neutron precursors in a point nuclear reactor. The resulting system of Itô stochastic differential equations are solved over each time-step size. The methods are verified by considering different initial conditions, experimental data and over constant reactivities. The computational results indicate that the methods are simple and suitable for solving stochastic point kinetic equations. In this article, a numerical investigation is made in order to observe the random oscillations in neutron and precursor population dynamics in subcritical and critical reactors.

  18. Consistency of the National Realization of Dew-Point Temperature Using Standard Humidity Generators

    Science.gov (United States)

    Benyon, R.; Vicente, T.

    2012-09-01

    The comparison of two high-range standard humidity generators used by Instituto Nacional de Técnica Aeroespacial to realize dew-point temperature in the range from -10 °C to +95 °C has been performed using state-of-the art transfer standards and measurement procedures, over their overlapping range from -10 °C to +75 °C. The aim of this study is to investigate the level of agreement between the two generators, to determine any bias, and to quantify the level of consistency of the two realizations. The measurement procedures adopted to minimize the effect of the influence factors due to the transfer standards are described, and the results are discussed in the context of the declared calibration and measurement capabilities (CMCs).

  19. Nuclear technology transfer via standards: the OMB Circular A-119 in action

    International Nuclear Information System (INIS)

    Zapp, F.C.

    1986-01-01

    The Performance Assurance Project Office (PAPO) has 23 nuclear energy (NE) standards in some phase of conversion to the national consensus standards, and identified three new NE standards for possible conversion. The author describes the methods of developing a consensus for standards through the use of working groups and ballots and the process of adopting a standard. Voluntary NE standards categories cover operation, instrumentation and controls, equipment, programs and procedures, materials, electrical, and structures and building. 4 references, 2 tables

  20. An operational approach to standard nuclear process model (SNPM) and SAP nuclear software implementation at Slovenske Elektrarne

    International Nuclear Information System (INIS)

    Warren, C.C.

    2010-01-01

    Benchmarking efforts in the fall of 2006 showed significant performance gaps in multiple measured processes between the Slovenske Elektrarne (SE) nuclear organization and the highest performing nuclear organizations in the world. While overall performance of the SE nuclear fleet was good and in the second quartile, when compared to the worldwide population of Pressurized Water Reactors (PWR), SE leadership set new goals to improve safety and operational performance to the first decile of the worldwide PWR Fleet. To meet these goals the SE nuclear team initiated a project to identify and implement the Best Practice nuclear processes in multiple areas. The benchmarking process identified the Standard Nuclear Performance Model (SNPM), used in the US nuclear fleet, as the industry best practice process model. The Slovenske Elektrarne nuclear management team used various change management techniques to clearly establish the case for organizational and process change within the nuclear organization. The project organization established by the SE nuclear management team relied heavily on functional line organization personnel to gain early acceptance of the project goals and methods thereby reducing organizational opposition to the significant organizational and process changes. The choice of a standardized process model used, all or in part, by approximately one third of the nuclear industry worldwide greatly facilitated the development and acceptance of the changes. Use of a nuclear proven templated software platform significantly reduced development and testing efforts for the resulting fully integrated solution. In the spring of 2007 SE set in motion a set of initiatives that has resulted in a significant redesign of most processes related to nuclear plant maintenance and continuous improvement. Significant organizational structure changes have been designed and implemented to align the organization to the SNPM processes and programs. The completion of the initial

  1. Standard specification for Nuclear-Grade aluminum oxide powder

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2011-01-01

    1.1 This specification provides the chemical and physical requirements for nuclear-grade aluminum oxide powder intended for fabrication into shapes for nuclear applications. Two specific uses for which this powder is intended are Al2O3 pellets and Al2O 3 − B4C composite pellets for use as thermal insulator or burnable neutron absorbers, respectively. 1.2 The material described herein shall be particulate in nature.

  2. Review of August 1978 changes to the NRC's program for standardization of nuclear power plants

    International Nuclear Information System (INIS)

    Kane, W.F.

    1979-01-01

    The Nuclear Regulatory Commission's (NRC's) standardization program for the licensing of nuclear power plants was initiated in April 1972 and has been used extensively by industry since that time. In June 1977 the NRC directed the staff to undertake a detailed study of the program. As part of that study, the staff was to determine steps that the NRC might take to further encourage standardization. The article discusses the changes made to the standardization program that resulted from that study

  3. Application of the fractional neutron point kinetic equation: Start-up of a nuclear reactor

    International Nuclear Information System (INIS)

    Polo-Labarrios, M.-A.; Espinosa-Paredes, G.

    2012-01-01

    Highlights: ► Neutron density behavior at reactor start up with fractional neutron point kinetics. ► There is a relaxation time associated with a rapid variation in the neutron flux. ► Physical interpretation of the fractional order is related with non-Fickian effects. ► Effect of the anomalous diffusion coefficient and the relaxation time is analyzed. ► Neutron density is related with speed and duration of the control rods lifting. - Abstract: In this paper we present the behavior of the variation of neutron density when the nuclear reactor power is increased using the fractional neutron point kinetic (FNPK) equation with a single-group of delayed neutron precursor. It is considered that there is a relaxation time associated with a rapid variation in the neutron flux and its physical interpretation of the fractional order is related with non-Fickian effects from the neutron diffusion equation point of view. We analyzed the case of increase the nuclear reactor power when reactor is cold start-up which is a process of inserting reactivity by lifting control rods discontinuously. The results show that for short time scales of the start-up the neutronic density behavior with FNPK shows sub-diffusive effects whose absorption are government by control rods velocity. For large times scale, the results shows that the classical equation of the neutron point kinetics over predicted the neutron density regarding to FNPK.

  4. Enabling benchmarking and improving operational efficiency at nuclear power plants through adoption of a common process model: SNPM (standard nuclear performance model)

    International Nuclear Information System (INIS)

    Pete Karns

    2006-01-01

    others. The goal of the SNPM is to give the people maintaining and operating nuclear power stations a common model on which to base their business processes and measure/benchmark themselves against others. The importance of benchmarking and comparing 'apples to apples' has and will continue to safely drive improvement and efficiencies throughout the business. For example, in the mid 1990's it was quite difficult to compare work management statistics and programs between plants. The introduction of several INPO documents, which eventually became the SNPM work management process (AP 928) enabled plants to benchmark and compare information on many aspects of work management, in fact INPO began to evaluate the nuclear plants on their implementation and usage of AP 928. Also, the standardization enabled the identification and benchmarking of innovations in plant processes and performance, which in turn helped to facilitate those innovations being accepted in other plants-thus furthering the cycle of continuous improvement. Using a master plan, all communities of practice are able to identify specific improvement projects and coordinate the implementation of the processes to ensure smooth transitions between the various process interface or intersection points. In essence the nuclear energy industry in the United States is working as one company-driving efficiencies and operational improvements. Key enablers in adopting the best practices like the SNPM are work, asset and supply chain management solutions - both from a functional and a technological point of view. In addition to the importance of supporting industry best practices, there are two additional attributes a nuclear power operating company should evaluate regarding software solutions for work, asset, and supply chain management: breadth of assets managed, and the architecture of solution. (author)

  5. Development of standard design licensing system of nuclear power plants

    International Nuclear Information System (INIS)

    Lee, S. K.; Yun, Y. K.; Kim, W. S.; Lee, J. H.; Baek, M.

    2001-01-01

    The design of the APR 1400 (Advanced Power Reactor 1400) is being developed based on the concept of a standard design so that the APR 1400 can be constructed repetitively without major design change. Therefore, in order to avoid repetitive licensing review for the portion of the standard design of the APR 1400, it is necessary to introduced a new licensing system for a standard design. Since the Korean government has acknowledged this necessity, it is now pursuing the legislation of a standard design licensing system. In this technical report, procedural requirements and the format and contents of licensing basis documents considered for the adaption of a standard design licensing system are introduced

  6. Standard Specification for Nuclear Facility Transient Worker Records

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1995-01-01

    1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. 1.2 This specification applies to records to be used for in-processing only. 1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications). 1.4 This specification does not reduce any regulatory requirement for records retention at a licensed nuclear facility. Note 1—Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD...

  7. A call for the adoption of nuclear utility information standards

    International Nuclear Information System (INIS)

    Slone, B.J. III; Richardson, C.E.

    1993-01-01

    In December 1986, the International Organization for Standardization (SO) issued a standard for document representation, ISO 8879, open-quotes Standard Generalized Markup Languageclose quotes (SGML). The standard prescribes a method for defining documents in two parts, one containing text and the other describing its structure without reference to word processing or publishing system software or hardware. It provides a method for open-quotes marking upclose quotes information, a way to place open-quotes tagsclose quotes on pieces of information to define their purpose. The SGML is part of a group of ISO standards titled open-quotes Information Processing-Text and Office Systems.close quotes This group contains the Document Style Specification and Semantics Language, the Standard Document Interchange Format, the Standard Page Description Language, and the fonts standard. The Department of Defense (DoD) has taken a standards initiative to improve the efficiency and reliability of systems by mandating that DoD suppliers comply with specific standards when delivering technical information. The initiative is called the Computer-aided Acquisition and Logistics Support (CALS) and includes a package of standards to address engineering drawings, raster font images, vector illustrations, text, and magnetic tape format. SGML is the CALS standard for documentation representation. Other industries have adopted this standard. Several industry groups, such as the Air Transport Association, American Association of Publishers, and the Telecommunications Industry Forum, are moving ahead vigorously with their own applications of SGML. The Institute of Electrical and Electronics Engineers has also adopted the ISO standard for production of its documents. Work is under way to develop their own SGML application

  8. Converting point-wise nuclear cross sections to pole representation using regularized vector fitting

    Science.gov (United States)

    Peng, Xingjie; Ducru, Pablo; Liu, Shichang; Forget, Benoit; Liang, Jingang; Smith, Kord

    2018-03-01

    Direct Doppler broadening of nuclear cross sections in Monte Carlo codes has been widely sought for coupled reactor simulations. One recent approach proposed analytical broadening using a pole representation of the commonly used resonance models and the introduction of a local windowing scheme to improve performance (Hwang, 1987; Forget et al., 2014; Josey et al., 2015, 2016). This pole representation has been achieved in the past by converting resonance parameters in the evaluation nuclear data library into poles and residues. However, cross sections of some isotopes are only provided as point-wise data in ENDF/B-VII.1 library. To convert these isotopes to pole representation, a recent approach has been proposed using the relaxed vector fitting (RVF) algorithm (Gustavsen and Semlyen, 1999; Gustavsen, 2006; Liu et al., 2018). This approach however needs to specify ahead of time the number of poles. This article addresses this issue by adding a poles and residues filtering step to the RVF procedure. This regularized VF (ReV-Fit) algorithm is shown to efficiently converge the poles close to the physical ones, eliminating most of the superfluous poles, and thus enabling the conversion of point-wise nuclear cross sections.

  9. IEEE [Institute of Electrical and Electronics Engineers] standards and nuclear software quality engineering

    International Nuclear Information System (INIS)

    Daughtrey, T.

    1988-01-01

    Significant new nuclear-specific software standards have recently been adopted under the sponsorship of the American Nuclear Society and the American Society of Mechanical Engineers. The interest of the US Nuclear Regulatory Commission has also been expressed through their issuance of NUREG/CR-4640. These efforts all indicate a growing awareness of the need for thorough, referenceable expressions of the way to build in and evaluate quality in nuclear software. A broader professional perspective can be seen in the growing number of software engineering standards sponsored by the Institute of Electrical and Electronics Engineers (IEEE) Computer Society. This family of standards represents a systematic effort to capture professional consensus on quality practices throughout the software development life cycle. The only omission-the implementation phase-is treated by accepted American National Standards Institute or de facto standards for programming languages

  10. SU-F-J-100: Standardized Biodistribution Template for Nuclear Medicine Dosimetry Collection and Reporting

    Energy Technology Data Exchange (ETDEWEB)

    Kesner, A [University of Colorado, Anschutz Medical Campus, Aurora, Colorado (United States); Poli, G [International Atomic Energy Agency, Vienna, Vienna (Austria); Beykan, S; Lassman, M [University of Wuerzburg, Wuerzberg, Wuerzberg (Germany)

    2016-06-15

    Purpose: As the field of Nuclear Medicine moves forward with efforts to integrate radiation dosimetry into clinical practice we can identify the challenge posed by the lack of standardized dose calculation methods and protocols. All personalized internal dosimetry is derived by projecting biodistribution measurements into dosimetry calculations. In an effort to standardize organization of data and its reporting, we have developed, as a sequel to the EANM recommendation of “Good Dosimetry Reporting”, a freely available biodistribution template, which can be used to create a common point of reference for dosimetry data. It can be disseminated, interpreted, and used for method development widely across the field. Methods: A generalized biodistribution template was built in a comma delineated format (.csv) to be completed by users performing biodistribution measurements. The template is available for free download. The download site includes instructions and other usage details on the template. Results: This is a new resource developed for the community. It is our hope that users will consider integrating it into their dosimetry operations. Having biodistribution data available and easily accessible for all patients processed is a strategy for organizing large amounts of information. It may enable users to create their own databases that can be analyzed for multiple aspects of dosimetry operations. Furthermore, it enables population data to easily be reprocessed using different dosimetry methodologies. With respect to dosimetry-related research and publications, the biodistribution template can be included as supplementary material, and will allow others in the community to better compare calculations and results achieved. Conclusion: As dosimetry in nuclear medicine become more routinely applied in clinical applications, we, as a field, need to develop the infrastructure for handling large amounts of data. Our organ level biodistribution template can be used as a

  11. Standardization of nuclear power plants in the United States: recent regulatory developments

    International Nuclear Information System (INIS)

    Cowan, B.Z.; Tourtellotte, J.R.

    1992-01-01

    On April 18, 1989, the United States (U.S.) Nuclear Regulatory Commission (NRC) amended the regulations governing the process for licensing nuclear power plants in the United States to provide for issuance of early site permits, standard design certifications and combined construction permits and operating licenses for nuclear power reactors. The new regulations are designed to achieve early resolution of licensing issues and facilitate standardization of nuclear power plants in the United States. The program for design standardization is central to efforts mounted by the U.S. government and industry to ensure that there will be a next generation of nuclear power facilities in the U.S. The most significant changes are provisions for certification of standard designs and for issuance prior to start of construction of combined licenses which incorporate a construction permit and an operating license with conditions. Such certifications and combined licenses must contain tests, inspections and analyses, and acceptance criteria, which are necessary and sufficient to provide reasonable assurance that the facility has been constructed and will operate in accordance with the combined license. A number of significant implementation issues have arisen. In addition a major court case brought by several anti-nuclear groups is pending, challenging NRC authority to issue combined licenses. It is the goal of the U.S. nuclear industry to have the first of the next generation of standardized nuclear power plants ordered, licensed, constructed and on-line by the year 2000. (author)

  12. Nuclear criticality safety program development using necessary and sufficient standards

    Energy Technology Data Exchange (ETDEWEB)

    Croucher, D.W.; Stachowiak, R.V. [Kaiser-Hill Co., LLC, Golden, CO (United States); Wilson, R.E. [Safe Sites of Colorado, Golden, CO (United States)

    1996-12-31

    The U.S. Department of Energy`s (DOE`s) Necessary and Sufficient Standards Closure Process has been used to develop a new criticality, safety program manual for the Rocky Flats Environmental Technology Site (RFETS). Standards define and communicate the expectations for performance of work. The purpose of the necessary and sufficient standards closure process is to apply standards determined to be necessary and sufficient for protecting the workers, the public, and the environment. This ensures that the applied standards add value to the performance of the activity; work effectiveness is increased. The purpose of this paper is to briefly describe the process and the results for the selection of national criticality safety standards for use at the Rocky Flats facilities.

  13. ASME nuclear codes and standards: Scope of coverage and current initiatives

    International Nuclear Information System (INIS)

    Eisenberg, G. M.

    1995-01-01

    The objective of this paper is to address the broad scope of coverage of nuclear codes, standards and guides produced and administered by the American Society of Mechanical Engineers (ASME). Background information is provided regarding the evolution of the present activities. Details are provided on current initiatives intended to permit ASME to meet the needs of a changing nuclear industry on a worldwide scale. During the early years of commercial nuclear power, ASME produced a code for the construction of nuclear vessels used in the reactor coolant pressure boundary, containment and auxiliary systems. In response to industry growth, ASME Code coverage soon broadened to include rules for construction of other nuclear components, and inservice inspection of nuclear reactor coolant systems. In the years following this, the scope of ASME nuclear codes, standards and guides has been broadened significantly to include air cleaning activities for nuclear power reactors, operation and maintenance of nuclear power plants, quality assurance programs, cranes for nuclear facilities, qualification of mechanical equipment, and concrete reactor vessels and containments. ASME focuses on globalization of its codes, standards and guides by encouraging and promoting their use in the international community and by actively seeking participation of international members on its technical and supervisory committees and in accreditation activities. Details are provided on current international representation. Initiatives are underway to separate the technical requirements from administrative and enforcement requirements, to convert to hard metric units, to provide for non-U. S. materials, and to provide for translations into non-English languages. ASME activity as an accredited ISO 9000 registrar for suppliers of mechanical equipment is described. Rules are being developed for construction of containment systems for nuclear spent fuel and high-level waste transport packagings. Intensive

  14. Environmental monitoring report for the Point Lepreau, New Brunswick nuclear generating station 1984

    International Nuclear Information System (INIS)

    Nelson, R.W.P.; Ellis, K.M.; Smith, J.N.

    1986-07-01

    The Point Lepreau Environmental Monitoring Program (PLEMP) has been established within the Department of Fisheries and Oceans to assess the environmental impact of radioactive, thermal, and chemical releases from the Point Lepreau, N.B. Nuclear Generating Station (NGS) located on the Bay of Fundy. This report contains the results for the second year of the operational phase of the monitoring program. Emphasis has been placed on those areas where effects from the NGS operation were expected to be observed. Further studies were carried out on the characterization of the thermal plume during several pre-arranged tritium releases. Attention was given to tritium levels at the outfall, in the atmosphere and in biological samples. An initial attempt was made to relate the distribution of tritium in the Point Lepreau area in various phases to local meteorological conditions. Radionuclide levels in lichen, including, for the first time, aerial lichen on a regular basis, an efficient accumulator of atmospheric particulates were monitored. In addition, radionuclide measurements were made on samples collected during the pre-operational phase from the major environmental reservoirs and these radioactivity levels were compared to previous measurements to assess the impact of the operation of the NGS. The purpose of this program is to provide government with a comprehensive scientific basis upon which to assess the environmental implications of the operation of nuclear reactors in coastal regions

  15. A saddle-point for data verification and materials accountancy to control nuclear material

    International Nuclear Information System (INIS)

    Beedgen, R.

    1983-01-01

    Materials accountancy is one of the main elements in international safeguards to determine whether or not nuclear material has been diverted in nuclear plants. The inspector makes independent measurements to verify the plant-operator's data before closing the materials balance with the operator's data. All inspection statements are in principle probability statements because of random errors in measuring the material and verification on a random sampling basis. Statistical test procedures help the inspector to decide under this uncertainty. In this paper a statistical test procedure representing a saddle-point is presented that leads to the highest guaranteed detection probability taking all concealing strategies into account. There are arguments favoring a separate statistical evaluation of data verification and materials accountancy. Following these considerations, a bivariate test procedure is explained that evaluates verification and accountancy separately. (orig.) [de

  16. Defining nuclear medical file format based on DICOM standard

    International Nuclear Information System (INIS)

    He Bin; Jin Yongjie; Li Yulan

    2000-01-01

    With the wide using of computer technology in medical area, DICOM is becoming the standard of digital imaging and communication. The author discusses how to define medical imaging file format based on DICOM standard. It also introduces the file format of ANMIS system authors defined and the validity and integrality of this format

  17. Defining nuclear medical file formal based on DICOM standard

    International Nuclear Information System (INIS)

    He Bin; Jin Yongjie; Li Yulan

    2001-01-01

    With the wide application of computer technology in medical area, DICOM is becoming the standard of digital imaging and communication. The author discusses how to define medical imaging file formal based on DICOM standard. It also introduces the format of ANMIS system the authors defined the validity and integrality of this format

  18. KWOC [Key-Word-Out-of-Context] index of nuclear energy standards

    International Nuclear Information System (INIS)

    Jennings, S.D.

    1990-05-01

    One major task of the Nuclear Standards Program funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs is to promote and support the use of standards by providing line managers and standards coordinators with data that facilitates their ability to utilize standards requirements. To meet this task, the Performance Assurance Project Office (PAPO) administers a Performance Assurance Information Program. The task is carried out in accordance with the principle set forth in DOE Order 1300.2, ''Department of Energy Standards Program,'' December 18, 1980, and DOE memorandum, ''Implementation of DOE Orders on Quality Assurance, Standards, and Unusual Occurrence Reporting for Nuclear Energy Programs,'' March 3, 1982, and with guidance from the DOE-NE Technology Support Programs. The purpose of this information program is to collect, compile, and distribute program-related information, reports, and publications for the benefit of the DOE-NE program participants

  19. Controversy over nuclear power. Behavior of two sides and media from the point of communication

    International Nuclear Information System (INIS)

    Sata, Tsutomu

    2006-01-01

    The interaction process among the four groups such as the affirmative side, the reverse side, mass media and the people for nuclear power is analyzed from the point of communication. A definition of four groups, safety of the sites and economic induction, the affirmative side aims at persuasion, the reverse side appeals to feelings, mass media takes up news to amusement, articles dramatized on the basis of the fact, persuasion with threatening has the opposite effect, personal attitude is affected by the group criterion, media brings people's interaction into focus, people have a hatred for a one-sided information, and information with sincerity touches the heart are reported. (S.Y.)

  20. Numerical Solution of Fractional Neutron Point Kinetics Model in Nuclear Reactor

    Directory of Open Access Journals (Sweden)

    Nowak Tomasz Karol

    2014-06-01

    Full Text Available This paper presents results concerning solutions of the fractional neutron point kinetics model for a nuclear reactor. Proposed model consists of a bilinear system of fractional and ordinary differential equations. Three methods to solve the model are presented and compared. The first one entails application of discrete Grünwald-Letnikov definition of the fractional derivative in the model. Second involves building an analog scheme in the FOMCON Toolbox in MATLAB environment. Third is the method proposed by Edwards. The impact of selected parameters on the model’s response was examined. The results for typical input were discussed and compared.

  1. Research on the General Framework of the Construction of Nuclear and Radiation Safety Standard System in China

    Science.gov (United States)

    Song, Dahu; Liu, Ting; Gao, Siyi; Tian, Yu; Yang, Lili; Zhang, Qiaoer

    2018-01-01

    In this paper, the general framework and suggestion for the construction of China Nuclear and radiation safety standard system are put forward. The relationship of nuclear and radiation safety standards with the relevant laws and regulations is discussed. The status quo, existing problems and requirements of nuclear and radiation safety standard are analysed in China. The research work has laid a foundation for the establishment and improvement of China’s nuclear and radiation safety standards system, and has made a useful exploration.

  2. Should evacuation standards be reviewed after a nuclear accident?

    International Nuclear Information System (INIS)

    Nifenecker, Herve

    2011-10-01

    The author comments the current practices of post-accident management of nuclear disasters. He outlines the peculiarities of nuclear evacuations with respect to other disasters. After referring to the use of life expectancy or of the reduction of life expectancy, for example for smokers, he suggests that irradiation could be expressed this way and then provide some intuitive information. He discusses the notion of linear no-threshold relationship which has been introduced by the ICRP after analysis of cancers noticed on survivors of Hiroshima and Nagasaki. He addresses the case of Fukushima, the issue of low doses applied to large populations. He discusses the limitations of the linear no-threshold relationship. He discusses possible improvements of evacuation procedures

  3. Standard guide for drying behavior of spent nuclear fuel

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This guide is organized to discuss the three major components of significance in the drying behavior of spent nuclear fuel: evaluating the need for drying, drying spent nuclear fuel, and confirmation of adequate dryness. 1.1.1 The guide addresses drying methods and their limitations in drying spent nuclear fuels that have been in storage at water pools. The guide discusses sources and forms of water that remain in SNF, its container, or both, after the drying process and discusses the importance and potential effects they may have on fuel integrity, and container materials. The effects of residual water are discussed mechanistically as a function of the container thermal and radiological environment to provide guidance on situations that may require extraordinary drying methods, specialized handling, or other treatments. 1.1.2 The basic issue in drying is to determine how dry the SNF must be in order to prevent issues with fuel retrievability, container pressurization, or container corrosion. Adequate d...

  4. Overview of the ANS [American Nuclear Society] mathematics and computation software standards

    International Nuclear Information System (INIS)

    Smetana, A.O.

    1991-01-01

    The Mathematics and Computations Division of the American Nuclear Society sponsors the ANS-10 Standards Subcommittee. This subcommittee, which is part of the ANS Standards Committee, currently maintains four ANSI/ANS software standards. These standards are: Recommended Programming Practices to Facilitate the Portability of Scientific Computer Programs, ANS-10.2; Guidelines for the Documentation of Computer Software, ANS-10.3; Guidelines for the Verification and Validation of Scientific and Engineering Computer Programs for the Nuclear Industry, ANS-10.4; and Guidelines for Accommodating User Needs in Computer Program Development, ANS-10.5. 5 refs

  5. American National Standard administrative practices for nuclear criticality safety, ANSI/ANS-8.19

    International Nuclear Information System (INIS)

    Smith, D.R.; Carson, R.W.

    1991-01-01

    American National Standard Administrative Practices for Nuclear Criticality Safety, ANSI/ANS-8.19, provides guidance for the administration of an effective program to control the risk of nuclear criticality in operations with fissile material outside reactors. The several sections of the standard address the responsibilities of management, supervisory personnel, and the criticality safety staff, as well as requirements and suggestions for the content of operating procedures, process evaluations, material control procedures, and emergency procedures

  6. A no-gold-standard technique for objective assessment of quantitative nuclear-medicine imaging methods.

    Science.gov (United States)

    Jha, Abhinav K; Caffo, Brian; Frey, Eric C

    2016-04-07

    The objective optimization and evaluation of nuclear-medicine quantitative imaging methods using patient data is highly desirable but often hindered by the lack of a gold standard. Previously, a regression-without-truth (RWT) approach has been proposed for evaluating quantitative imaging methods in the absence of a gold standard, but this approach implicitly assumes that bounds on the distribution of true values are known. Several quantitative imaging methods in nuclear-medicine imaging measure parameters where these bounds are not known, such as the activity concentration in an organ or the volume of a tumor. We extended upon the RWT approach to develop a no-gold-standard (NGS) technique for objectively evaluating such quantitative nuclear-medicine imaging methods with patient data in the absence of any ground truth. Using the parameters estimated with the NGS technique, a figure of merit, the noise-to-slope ratio (NSR), can be computed, which can rank the methods on the basis of precision. An issue with NGS evaluation techniques is the requirement of a large number of patient studies. To reduce this requirement, the proposed method explored the use of multiple quantitative measurements from the same patient, such as the activity concentration values from different organs in the same patient. The proposed technique was evaluated using rigorous numerical experiments and using data from realistic simulation studies. The numerical experiments demonstrated that the NSR was estimated accurately using the proposed NGS technique when the bounds on the distribution of true values were not precisely known, thus serving as a very reliable metric for ranking the methods on the basis of precision. In the realistic simulation study, the NGS technique was used to rank reconstruction methods for quantitative single-photon emission computed tomography (SPECT) based on their performance on the task of estimating the mean activity concentration within a known volume of interest

  7. A no-gold-standard technique for objective assessment of quantitative nuclear-medicine imaging methods

    International Nuclear Information System (INIS)

    Jha, Abhinav K; Frey, Eric C; Caffo, Brian

    2016-01-01

    The objective optimization and evaluation of nuclear-medicine quantitative imaging methods using patient data is highly desirable but often hindered by the lack of a gold standard. Previously, a regression-without-truth (RWT) approach has been proposed for evaluating quantitative imaging methods in the absence of a gold standard, but this approach implicitly assumes that bounds on the distribution of true values are known. Several quantitative imaging methods in nuclear-medicine imaging measure parameters where these bounds are not known, such as the activity concentration in an organ or the volume of a tumor. We extended upon the RWT approach to develop a no-gold-standard (NGS) technique for objectively evaluating such quantitative nuclear-medicine imaging methods with patient data in the absence of any ground truth. Using the parameters estimated with the NGS technique, a figure of merit, the noise-to-slope ratio (NSR), can be computed, which can rank the methods on the basis of precision. An issue with NGS evaluation techniques is the requirement of a large number of patient studies. To reduce this requirement, the proposed method explored the use of multiple quantitative measurements from the same patient, such as the activity concentration values from different organs in the same patient. The proposed technique was evaluated using rigorous numerical experiments and using data from realistic simulation studies. The numerical experiments demonstrated that the NSR was estimated accurately using the proposed NGS technique when the bounds on the distribution of true values were not precisely known, thus serving as a very reliable metric for ranking the methods on the basis of precision. In the realistic simulation study, the NGS technique was used to rank reconstruction methods for quantitative single-photon emission computed tomography (SPECT) based on their performance on the task of estimating the mean activity concentration within a known volume of interest

  8. Personnel involved in the development of nuclear standards in the United States, 1976

    International Nuclear Information System (INIS)

    Johnson, E.B.

    1977-03-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The directory has four major sections: personnel, employers, committees, and a KWIC index of committee titles. The directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities

  9. Personnel involved in the development of nuclear standards in the United States, 1976

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, E.B. (ed.)

    1977-03-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The directory has four major sections: personnel, employers, committees, and a KWIC index of committee titles. The directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

  10. Evaluation of the safety of the operating nuclear power plants built to earlier standards

    International Nuclear Information System (INIS)

    Menteseoglu, S.

    2001-01-01

    The objective of this paper is to provide practical assistance on judging the safety of a nuclear power plant, on the basis of a comparison with current safety standards and operational practices. For nuclear power plants built to earlier standards for which there are questions about the adequacy of the maintenance of the plant design and operational practices, a safety review against current standards and practices can be considered a high priority. The objective of reviewing nuclear power plants built to earlier standards against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The safety significance of the issues identified should be judged according to their implications for plant design and operation in terms of basic safety concepts such as defence in depth and safety culture. In addition, this paper provides assistance on the prioritization of corrective measures and their implementation so as to approach an acceptable level of safety

  11. Personnel involved in the development of nuclear standards in the United States, 1975

    International Nuclear Information System (INIS)

    Johnson, E.B.

    1976-05-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The Directory has four major sections: personnel, employers, committees, and a KWIC Index of committee titles. The Directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities

  12. Personnel involved in the development of nuclear standards in the United States, 1975

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, E.B. (ed.)

    1976-05-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The Directory has four major sections: personnel, employers, committees, and a KWIC Index of committee titles. The Directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

  13. Design of nuclear spectroscopy electronics based on the EUROsystem standard

    International Nuclear Information System (INIS)

    Pahor, J.

    1987-11-01

    The development of modular nuclear instruments in the EUROcard system has been continued by the design of a staircase generator; such an instrument is needed for accurate testing of spectroscopy amplifiers. The generator provides very precisely defined steps with the period between them varying from 8 to 50 microseconds, the output voltage continuously variable from 2 to 5 V, and attenuated ion steps between 1 and 100. Great care was taken that individual steps exhibit no overshot, thus providing a very clean signal to the input of a tested amplifier. The circuitry is kept simple, and it can be easily constructed in any electronics laboratory. Figs

  14. Standards for digital computers used in non-safety nuclear power plant applications: objectives and limitations

    International Nuclear Information System (INIS)

    Rorer, D.C.; Long, A.B.

    1977-01-01

    There are currently a number of efforts to develop standards which would apply to digital computers used in nuclear power plants for functions other than those directly involving plant protection (for example, ANS: 4.3.3 Subworking Group in the U.S., IEC 45A/WGA1 Subcommittee in Europe). The impetus for this activity is discussed and generally attributed to the realization that nonsafety systems computers may affect the assumptions used as the design bases for safety systems, the sizable economic loss which can result from the failure of a critical computer application, and the lingering concern about the misapplication of a still-new technology. At the same time, it is pointed out that these standards may create additional obstacles for the use of this new technology which are not present in the application of more conventional instrumentation and control equipment. Much of the U.S. effort has been directed toward the problem of validation of computer systems in which the potential exists for unplanned interactions between various functions in a multiprogram environment, using common hardware in a time-sharing mode. The goal is to develop procedures for the specification, development implementation, and documentation of testable, modular systems which, in the absence of proven quantitative techniques for assessing software reliability, are felt to provide reasonable assurance that the computer system will function as planned

  15. Standard specification for nuclear-grade aluminum oxide pellets

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This specification applies to pellets of aluminum oxide that may be ultimately used in a reactor core, for example, as filler or spacers within fuel, burnable poison, or control rods. In order to distinguish between the subject pellets and “burnable poison” pellets, it is established that the subject pellets are not intended to be used as neutron-absorbing material. 1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.

  16. a Registration Method of Point Clouds Collected by Mobile LIDAR Using Solely Standard Las Files Information

    Science.gov (United States)

    Gézero, L.; Antunes, C.

    2017-05-01

    In the last few years, LiDAR sensors installed in terrestrial vehicles have been revealed as an efficient method to collect very dense 3D georeferenced information. The possibility of creating very dense point clouds representing the surface surrounding the sensor, at a given moment, in a very fast, detailed and easy way, shows the potential of this technology to be used for cartography and digital terrain models production in large scale. However, there are still some limitations associated with the use of this technology. When several acquisitions of the same area with the same device, are made, differences between the clouds can be observed. The range of that differences can go from few centimetres to some several tens of centimetres, mainly in urban and high vegetation areas where the occultation of the GNSS system introduces a degradation of the georeferenced trajectory. Along this article a different method point cloud registration is proposed. In addition to the efficiency and speed of execution, the main advantages of the method are related to the fact that the adjustment is continuously made over the trajectory, based on the GPS time. The process is fully automatic and only information recorded in the standard LAS files is used, without the need for any auxiliary information, in particular regarding the trajectory.

  17. Recommendations to reduce hand exposure for standard nuclear medicine procedures

    International Nuclear Information System (INIS)

    Sans-Merce, M.; Ruiz, N.; Barth, I.; Carnicer, A.; Donadille, L.; Ferrari, P.; Fulop, M.; Ginjaume, M.; Gualdrini, G.; Krim, S.; Mariotti, F.; Ortega, X.; Rimpler, A.; Vanhavere, F.; Baechler, S.

    2011-01-01

    The optimization of the extremity dosimetry of medical staff in nuclear medicine was the aim of the Work Package 4 (WP4) of the ORAMED project, a Collaborative Project (2008–2011) supported by the European Commission within its 7th Framework Programme. Hand doses and dose distributions across the hands of medical staff working in nuclear medicine departments were evaluated through an extensive measurement program involving 32 hospitals in Europe and 139 monitored workers. The study included the most frequently used radionuclides, 99m Tc- and 18 F-labelled radiopharmaceuticals for diagnostic and 90 Y-labelled Zevalin ® and DOTATOC for therapy. Furthermore, Monte Carlo simulations were performed in different predefined scenarios to evaluate separately the efficacy of different radiation protection measures by comparing hand dose distributions according to various parameters. The present work gives recommendations based on results obtained with both measurements and simulations. This results in nine practical recommendations regarding the positioning of the dosemeters for an appropriate skin dose monitoring and the best protection means to reduce the personnel exposure.

  18. Fixed point and anomaly mediation in partial {\\boldsymbol{N}}=2 supersymmetric standard models

    Science.gov (United States)

    Yin, Wen

    2018-01-01

    Motivated by the simple toroidal compactification of extra-dimensional SUSY theories, we investigate a partial N = 2 supersymmetric (SUSY) extension of the standard model which has an N = 2 SUSY sector and an N = 1 SUSY sector. We point out that below the scale of the partial breaking of N = 2 to N = 1, the ratio of Yukawa to gauge couplings embedded in the original N = 2 gauge interaction in the N = 2 sector becomes greater due to a fixed point. Since at the partial breaking scale the sfermion masses in the N = 2 sector are suppressed due to the N = 2 non-renormalization theorem, the anomaly mediation effect becomes important. If dominant, the anomaly-induced masses for the sfermions in the N = 2 sector are almost UV-insensitive due to the fixed point. Interestingly, these masses are always positive, i.e. there is no tachyonic slepton problem. From an example model, we show interesting phenomena differing from ordinary MSSM. In particular, the dark matter particle can be a sbino, i.e. the scalar component of the N = 2 vector multiplet of {{U}}{(1)}Y. To obtain the correct dark matter abundance, the mass of the sbino, as well as the MSSM sparticles in the N = 2 sector which have a typical mass pattern of anomaly mediation, is required to be small. Therefore, this scenario can be tested and confirmed in the LHC and may be further confirmed by the measurement of the N = 2 Yukawa couplings in future colliders. This model can explain dark matter, the muon g-2 anomaly, and gauge coupling unification, and relaxes some ordinary problems within the MSSM. It is also compatible with thermal leptogenesis.

  19. Study of the effects of a tornado on a nuclear plant(from the point of view of civil engineering)

    International Nuclear Information System (INIS)

    Melendro, J.

    2010-01-01

    is to analyze the applicability of Regulatory Guide 1.76 d esign basis Tornado and Tornado Missiles for Nuclear Power Plants , assessing the guide / standard compliance of a nuclear facility with respect to it, identifying the actions required for the compliance if applicable and valuation, with engineering judgment, the benefits for the plant would total or partial implantation of the guide.

  20. IAEA nuclear data for applications: Cross section standards and the reference input parameter library (RIPL)

    International Nuclear Information System (INIS)

    Capote Noy, Roberto; Nichols, Alan L.; Pronyaev, Vladimir G.

    2003-01-01

    An integral part of the activities of the IAEA Nuclear Data Section involves the development of nuclear data for a wide range of user applications. When considering low-energy nuclear reactions induced by neutrons, photons and charged particles, a detailed knowledge is required of the production cross sections over a wide energy range, spectra of emitted particles and their angular distributions. Two highly relevant IAEA data development projects are considered in this paper. Neutron reaction cross-section standards represent the basic quantities needed in nuclear reaction cross-section measurements and evaluations. These standards and the covariance matrices of their uncertainties were previously evaluated and released in 1987. However, the derived uncertainties were subsequently considered to be unrealistic low due to the effect of the low uncertainties obtained in fitting the light element standards to the R-matrix model; as a result, evaluators were forced to scale up the uncertainties to 'expected values'. An IAEA Coordinated Research Project (CRP) entitled 'Improvement of the Standard Cross Sections for Light Elements' was initiated in 2002 to improve the evaluation methodology for the covariance matrix of uncertainty in the R-matrix model fits, and to produce R-matrix evaluations of the important light element standards. The scope of this CRP has been substantially extended to include the preparation of a full set of evaluated standard reactions and covariance matrices of their uncertainties. While almost all requests for nuclear data were originally addressed through measurement programmes, our theoretical understanding of nuclear phenomena has reached a reasonable degree of reliability and nuclear modeling has become standard practice in nuclear data evaluations (with measurements remaining crucial for data testing and benchmarking). Since nuclear model codes require a considerable amount of numerical input, the IAEA has instigated extensive efforts to

  1. Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992. [Final report

    Energy Technology Data Exchange (ETDEWEB)

    Hebdon, F.J. [Institute of Nuclear Power Operations, Atlanta, GA (United States)

    1993-03-01

    On August 24, 1992, Hurricane Andrew, a Category 4 hurricane, struck the Turkey Point Electrical Generating Station with sustained winds of 145 mph (233 km/h). This is the report of the team that the US Nuclear Regulatory Commission (NRC) and the Institute of Nuclear Power Operations (INPO) jointly sponsored (1) to review the damage that the hurricane caused the nuclear units and the utility`s actions to prepare for the storm and recover from it, and (2) to compile lessons that might benefit other nuclear reactor facilities.

  2. Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992

    International Nuclear Information System (INIS)

    Hebdon, F.J.

    1993-03-01

    On August 24, 1992, Hurricane Andrew, a Category 4 hurricane, struck the Turkey Point Electrical Generating Station with sustained winds of 145 mph (233 km/h). This is the report of the team that the US Nuclear Regulatory Commission (NRC) and the Institute of Nuclear Power Operations (INPO) jointly sponsored (1) to review the damage that the hurricane caused the nuclear units and the utility's actions to prepare for the storm and recover from it, and (2) to compile lessons that might benefit other nuclear reactor facilities

  3. Refined analysis of piping systens according to nuclear standard regulations

    International Nuclear Information System (INIS)

    Bisconti, N.; Lazzeri, L.; Strona, P.P.

    1975-01-01

    A number of programs have been selected to perform particular analyses partly coming from available libraries such as SAP 4 for static and dynamic analysis, partly directly written such as TRATE (for thermal analysis), VASTA, VASTB (to perform the analysis required by ASME 3 for pipings of class A and class B), CFRS (for the calculation of floor response spectra etc.). All the programs are automatically linked and directed by a general program (SCATCA for class A and SCATCB for class B pipings). The starting point is a list of the fabrication, thermal, geometrical and seismic data. The geometrical data are plotted (to check for possible errors) and fed to SAP for static and dynamic analysis together with seismic data and thermal data (average temperatures) reelaborated by TRATE 2 code. The raw data from SAP (weight, thermal, fixed points displacements, seismic, other dynamic) are concerned and reordered and fed to COMBIN 2 program together with the other data from thermal analysis (from TRATE 2). From Combin 2 program all the data are listed; each load set to be considered is provided, for each point, with the necessary data (thermal moments, pressure, average temperatures, thermal gradients), all the data from seismic, weight, and other dynamic analysis are also provided. All this amount of data is stored on a file and examined by VASTA code (for class A) or VASTB (for classes B,C) in order to make a decision about the acceptability of the design. Each subprogram may have an independent output in order to check partial results. Details about each program are provided and an exemple is given, together with a discussion of some-particular problems (thermohydraulic set definition, fatigue analysis, etc.)

  4. A systematic approach to the training in the nuclear power industry: The need for standard

    International Nuclear Information System (INIS)

    Wilkinson, J.D.

    1995-01-01

    The five elements of a open-quotes Systematic Approach to Trainingclose quotes (SAT) are analysis, design, development, implementation and evaluation. These elements are also present in the effective application of basic process control. The fundamental negative feedback process control loop is therefore an excellent model for a successful, systematic approach to training in the nuclear power industry. Just as standards are required in today's manufacturing and service industries, eg ISO 9000, so too are control standards needed in the training industry and in particular in the training of nuclear power plant staff. The International Atomic Energy Agency (IAEA) produced its TECDOC 525 on open-quotes Training to Establish and Maintain the Qualification and Competence of Nuclear Power Plant Operations Personnelclose quotes in 1989 and the American Nuclear Society published its open-quotes Selection, Qualification, and Training of Personnel for Nuclear Power Plants, an American National Standardclose quotes in 1993. It is important that community colleges, training vendors and organizations such as the Instrument Society of America (ISA), who may be supplying basic or prerequisite training to the nuclear power industry, become aware of these and other standards relating to training in the nuclear power industry

  5. Consensus standards utilized and implemented for nuclear criticality safety in Japan

    International Nuclear Information System (INIS)

    Nomura, Yasushi; Okuno, Hiroshi; Naito, Yoshitaka

    1996-01-01

    The fundamental framework for the criticality safety of nuclear fuel facilities regulations is, in many advanced countries, generally formulated so that technical standards or handbook data are utilized to support the licensing safety review and to implement its guidelines. In Japan also, adequacy of the safety design of nuclear fuel facilities is checked and reviewed on the basis of licensing safety review guides. These guides are, first, open-quotes The Basic Guides for Licensing Safety Review of Nuclear Fuel Facilities,close quotes and as its subsidiaries, open-quotes The Uranium Fuel Fabrication Facility Licensing Safety Review Guidesclose quotes and open-quotes The Reprocessing Facility Licensing Safety Review Guides.close quotes The open-quotes Nuclear Criticality Safety Handbook close-quote of Japan and the Technical Data Collection are published and utilized to supply related data and information for the licensing safety review, such as for the Rokkasho reprocessing plant. The well-established technical standards and data abroad such as those by the American Nuclear Society and the American National Standards Institute are also utilized to complement the standards in Japan. The basic principles of criticality safety control for nuclear fuel facilities in Japan are duly stipulated in the aforementioned basic guides as follows: 1. Guide 10: Criticality control for a single unit; 2. Guide 11: Criticality control for multiple units; 3. Guide 12: Consideration for a criticality accident

  6. Safety culture in a Belgian nuclear research centre from a social science point of view

    International Nuclear Information System (INIS)

    Fucks, I.; Hardeman, F.

    2002-01-01

    This paper is the result of a reflection within the framework of a Ph.D. research at SCK-CEN (Belgian Nuclear Research Centre) in collaboration with the University of Liege. The starting point of the work was the 'safety culture' model presented in the IAEA report 75-INSAG-4. This model is applied to the working organization of the SCK-CEN, also considering the safety culture as an open concept given its multi dimensionality. The methodology is based on three methods: observations, focus groups and interviews. The fieldwork was limited to two main installations: a research reactor, and a dismantling site. The preliminary findings are based on the data resulting from 4 Focus Groups. The most prominent components of a safety culture and the multiplicity of safety cultures in a large organization such as SCK-CEN will be discussed. (author)

  7. Indian Point Nuclear Power Station: verification analysis of County Radiological Emergency-Response Plans

    International Nuclear Information System (INIS)

    Nagle, J.; Whitfield, R.

    1983-05-01

    This report was developed as a management tool for use by the Federal Emergency Management Agency (FEMA) Region II staff. The analysis summarized in this report was undertaken to verify the extent to which procedures, training programs, and resources set forth in the County Radiological Emergency Response Plans (CRERPs) for Orange, Putnam, and Westchester counties in New York had been realized prior to the March 9, 1983, exercise of the Indian Point Nuclear Power Station near Buchanan, New York. To this end, a telephone survey of county emergency response organizations was conducted between January 19 and February 22, 1983. This report presents the results of responses obtained from this survey of county emergency response organizations

  8. Project on standards on good behaviour for the civilian nuclear industry

    International Nuclear Information System (INIS)

    Strohl, Pierre; Derche, Bernard

    1995-01-01

    Nuclear energy has provoked complex and sometimes heated debates involving politic, economic, scientific and moral issues, objective data alongside irrational feelings, short-term calculations as well as concerns touching on the far-reaching of humanity and the earth. These debates go beyond national borders as it is obvious that even though each country may hold divergent positions regarding the development of nuclear energy, their effects have an international scope, and, therefore, must be taken into account by all nations, even those who do not operate nuclear installations. Whatever conclusion may be drawn from these debates, decisions on nuclear energy are always taken by the political authorities, almost always at the highest level, be it national or international. These political decisions then become the body of legal standards, particularly the regulations which govern how nuclear energy is used. The main standards are for technical and scientific quality, applying to energy resource needs, to the reasons why the nuclear industry should be developed, to radioprotection and nuclear security, to protection of the environment, to radioactive waste management, to information and consulting to the public, to international cooperation, to non-proliferation of atomic weapons and to physical protection of nuclear materials. (author)

  9. Spatial distribution of radionuclides in Lake Michigan biota near the Big Rock Point Nuclear Plant

    International Nuclear Information System (INIS)

    Wahlgren, M.A.; Yaguchi, E.M.; Nelson, D.M.; Marshall, J.S.

    1974-01-01

    A survey was made of four groups of biota in the vicinity of the Big Rock Point Nuclear Plant near Charlevoix, Michigan, to determine their usefulness in locating possible sources of plutonium and other radionuclides to Lake Michigan. This 70 MW boiling-water reactor, located on the Lake Michigan shoreline, was chosen because its fuel contains recycled plutonium, and because it routinely discharges very low-level radioactive wastes into the lake. Samples of crayfish (Orconectes sp.), green algae (Chara sp. and Cladophora sp.), and an aquatic macrophyte (Potamogeton sp.) were collected in August 1973, at varying distances from the discharge and analyzed for 239 240 Pu, 90 Sr, and five gamma-emitting radionuclides. Comparison samples of reactor waste solution have also been analyzed for these radionuclides. Comparisons of the spatial distributions of the extremely low radionuclide concentrations in biota clearly indicated that 137 Cs, 134 Cs, 65 Zn, and 60 Co were released from the reactor; their concentrations decreased exponentially with increasing distance from the discharge. Conversely, concentrations of 239 240 Pu, 95 Zr, and 90 Sr showed no correlation with distance, suggesting any input from Big Rock was insignificant with respect to the atmospheric origin of these isotopes. The significance of these results is discussed, particularly with respect to current public debate over the possibility of local environmental hazards associated with the use of plutonium as a nuclear fuel. (U.S.)

  10. The energy sources and nuclear energy - The point of view of the Belgian Catholic Church

    International Nuclear Information System (INIS)

    Hoenraet, Christian

    2000-01-01

    The problems related to the environment are reported regularly to the public by means of the newspapers, on radio and television. The story is the product of a journalistic process and in general does not bear much resemblance to the original event. The rate and type of reportage depend not only on the body of data available to the journalist but on the information sources the journalist chosen to use. The same story is reported in a positive or negative way. Finally people are overwhelmed by contradictory information and became uncertain or frightened. In order to provide the general public with objective information about nuclear energy in particular and to made a statement about the position of the Belgian Catholic Church concerning this matter, the results of the study were published in Dutch under the form of a book with the title 'The Energy Sources and Nuclear Energy - Comparative analysis and ethical thoughts written the same author. Thia paper is a short survey of the results of the study and to present the point of view of the Belgian Catholic Church in the energy debate

  11. The point of view of religious authorities and philosophers on nuclear energy - Philosophy

    International Nuclear Information System (INIS)

    Anon.

    2016-01-01

    This article is the reporting of an interview made with Jacques Arnould, a science historian and philosopher. The philosopher thinks that the main problem of sciences and technologies is the lack of questioning about the real purpose of developing new technologies. Are they developed for the well-being and comfort of mankind or for the sole business and economical aspects? The response to this basic question is fundamental for the long-term acceptance of controversial technologies. In 2009 in the strong debate that took place on nano-technologies, the question of 'why this technology' was never asked and the debate was bogged down in technical issues. The consequences: 10 years later we are still at the same point. For nuclear technologies the ethical aspect is even more important because we engage future generations through the disposal of radioactive wastes. The nuclear risk should be balanced by the response to the why question: do we accept this risk because we want to provide humanity with plentiful non-carbon energy or because we want to develop an industrial sector? the ethical aspect is fundamental to deal with in terms of public acceptance. (A.C.)

  12. Socio-economic impacts of nuclear generating stations: Nine Mile Point and Fitzpatrick case study

    International Nuclear Information System (INIS)

    Branch, K.; Cochran, R.; Meale, R.

    1982-07-01

    This report documents a case study of the socio-economic impacts of the construction and operation of the Nine Mile Point and Fitzpatrick nuclear power stations. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of the construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

  13. Issues and relationships among software standards for nuclear safety applications. Version 2.0

    International Nuclear Information System (INIS)

    Scott, J.A.; Preckshot, G.G.; Lawrence, J.D.; Johnson, G.L.

    1996-01-01

    Lawrence Livermore National Laboratory is assisting the Nuclear Regulatory Commission with the development of draft regulatory guides for selected software engineering standards. This report describes the results of the initial task in this work. The selected software standards and a set of related software engineering standards were reviewed, and the resulting preliminary elements of the regulatory positions are identified in this report. The importance of a thorough understanding of the relationships among standards useful for developing safety-related software is emphasized. The relationship of this work to the update of the Standard Review Plan is also discussed

  14. Evaluating operational specifications of point-of-care diagnostic tests: a standardized scorecard.

    Directory of Open Access Journals (Sweden)

    Jonathan D Lehe

    Full Text Available The expansion of HIV antiretroviral therapy into decentralized rural settings will increasingly require simple point-of-care (POC diagnostic tests that can be used without laboratory infrastructure and technical skills. New POC test devices are becoming available but decisions around which technologies to deploy may be biased without systematic assessment of their suitability for decentralized healthcare settings. To address this, we developed a standardized, quantitative scorecard tool to objectively evaluate the operational characteristics of POC diagnostic devices. The tool scores devices on a scale of 1-5 across 30 weighted characteristics such as ease of use, quality control, electrical requirements, shelf life, portability, cost and service, and provides a cumulative score that ranks products against a set of ideal POC characteristics. The scorecard was tested on 19 devices for POC CD4 T-lymphocyte cell counting, clinical chemistry or hematology testing. Single and multi-parameter devices were assessed in each of test categories. The scores across all devices ranged from 2.78 to 4.40 out of 5. The tool effectively ranked devices within each category (p0.80; p<0.001. Use of this tool enables the systematic evaluation of diagnostic tests to facilitate product selection and investment in appropriate technology. It is particularly relevant for countries and testing programs considering the adoption of new POC diagnostic tests.

  15. Characterization of a metallic mechanical standard junction for a specific nuclear application

    International Nuclear Information System (INIS)

    Villanueva, Jose; Miller, Marcelo E.; Vazquez, Luis; Halpert, Silvia

    2007-01-01

    A testing procedure, targeted to promote that an industrial standard component can be used in a nuclear particular application, is designed and applied. Namely, a mechanical standard junction component, that is widely recognized for its industrial reliability, is commonly used to fit two stainless steel tubes, is intended to be used in a particular nuclear application fitting a stainless steel tube to a Zircaloy-4 tube counterpart. The junction will be subjected to pressure and temperature typical of primary circuit coolant in a nuclear power plant. The results found once the test was applied (catastrophic fault and significant water leakage absence) allow to advice using this mechanical junction device as a valid nuclear design option fitting the proposed tubes. (author) [es

  16. Auxiliary feedwater system risk-based inspection guide for the Point Beach nuclear power plant

    International Nuclear Information System (INIS)

    Lloyd, R.C.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.; Vehec, T.A.

    1993-02-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Point Beach was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRS. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Point Beach plant

  17. A brief review of nuclear electronics standards . . . Past, present and future

    International Nuclear Information System (INIS)

    Larsen, R.S.

    2000-01-01

    Modular Nuclear Instrument Standards have played a key role in U. S. Department of Energy National Laboratories and similar scientific laboratories worldwide for more than three decades. The scientific and engineering efficiency and economic benefits have been well documented. Standards are constantly evolving with the introduction of new technologies and the present is a time of rapid change. This report is based on an invited talk presented at the Joint Meeting of the U.S. Nuclear Instrument Module (NIM) and European Standards for Norms in Electronics (ESONE) Standards Committees, Lyon, France, October 20, 2000. It provides a brief overview of past developments and attempts to identify areas of possible opportunities for renewed standardization efforts to meet future challenges

  18. Contribution of the C.E.A. to standardization of nuclear plant equipments

    International Nuclear Information System (INIS)

    Dumax, P.; Seran, R.

    1980-01-01

    In research and production laboratories working in the nuclear field standardization of equipments greatly improves the profits of the installation and the protection of individuals and goods. The standardization effort on technical equipments of shielding, handling, detection and safety (so called P.M.D.S.) initiated by the C.E.A. in 1967 is being carried out now within the Institute of Protection and Nuclear Safety (I.P.S.N.) by a technical Service specialized in protection and dosimetry (S.T.E.P.D.). Its purpose is to establish standardization documents for internal use and to take part in the work of official standardization organizations. The benefits of standardization are reviewed. The achievements of the various working groups common to C.E.A. centers are stated and the documents published or to be published are listed [fr

  19. Actinide half-lives as standards for nuclear data measurements: current status

    International Nuclear Information System (INIS)

    Reich, C.W.

    1984-01-01

    The present status of knowledge of the half-life data for a number of long-lived actinide nuclides useful as standards for nuclear data measurements and reactor research and technology is summarized. The half-life information given draws heavily from the file of recommended decay data, generated over a number of years through the activities of an IAEA coordinated research program on the measurement and evaluation of transactinium-isotope nuclear decay data, whose work has recently been completed

  20. Recent developments in the IAEA safety standards: design and operation of nuclear power plants

    International Nuclear Information System (INIS)

    Saito, Takehiko

    2004-01-01

    The IAEA has been publishing a wide variety of safety standards for nuclear and radiation related facilities and activities since 1978. In 1996, a more rigorously structured approach for the preparation and review of its safety standards was introduced. Currently, based on the approach, revision of most of the standards is in completion or near completion. The latest versions of the Safety Requirements for ''Design'' and ''Operation'' of nuclear power plants were respectively published in 2000. Currently, along with this revision of the Safety Requirements, many Safety Guides have been revised. In order to clarify the complicated revision procedure, an example of the entire revision process for a Safety Guide is provided. Through actual example of the revision process, enormous amount of work involved in the revision work is clearly indicated. The current status of all of the Safety Standards for Design and that for Operation of nuclear power plants are summarized. Summary of other IAEA safety standards currently revised and available related IAEA publications, together with information on the IAEA Web Site from where these documents can be downloaded, is also provided. The standards are reviewed to determine whether revision (or new issue) is necessary in five years following publication. The IAEA safety standards will continue to be updated through comprehensive and structured approach, collaboration of many experts of the world, and reflecting good practices of the world. The IAEA safety standards will serve to provide high level of safety assurance. (author)

  1. A basic plan for the environment-friendly aspects of improved Korean standard nuclear power plant

    International Nuclear Information System (INIS)

    Jung, Hoon-Seok; Lee, Yong-Koo; Kim, Kwang-Ho

    2006-01-01

    The Improved Korean Standard Nuclear Power Plant (KSNP+) design has been made possible on the basis of engineering experiences and referring to an in-depth analysis of the design and construction of all the domestic nuclear power plants in operation. The KSNP+ is designed for improved safety, better economics, operability and maintainability by means of advanced technology expecting to demonstrate enhanced performance. The plant also has incorporated several environmentally friendly features through the restoration of excavated areas using an ecological approach, external coloring, figure of turbine generator building and landscaping around nuclear power plant. This is the first time that KOPEC has embarked on inducing environmentally friendly features into the basic plan. This is expected to mitigate the negative perceptions held by the residents in the vicinity of nuclear power plants and will contribute to a new and improved image of nuclear power plants. (authors)

  2. Standard concerning the design of nuclear power stations in earthquake-prone districts

    International Nuclear Information System (INIS)

    Kirillov, A.P.; Anbriashivili, Y.K.; Suvilova, A.V.

    1980-01-01

    The measures of security assurance against the effect of radioactive contamination has become more and more complex due to the construction of nuclear power stations of diverse types. The aseismatic measures for the nuclear power stations built in the districts where earthquakes of different intensity occur are important problems. All main machinery and equipments and emergency systems in power stations must be protected from earthquakes, and this makes the solution of problems difficult. At present in USSR, the provisional standard concerning the design of atomic energy facilities built in earthquake-prone districts is completed. The basic philosophy of the standard is to decide the general requirements as the conditions for the design of nuclear power stations built in earthquake-prone districts. The lowest earthquake activity in the construction districts is considered as magnitude 4, and in the districts where earthquake activity is magnitude 9 or more, the construction of nuclear power stations is prohibited. Two levels of earthquake action are specified for the design: design earthquake and the largest design earthquake. The construction sites of nuclear power stations must be 15 to 150 km distant from the potential sources of earthquakes. Nuclear power stations are regarded as the aseismatically guaranteed type when the safety of reactors is secured under the application of the standard. The buildings and installations are classified into three classes regarding the aseismatic properties. (Kako, I.)

  3. Some internationl law elements of national nuclear regulations from the Polish point of view

    International Nuclear Information System (INIS)

    Gadkowski, T.

    1992-01-01

    The essential contents of the Polish Nuclear Act from 1986 reflects on one hand needs and possibilities of the industrial use of nuclear energy and, on the other, international obligations of Poland. Poland is a State with a limited activity regarding to industrial use of nuclear energy; the main international-law elements of national nuclear regulations can be described as follows: 1. The good-neighborliness principle concerning the siting of nuclear installations in border areas. 2. An adequate concept of nuclear damage. 3. An adequate concept of liability for nuclear damage. (orig./HSCH)

  4. Nuclear reactor pressure vessel surveillance capsule examinations. Application of American Society for Testing and Materials Standards

    International Nuclear Information System (INIS)

    Perrin, J.S.

    1978-01-01

    A series of pressure vessel surveillance capsules is installed in each commercial nuclear power plant in the United States. A capsule typically contains neutron dose meters, thermal monitors, tensile specimens, and Charpy V-notch impact specimens. In order to determine property changes of the pressure vessel resulting from irradiation, surveillance capsules are periodically removed during the life of a reactor and examined. There are numerous standards, regulations, and codes governing US pressure vessel surveillance capsule programmes. These are put out by the US Nuclear Regulatory Commission, the Boiler and Pressure Vessel Committee of the American Society of Mechanical Engineers, and the American Society for Testing and Materials (ASTM). A majority of the pertinent ASTM standards are under the jurisdiction of ASTM Committee E-10 on Nuclear Applications and Measurements of Radiation Effects. The standards, regulations, and codes pertaining to pressure vessel surveillance play an important role in ensuring reliability of the nuclear pressure vessels. ASTM E 185-73 is the Standard Recommended Practice for Surveillance Tests for Nuclear Reactors. This standard recommends procedures for both the irradiation and subsequent testing of surveillance capsules. ASTM E 185-73 references many additional specialized ASTM standards to be followed in specific areas of a surveillance capsule examination. A key element of surveillance capsule programmes is the Charpy V-notch impact test, used to define curves of fracture behaviour over a range of temperatures. The data from these tests are used to define the adjusted reference temperature used in determining pressure-temperature operating curves for a nuclear power plant. (author)

  5. Suggestions and comments about preliminary plans of ABNT 20:04.002-001 standard 'Seismic actions for nuclear facilities project'

    International Nuclear Information System (INIS)

    Soares, W.A.

    1984-01-01

    This paper presents an analysis of preliminary plans of standard 'seismic actions for nuclear facilities project'. This document presents since seismic event characterization up to details of structural project of nuclear facilities construction. (C.M.)

  6. 76 FR 22928 - Nextera Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental...

    Science.gov (United States)

    2011-04-25

    ... or create a new waste stream. Therefore, the impact from the proposed EPU on radioactive solid waste...-4--Environmental Impact of Transportation of Fuel and Waste to and from One Light-Water-Cooled... protection standards. Radioactive Solid Waste...... Amount of additional radioactive solid waste generated...

  7. Integrating industry nuclear codes and standards into United States Department of Energy facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jacox, J.

    1995-02-01

    Recently the United States Department of Energy (DOE) has mandated facilities under their jurisdiction use various industry Codes and Standards developed for civilian power reactors that operate under U.S. Nuclear Regulatory Commission License. While this is a major step forward in putting all our nuclear facilities under common technical standards there are always problems associated with implementing such advances. This paper will discuss some of the advantages and problems experienced to date. These include the universal challenge of educating new users of any technical documents, repeating errors made by the NRC licensed facilities over the years and some unique problems specific to DOE facilities.

  8. The nuclear debate in France: some additional data. A point of view by the French Nuclear Energy Society (SFEN)

    International Nuclear Information System (INIS)

    2011-01-01

    Coming after the Fukushima accident which boosted the debate on nuclear energy in France, this document expresses the opinion of the French Nuclear Energy Society (SFEN). According to it, nuclear energy is an answer to the two main current challenges the World is facing: energy supply and global warming. Perspectives of energy policy should be based on a triptych: energy savings, renewable energies and nuclear energy. The authors also states that uranium reserves are available for centuries and even more, that the nuclear industry has a better record than other sources of production of electricity in terms of safety, and that the problem of nuclear wastes is solved. They consider that, provided that AREVA possesses property rights on important uranium reserves in America, Africa and Asia, the national independence is therefore guaranteed. Moreover, the French nuclear industry is a world leader, and the existence of nuclear energy production in France avoids many expenses. Therefore, the authors assert that giving up nuclear energy would be a triple step backwards

  9. Use of the Neutron Activation Analysis, k0-standardized method, in the evaluation of the air quality in critical points of Belo Horizonte

    International Nuclear Information System (INIS)

    Moura, Igor Felipe S.; Cruz, Ananda B.; Cesar, Raisa H.S.; Oliveira, Aline F.G. de; Barreto, Alberto A.; Menezes, Maria Ângela de B.C.; Centro de Desenvolvimento da Tecnologia Nuclear

    2017-01-01

    Belo Horizonte, the capital of Minas Gerais, is one of the largest cities in Brazil. It is geographically centered on a region with intense mining and industrial activity and a fleet of more than 1.5 million vehicles. The numerous sources of atmospheric emissions of particulate matter in this capital and its vicinity offer a considerable risk to the degradation of air quality. In order to contribute with elemental composition of particulate matter, the Nuclear Technology Development Center / Brazilian Commission for Nuclear Energy, and the Department of Nuclear Engineering of the Federal University of Minas Gerais has developed a research based on environmental samples. This work aims to present the sampling methodology, the concentration values of sampled particulate matter, the methodology of analysis of elemental concentration using the nuclear technique of neutron activation analysis, k 0 -standardized method, and interpreted through statistical techniques and values of the elemental concentrations more representative of the samplings carried out. The results pointed out the vehicle emissions as the major source that contributes to airborne particulate matter followed by soil resuspension. (author)

  10. Use of the Neutron Activation Analysis, k0-standardized method, in the evaluation of the air quality in critical points of Belo Horizonte

    Energy Technology Data Exchange (ETDEWEB)

    Moura, Igor Felipe S.; Cruz, Ananda B.; Cesar, Raisa H.S.; Oliveira, Aline F.G. de; Barreto, Alberto A.; Menezes, Maria Ângela de B.C., E-mail: igorfelipedx@yahoo.com.br, E-mail: abc@cdtn.br, E-mail: raisa.santana@hotmail.com, E-mail: afgo@cdtn.br, E-mail: aab@cdtn.br, E-mail: menezes@cdtn.br [Universidade Federal de Minas Gerais (DEN/UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN), Belo Horizonte, MG (Brazil). Divisão de Meio Ambiente

    2017-07-01

    Belo Horizonte, the capital of Minas Gerais, is one of the largest cities in Brazil. It is geographically centered on a region with intense mining and industrial activity and a fleet of more than 1.5 million vehicles. The numerous sources of atmospheric emissions of particulate matter in this capital and its vicinity offer a considerable risk to the degradation of air quality. In order to contribute with elemental composition of particulate matter, the Nuclear Technology Development Center / Brazilian Commission for Nuclear Energy, and the Department of Nuclear Engineering of the Federal University of Minas Gerais has developed a research based on environmental samples. This work aims to present the sampling methodology, the concentration values of sampled particulate matter, the methodology of analysis of elemental concentration using the nuclear technique of neutron activation analysis, k{sub 0}-standardized method, and interpreted through statistical techniques and values of the elemental concentrations more representative of the samplings carried out. The results pointed out the vehicle emissions as the major source that contributes to airborne particulate matter followed by soil resuspension. (author)

  11. Standard GAX versus hybrid GAX absorption refrigeration cycle: From the view point of thermoeconomics

    International Nuclear Information System (INIS)

    Mehr, A.S.; Zare, V.; Mahmoudi, S.M.S.

    2013-01-01

    Highlights: • The SGAX cycle is found to be thermoeconomically efficient compared to HGAX cycle. • The HGAX cycle has higher COP and exergy efficiency compared to SGAX cycle. • Minimum product cost is found 180.5 $/GJ and 159.1 $/GJ for HGAX and SGAX, respectively. - Abstract: The main goal of this research is to compare thermoeconomic performance of a GAX absorption cycle and a hybrid GAX absorption cycle in which a compressor is employed to raise the absorber pressure. In order to do this, the ammonia–water standard GAX (SGAX) and hybrid GAX (HGAX) absorption refrigeration cycles are investigated and optimized from the viewpoints of thermodynamics and economics. Parametric studies are carried out and with the help of genetic algorithm (GA), the cycles’ performance is optimized based on the COP and exergy efficiency as well as the cost of unit product. Results indicate that although, compared to the GAX cycle, the HGAX cycle demonstrates a better performance from the view points of both the first and second laws of thermodynamics, the unit product cost for the HGAX cycle is higher. At the optimum operating conditions, the cost of unit product for the HGAX cycle is calculated as 180.5 $/GJ while the corresponding value for the SGAX cycle is obtained as 159.1 $/GJ. Also, the exergoeconomic analyses unfold that the condenser has the lowest exergoeconomic factor, f, in both the systems. In addition, inspired from nature, a new graphical plot is proposed to illustrate the fuel cost, product cost, capital investment and operating and maintenance cost and cost rates associated with the exergy destruction and losses within the system’s components

  12. Evaluation of the H-point standard additions method (HPSAM) and the generalized H-point standard additions method (GHPSAM) for the UV-analysis of two-component mixtures.

    Science.gov (United States)

    Hund, E; Massart, D L; Smeyers-Verbeke, J

    1999-10-01

    The H-point standard additions method (HPSAM) and two versions of the generalized H-point standard additions method (GHPSAM) are evaluated for the UV-analysis of two-component mixtures. Synthetic mixtures of anhydrous caffeine and phenazone as well as of atovaquone and proguanil hydrochloride were used. Furthermore, the method was applied to pharmaceutical formulations that contain these compounds as active drug substances. This paper shows both the difficulties that are related to the methods and the conditions by which acceptable results can be obtained.

  13. Round table discussion: Quality control and standardization of nuclear medicine software

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    In summary the round table came to the following important conclusions: Nuclear medicine software systems need better documentation, especially regarding details of algorithms and limitations, and user friendliness could be considerably improved. Quality control of software is an integral part of quality assurance in nuclear medicine and should be performed at all levels of the software. Quality control of applications software should preferably be performed with assistance of generally accepted software phantoms. A basic form of standardization was welcomed and partly regarded as essential by all participants. Some areas such as patient study files could be standardized in the near future, whereas other areas such as the standardization of clinical applications programs or acquisition protocols still present major difficulties. An international cooperation in the field of standardization of software and other topics has already been started on the European level and should be continued and supported. (orig.)

  14. Methodology to evaluate the site standard seismic motion for a nuclear facility

    International Nuclear Information System (INIS)

    Soares, W.A.

    1983-03-01

    An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic priciples of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; avalable methodologies and recommended procedures to evaluate the site standard seismic motion. (E.G.) [pt

  15. Selected review of regulatory standards and licensing issues for nuclear power plants

    International Nuclear Information System (INIS)

    Stevenson, J.D.; Thomas, F.A.

    1982-11-01

    This report presents a compilation and description of current foreign regulatory standards and licensing issues in the areas of interest associated with Siting, Structural Engineering, Metallurgy and Materials, and Mechanical Engineering. In addition, summary comparisons of the requirements of both the US and foreign nuclear power plant regulatory standards are provided. The selected foreign countries surveyed include Canada, France, Japan, Sweden, United Kingdom of Great Britain and Northern Ireland, and the Federal Republic of Germany

  16. Nuclear reactors' construction costs: The role of lead-time, standardization and technological progress

    International Nuclear Information System (INIS)

    Berthelemy, Michel; Escobar Rangel, Lina

    2013-01-01

    This paper provides the first comparative analysis of nuclear reactor construction costs in France and the United States. Studying the cost of nuclear power has often been a challenge, owing to the lack of reliable data sources and heterogeneity between countries, as well as the long time horizon which requires controlling for input prices and structural changes. We build a simultaneous system of equations for overnight costs and construction time (lead-time) to control for endogeneity, using expected demand variation as an instrument. We argue that benefits from nuclear reactor program standardization can arise through short term coordination gains, when the diversity of nuclear reactors' technologies under construction is low, or through long term benefits from learning spillovers from past reactor construction experience, if those spillovers are limited to similar reactors. We find that overnight construction costs benefit directly from learning spillovers but that these spillovers are only significant for nuclear models built by the same Architect-Engineer (A- E). In addition, we show that the standardization of nuclear reactors under construction has an indirect and positive effect on construction costs through a reduction in lead-time, the latter being one of the main drivers of construction costs. Conversely, we also explore the possibility of learning by searching and find that, contrary to other energy technologies, innovation leads to construction costs increases. (authors)

  17. Topical questions of nuclear energy law from an international point of view

    International Nuclear Information System (INIS)

    Ziegler, E.

    1984-01-01

    Apart from the national legal problems, national regulations and developments were discussed with a view to their consequences on an international scale and compared with the regulations of other countries. Subjects: International cooperation, non-proliferation policy, national licensing procedures compared, problems of nuclear power acceptance, liabilities and commercial law in the nuclear fuel cycle, legal and financial problems in nuclear waste management and decommissioning, recent problems of nuclear liability. (orig./HP) [de

  18. Development of a consensus standard for verification and validation of nuclear system thermal-fluids software

    International Nuclear Information System (INIS)

    Harvego, Edwin A.; Schultz, Richard R.; Crane, Ryan L.

    2011-01-01

    With the resurgence of nuclear power and increased interest in advanced nuclear reactors as an option to supply abundant energy without the associated greenhouse gas emissions of the more conventional fossil fuel energy sources, there is a need to establish internationally recognized standards for the verification and validation (V and V) of software used to calculate the thermal–hydraulic behavior of advanced reactor designs for both normal operation and hypothetical accident conditions. To address this need, ASME (American Society of Mechanical Engineers) Standards and Certification has established the V and V 30 Committee, under the jurisdiction of the V and V Standards Committee, to develop a consensus standard for verification and validation of software used for design and analysis of advanced reactor systems. The initial focus of this committee will be on the V and V of system analysis and computational fluid dynamics (CFD) software for nuclear applications. To limit the scope of the effort, the committee will further limit its focus to software to be used in the licensing of High-Temperature Gas-Cooled Reactors. Although software verification will be an important and necessary part of the standard, much of the initial effort of the committee will be focused on the validation of existing software and new models that could be used in the licensing process. In this framework, the Standard should conform to Nuclear Regulatory Commission (NRC) and other regulatory practices, procedures and methods for licensing of nuclear power plants as embodied in the United States (U.S.) Code of Federal Regulations and other pertinent documents such as Regulatory Guide 1.203, “Transient and Accident Analysis Methods” and NUREG-0800, “NRC Standard Review Plan”. In addition, the Standard should be consistent with applicable sections of ASME NQA-1-2008 “Quality Assurance Requirements for Nuclear Facility Applications (QA)”. This paper describes the general

  19. Plume tracer experiments at Hinkley Point 'A' [Nuclear Power Station] during 1987

    International Nuclear Information System (INIS)

    Foster, P.M.

    1988-11-01

    The results of the first part of a programme of plume dispersion measurements at the Hinkley Point Nuclear Power Station are described. Using SF 6 gas and pyrotechnic smoke tracer techniques developed during an earlier study at Oldbury, measurements of ground level plume behaviour out to about 4 km and elevated plume behaviour out to about 1 km have been made in a series of twelve 1 hour trials and one 15 minute trial. Whereas the Oldbury study considered passive emissions, attention in this study has been focussed on the behaviour of the buoyant shield cooling air emission. Data on plume rise and the degree of plume entrainment by the building wake and on the effects of entrainment and wind meander on plume width and concentration, are presented and discussed in relation to current modelling recommendations. A limited number of 10 minute averaged measurements of plume concentration and 41-Ar decay gamma count were also made at 2 km range and their correlation and variability examined. (author)

  20. Nuclear Quantum Effects in Water at the Triple Point: Using Theory as a Link Between Experiments.

    Science.gov (United States)

    Cheng, Bingqing; Behler, Jörg; Ceriotti, Michele

    2016-06-16

    One of the most prominent consequences of the quantum nature of light atomic nuclei is that their kinetic energy does not follow a Maxwell-Boltzmann distribution. Deep inelastic neutron scattering (DINS) experiments can measure this effect. Thus, the nuclear quantum kinetic energy can be probed directly in both ordered and disordered samples. However, the relation between the quantum kinetic energy and the atomic environment is a very indirect one, and cross-validation with theoretical modeling is therefore urgently needed. Here, we use state of the art path integral molecular dynamics techniques to compute the kinetic energy of hydrogen and oxygen nuclei in liquid, solid, and gas-phase water close to the triple point, comparing three different interatomic potentials and validating our results against equilibrium isotope fractionation measurements. We will then show how accurate simulations can draw a link between extremely precise fractionation experiments and DINS, therefore establishing a reliable benchmark for future measurements and providing key insights to increase further the accuracy of interatomic potentials for water.

  1. Summary of component reliability data for probabilistic safety analysis of Korean standard nuclear power plant

    International Nuclear Information System (INIS)

    Choi, S. Y.; Han, S. H.

    2004-01-01

    The reliability data of Korean NPP that reflects the plant specific characteristics is necessary for PSA of Korean nuclear power plants. We have performed a study to develop the component reliability DB and S/W for component reliability analysis. Based on the system, we had have collected the component operation data and failure/repair data during plant operation data to 1998/2000 for YGN 3,4/UCN 3,4 respectively. Recently, we have upgraded the database by collecting additional data by 2002 for Korean standard nuclear power plants and performed component reliability analysis and Bayesian analysis again. In this paper, we supply the summary of component reliability data for probabilistic safety analysis of Korean standard nuclear power plant and describe the plant specific characteristics compared to the generic data

  2. Impact of New Radiation Safety Standards on Licensing Requirements of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Strohal, P.; Subasic, D.; Valcic, I.

    1996-01-01

    As the outcomes of the newly introduced safety philosophies, new and more strict safety design requirements for nuclear installation are expected to be introduced. New in-depth defence measures should be incorporated into the design and operation procedure for a nuclear installation, to compensate for potential failures in protection or safety measures. The new requirements will also apply to licensing of NPP's operation as well as to licensing of nuclear sites, especially for radioactive waste disposal sites. This paper intends to give an overview of possible impacts of new internationally agreed basic safety standards with respect to NPP and related technologies. Recently issued new basic safety standards for radiation protection are introducing some new safety principles which may have essential impact on future licensing requirements regarding nuclear power plants and radioactive waste installations. These new standards recognize exposures under normal conditions ('practices') and intervention conditions. The term interventions describes the human activities that seek to reduce the existing radiation exposure or existing likelihood of incurring exposure which is not part of a controlled practice. The other new development in safety standards is the introduction of so called potential exposure based on the experience gained from a number of radiation accidents. This exposure is not expected to be delivered with certainty but it may result from an accident at a source or owing to an event or sequence of events of a probabilistic nature, including equipment failures and operating errors. (author)

  3. Solution for the nuclear reactor point-kinetics problem via decomposition method; Solucao via metodo da decomposicao do problema de cinetica puntual de um reator nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Vargas, Rubem Mario Figueiro [Pontificia Univ. Catolica do Rio Grande do Sul, Porto Alegre, RS (Brazil). Faculdade de Engenharia. Dept. de Engenharia Quimica]. E-mail: rvargas@pucrs.br; Vilhena, Marco Tullio de [Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Inst. de Matematica]. E-mail: vilhena@mat.ufrgs.br; Cardona, Augusto Vieira [Pontificia Univ. Catolica do Rio Grande do Sul, Porto Alegre, RS (Brazil). Faculdade de Matematica]. E-mail: acardona@pucrs.br

    2005-07-01

    The decomposition method is a mathematical technique, usually, applied to solve nonlinear problems, but can be an effective procedure for analytical solution of linear problems presenting advantages when compared with others techniques. In this work, an analytical solution for the nuclear reactor point-kinetics equations is developed using the decomposition method. (author)

  4. 78 FR 34431 - Effluent Limitations Guidelines and Standards for the Steam Electric Power Generating Point...

    Science.gov (United States)

    2013-06-07

    ... Health XV. Non-Water Quality Environmental Impacts A. Energy Requirements B. Air Pollution C. Solid Waste... Power Generating Point Source Category AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed... Generating Point Source Category (TDD), Document No. EPA-821-R-13-002. Environmental Assessment for the...

  5. Proposals for Standardizing and Improving the Policy of Adding Points on the Entrance Exam

    Science.gov (United States)

    Yuhong, Deng

    2013-01-01

    This article reviews policies for adding points on the College Entrance Examination. It analyzes the rationales and specific implementation strategies of various policies for adding points on the entrance exam, as well as their advantages and pitfalls. Based on these observations and analysis, the author also offers policy recommendations on the…

  6. Controlling engineering project changes for multi-unit, multi-site standardized nuclear power plants

    International Nuclear Information System (INIS)

    Randall, E.; Boddeker, G.; McGugin, H.; Strother, E.; Waggoner, G.

    1978-01-01

    Multibillioin dollar multiple nuclear power plant projects have numerous potential sources of engineering changes. The majority of these are internally generated changes, client generated changes, and changes from construction, procurement, other engineering organizations, and regulatory organizations. For multiunit, multisite projects, the use of a standardized design is cost effective. Engineering changes can then be controlled for a single standardized design, and the unit or site unique changes can be treated as deviations. Once an effective change procedure is established for change control of the standardized design, the same procedures can be used for control of unit or site unique changes

  7. A Brief Review of Nuclear Electronics Standards Past, Present and Future

    International Nuclear Information System (INIS)

    Larsen, Ray S.

    2001-01-01

    Modular Nuclear Instrument Standards have played a key role in U.S. Department of Energy National Laboratories and similar scientific laboratories worldwide for more than three decades. The scientific and engineering efficiency and economic benefits have been well documented. Standards are constantly evolving with the introduction of new technologies and the present is a time of rapid change. This paper gives a brief overview of past developments and attempts to identify areas of possible opportunities for renewed standardization efforts to meet future challenges

  8. 78 FR 41907 - Effluent Limitations Guidelines and Standards for the Steam Electric Power Generating Point...

    Science.gov (United States)

    2013-07-12

    ...-0209] RIN 2040-AF14 Effluent Limitations Guidelines and Standards for the Steam Electric Power... proposed rule entitled, ``Effluent Limitations Guidelines and Standards for the Steam Electric Power....regulations.gov or in hard copy at the Water Docket in the EPA Docket Center, EPA/DC, EPA West, Room 3334...

  9. Analytical solution of point kinetics equations for linear reactivity variation during the start-up of a nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Palma, Daniel A.P. [CEFET QUIMICA de Nilopolis/RJ, 21941-914 Rio de Janeiro (Brazil)], E-mail: agoncalves@con.ufrj.br; Martinez, Aquilino S.; Goncalves, Alessandro C. [COPPE/UFRJ - Programa de Engenharia Nuclear, Rio de Janeiro (Brazil)

    2009-09-15

    The analytical solution of point kinetics equations with a group of delayed neutrons is useful in predicting the variation of neutron density during the start-up of a nuclear reactor. In the practical case of an increase of nuclear reactor power resulting from the linear insertion of reactivity, the exact analytical solution cannot be obtained. Approximate solutions have been obtained in previous articles, based on considerations that need to be verifiable in practice. In the present article, an alternative analytic solution is presented for point kinetics equations in which the only approximation consists of disregarding the term of the second derivative for neutron density in relation to time. The results proved satisfactory when applied to practical situations in the start-up of a nuclear reactor through the control rods withdraw.

  10. Analytical solution of point kinetics equations for linear reactivity variation during the start-up of a nuclear reactor

    International Nuclear Information System (INIS)

    Palma, Daniel A.P.; Martinez, Aquilino S.; Goncalves, Alessandro C.

    2009-01-01

    The analytical solution of point kinetics equations with a group of delayed neutrons is useful in predicting the variation of neutron density during the start-up of a nuclear reactor. In the practical case of an increase of nuclear reactor power resulting from the linear insertion of reactivity, the exact analytical solution cannot be obtained. Approximate solutions have been obtained in previous articles, based on considerations that need to be verifiable in practice. In the present article, an alternative analytic solution is presented for point kinetics equations in which the only approximation consists of disregarding the term of the second derivative for neutron density in relation to time. The results proved satisfactory when applied to practical situations in the start-up of a nuclear reactor through the control rods withdraw.

  11. Methodology to evaluate the site standard seismic motion to a nuclear facility

    International Nuclear Information System (INIS)

    Soares, W.A.

    1983-01-01

    For the seismic design of nuclear facilities, the input motion is normally defined by the predicted maximum ground horizontal acceleration and the free field ground response spectrum. This spectrum is computed on the basis of records of strong motion earthquakes. The pair maximum acceleration-response spectrum is called the site standard seismic motion. An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic principles of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; available methodologies and recommended procedures to evaluate the site standard seismic motion. (Author) [pt

  12. Register of international standard NP on IT based wireless application in nuclear power plants

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, I. W.; Choi, Y. S.; Lee, J. C.

    2011-04-01

    DC draft of standard technical report for wireless applications in NPP is developed, which is a Korean IT technologies. Wireless technologies are forwardwd to converging technologies nuclear and IT area. These technologies are supported to reduce vulnerability against cyber attacks and are forwarded to international standards which met with the nuclear environment requirements. DC draft of standard technical report is provided and circulated. Korean experts participate in Plenary meeting for IEC TC45/SC45A and intermediate meeting for IEC SC45A/WGA3 and 9. Korean expert takes the chair of wireless session at ANS winter conference. Visible light communication is experimented for feasibility study on reducing vulnerability against cyber attacks. VLC is capable of robust wireless communication against cyber attacks. This is suggested to describe a method for technical report. Issue DTR for wireless applications in NPP in 2012

  13. Secondary standard dosimetry laboratory Saraykoy Nuclear Research and Training Center Ankara, Turkey

    International Nuclear Information System (INIS)

    Okruhlica, P.

    2014-01-01

    Turkish Saraykoy Nuclear Research and Training Center (SANA) was founded in 2005. In 2014 the company PTW Freiburg in cooperation with VF Cerna Hora started the construction of a comprehensive national metrology laboratories of ionizing radiation 'Secondary Standard Dosimetry Laboratory' (SSDL). The laboratory will be located in the area of 'Saraykoy Nuclear Research and Training Center' in Ankara in Turkey. SSDL will be equipped with metrology departments for calibration and measurement of standard required quantities of metrology of ionizing radiation: - Neutron workplace; Gamma workplace (low-energy X-ray, gamma Standard Cs-137 and high dose rate, Co-60); - Beta workplace; - Control system of metrology laboratories and irradiation VF DARS; - Radiation monitoring system VF RMS; - Camera and security system; - Measuring instruments (ionization chambers, electrometers, monitors for environmental measurements ...) with the appropriate phantoms and other systems.

  14. Scan-To Output Validation: Towards a Standardized Geometric Quality Assessment of Building Information Models Based on Point Clouds

    Science.gov (United States)

    Bonduel, M.; Bassier, M.; Vergauwen, M.; Pauwels, P.; Klein, R.

    2017-11-01

    The use of Building Information Modeling (BIM) for existing buildings based on point clouds is increasing. Standardized geometric quality assessment of the BIMs is needed to make them more reliable and thus reusable for future users. First, available literature on the subject is studied. Next, an initial proposal for a standardized geometric quality assessment is presented. Finally, this method is tested and evaluated with a case study. The number of specifications on BIM relating to existing buildings is limited. The Levels of Accuracy (LOA) specification of the USIBD provides definitions and suggestions regarding geometric model accuracy, but lacks a standardized assessment method. A deviation analysis is found to be dependent on (1) the used mathematical model, (2) the density of the point clouds and (3) the order of comparison. Results of the analysis can be graphical and numerical. An analysis on macro (building) and micro (BIM object) scale is necessary. On macro scale, the complete model is compared to the original point cloud and vice versa to get an overview of the general model quality. The graphical results show occluded zones and non-modeled objects respectively. Colored point clouds are derived from this analysis and integrated in the BIM. On micro scale, the relevant surface parts are extracted per BIM object and compared to the complete point cloud. Occluded zones are extracted based on a maximum deviation. What remains is classified according to the LOA specification. The numerical results are integrated in the BIM with the use of object parameters.

  15. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Science.gov (United States)

    2010-01-01

    ... Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FOR NUCLEAR POWER PLANTS Pt. 52, App. N Appendix N to Part 52—Standardization of Nuclear Power Plant... that the applicant wishes to have the application considered under 10 CFR part 52, appendix N, and must...

  16. Development of point Kernel radiation shielding analysis computer program implementing recent nuclear data and graphic user interfaces

    International Nuclear Information System (INIS)

    Kang, S.; Lee, S.; Chung, C.

    2002-01-01

    There is an increasing demand for safe and efficient use of radiation and radioactive work activity along with shielding analysis as a result the number of nuclear and conventional facilities using radiation or radioisotope rises. Most Korean industries and research institutes including Korea Power Engineering Company (KOPEC) have been using foreign computer programs for radiation shielding analysis. Korean nuclear regulations have introduced new laws regarding the dose limits and radiological guides as prescribed in the ICRP 60. Thus, the radiation facilities should be designed and operated to comply with these new regulations. In addition, the previous point kernel shielding computer code utilizes antiquated nuclear data (mass attenuation coefficient, buildup factor, etc) which were developed in 1950∼1960. Subsequently, the various nuclear data such mass attenuation coefficient, buildup factor, etc. have been updated during the past few decades. KOPEC's strategic directive is to become a self-sufficient and independent nuclear design technology company, thus KOPEC decided to develop a new radiation shielding computer program that included the latest regulatory requirements and updated nuclear data. This new code was designed by KOPEC with developmental cooperation with Hanyang University, Department of Nuclear Engineering. VisualShield is designed with a graphical user interface to allow even users unfamiliar to radiation shielding theory to proficiently prepare input data sets and analyzing output results

  17. An Entry Point of the Emergency Response Robot for Management of Severe Accident of the Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Jaiwan; Jeong, Kyungmin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    In this paper, from the view point of DID (defense-in depth), we discuss the entry point of the nuclear emergency response robot to cope with a nuclear disaster. A Japanese nuclear disaster preparedness robot system was developed, after the JCO criticality accident in 1999, to cope with INES (International Nuclear and Radiological Event Scale) Level 3 serious incidents. INES Level 3 means the loss of DID (defense-in-depth) functions. It also indicates that ESF (engineered safety features) and ECCS (emergency core cooling system) resources, which are used to prevent serious incidents from escalating to severe accidents (core melt-down), have been almost exhausted. In the unit 1 reactor accident of Fukushima Daiichi Nuclear Power Plant, escalation from INES Level 1 (Out of Limiting Condition for Operation) to INES Level 5 (serious core melting-down) took less than two hours. Major facts are briefly described here in based on data gathered immediately after the tsunami over Fukushima Daiichi Nuclear Power Plant. Ο 15:35 on March 11, 2nd tsunami arrived. - 15:37, SBO (station black out) Ο 15:42, Interprets as a SBO (INES Level 1) - Loss of DC power for Instrumentation (Unknown of reactor water level) Ο 16:36, Loss of ECCS function (INELS Level 5) (Entry into a BDBA status) The Moni ROBO-A robot of the Japan Nuclear Safety Technology Center (NUSTEC) was a nuclear disaster preparedness robot developed after the JCO criticality accident. It was the only robot that had been steadily maintained and was available at the time of the Fukushima Daiichi Nuclear Power Plant accident. However, it was not helpful in mitigating the accident because it is assumed to have arrived at J-Village after the accident had been escalated to INES Level 5 or higher. Based on the paper by S. Kawatsuma of JAEA and response data gathered immediately after the tsunami, it is estimated that the NUSTEC's Moni ROBO-A arrived at J-Village after the designed entry point for INES Level 3

  18. Development of standard technical report on using and selecting wireless device in nuclear power plants

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, J. W.

    2011-11-01

    1. Purpose · Development of IEC technical report on wireless device using in nuclear power plants 2. Contents · IEC technical reports of draft for circulation and final draft for next planary meeting · Case study on experiment of wireless devices 3. Implementation methods · Preparation of first draft with experts group, its circulation, discussions on the results of the circulation · Organizing three teams such as preparation, reviews and experiment 4. Results · Maintenance cost will be reduced with application of the wireless technologies in nuclear power plants · Commercial wireless devices will be developed before standard is issued

  19. Development of the nuclear plant analyzer for Korean standard Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Shin Hwan; Kim, Hyeong Heon; Song, In Ho; Hong, Eon Yeong; Oh, Yeong Taek [Korea Power Engineering Company Inc., Yongin (Korea, Republic of)

    2000-12-15

    The purpose of this study is to develop an NPA for the Ulchin Nuclear Power Plant Unit 3 and 4, the first KSNP type plant. In this study, the process model simulating the overall plant systems, GUI and simulation executive which provide the functions of an engineering simulator were developed, and the NPA was completed by integrating them. The contents and the scope of this study are as follows : main feedwater system, auxiliary feedwater system, Chemical and Volume Control System(CVCS), Safety Injection System(SIS), Shutdown Cooling System(SCS), electric power supply system, Core Protection Calculator(CPC), various plant control system, development of the graphics screens for each system, real-time simulation, simulation control for the enhancement of functional capabilities, user friendly GUI, collection of the design and operating data, establishment of the NPA database, integration of the GUI and simulation control program with process model, collection of the data for the verification and validation of the developed NPA, collection of the plant test data, collection and review of the results of other computer codes, verification of the simulation accuracy by comparing the NPA results with the actual plant data, validation of the simulation capability of the NPA, comparison against available data from other analysis suing different computer codes.

  20. Development opportunities for communities: a point of view from the Canadian association of nuclear host communities

    International Nuclear Information System (INIS)

    Kraemer, L.

    2003-01-01

    L. Kraemer, Chairperson, Canadian Association for Nuclear Host Communities (CANHC), and Mayor of Kincardine, the host community of the Bruce nuclear power station, brought forward some 'grass roots ideals' of elected officials. The CANHC was recently created in recognition of the need for nuclear host communities to come together to engage not only the nuclear industry, but provincial and federal government as well, in a public dialogue. This association will champion host community needs as the new option-weighing process goes forward. It was a disappointment that the association did not receive a seat on the WMO board. With the new NFW Act, geological disposal of spent fuel waste is no longer a foregone conclusion, and the communities woke up to the possibility that waste now cooling within the nuclear power station area may potentially remain there for a much longer term. Even if these wastes are one day transported away from reactor sites, long-term storage on site needs attention. Mayor Kraemer views that a community not currently hosting a nuclear installation would volunteer to receive waste only on economic motives. Current host communities concentrate knowledge of nuclear operations and issues. Mayor Kraemer then recounted his own constituents' perceptions of the ongoing siting process for a low- and intermediate-level nuclear waste storage facility in Kincardine. He highlighted the importance of mutual co-operation between the nuclear industry and the municipality to 'debunk public hysteria', characterising 'fear' as 'False Expectations Appearing Real'. A Memorandum of Understanding has been developed between his municipal government and the local nuclear station, foreseeing elements of public education, safety and management methodology. In Mayor Kraemer's view, making an active investment in waste management solutions at the local level can realize the economic aspirations of both the community and the nuclear sector. (author)

  1. Nuclear spin dynamics in double quantum dots : Fixed points, transients, and intermittency

    NARCIS (Netherlands)

    Rudner, M.S.; Koppens, F.H.L.; Folk, J.A.; Vandersypen, L.M.K.; Levitov, L.S.

    2011-01-01

    Transport through spin-blockaded quantum dots provides a means for electrical control and detection of nuclear spin dynamics in the host material. Although such experiments have become increasingly popular in recent years, interpretation of their results in terms of the underlying nuclear spin

  2. 77 FR 112 - Effluent Limitations Guidelines and Standards for the Construction and Development Point Source...

    Science.gov (United States)

    2012-01-03

    .../L of TSS while the peak concentration discharged from the passive sand filter \\2\\ after the basin... two-day period. Effluent turbidity from one passive sand filter during this storm ranged from approximately 50 to 375 NTU, with 20 of the 24 data points below 200 NTU. For a second passive sand filter...

  3. Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal. 1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations. 1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams. 1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams. 1.5 This standard does not purport to address ...

  4. 40 CFR 414.111 - Toxic pollutant standards for indirect discharge point sources.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS ORGANIC CHEMICALS, PLASTICS, AND SYNTHETIC FIBERS Indirect... reduction of these pollutants. This determination must be based upon a review of relevant engineering... Zinc for Rayon Fiber Manufacture that uses the viscose process and Acrylic Fiber Manufacture that uses...

  5. A scheme for the audit of scientific and technological standards in clinical nuclear medicine

    International Nuclear Information System (INIS)

    Perkins, A.C.; Jarritt, P.H.

    2002-01-01

    Aim: Audit is the process whereby the quality of a service is monitored and optimised. It forms an essential component of the quality assurance process, whether by self-assessment or by external peer review. In the UK the British Nuclear Medicine Society (BNMS) has undertaken external organisational audit of departments providing clinical nuclear medicine services. This work aimed to develop a more thorough and service specific process for the audit of scientific and technological standards in nuclear medicine. Materials and Methods: The audit process has been implemented using written audit documents to facilitate the audit procedure. A questionnaire forms part of the formal documentation for audit of the scientific and technical standards of a clinical service. Scientific and technical standards were derived from a number of sources including legal requirements, regulatory obligations, notes for guidance, peer reviewed publications and accepted good clinical practice (GCP). Results: The audit process graded the standards of an individual department according to legal or safety requirements (Grade A), good practice (Grade B) and desirable aspects of service delivery (Grade C). The standards have been allocated into eight main categories. These are: Instrumentation; Software and data protection; Electrical Safety; Mechanical Safety; Workstation Safety; The Control of Substances Hazardous to Health (COSHH); Radiation Protection; Scientific and Technical staffing levels. During the audit visit a detailed inspection of clinical and laboratory areas and department written documentation is also necessary to validate the data obtained. Conclusion: The printed scheme now provides a means for external audit or self-assessment. There should be evidence of a well-organised and safe environment for both patients and staff. Health and Safety legislation requires written local rules and these records should be available to demonstrate the standard of service provision. Other

  6. Analysis of the nine-point finite difference approximation for the heat conduction equation in a nuclear fuel element

    International Nuclear Information System (INIS)

    Kadri, M.

    1983-01-01

    The time dependent heat conduction equation in the x-y Cartesian geometry is formulated in terms of a nine-point finite difference relation using a Taylor series expansion technique. The accuracy of the nine-point formulation over the five-point formulation has been tested and evaluated for various reactor fuel-cladding plate configurations using a computer program. The results have been checked against analytical solutions for various model problems. The following cases were considered in the steady-state condition: (a) The thermal conductivity and the heat generation were uniform. (b) The thermal conductivity was constant, the heat generation variable. (c) The thermal conductivity varied linearly with the temperature, the heat generation was uniform. (d) Both thermal conductivity and heat generation vary. In case (a), approximately, for the same accuracy, 85% fewer grid points were needed for the nine-point relation which has a 14% higher convergence rate as compared to the five-point relation. In case (b), on the average, 84% fewer grid points were needed for the nine-point relation which has a 65% higher convergence rate as compared to the five-point relation. In case (c) and (d), there is significant accuracy (91% higher than the five-point relation) for the nine-point relation when a worse grid was used. The numerical solution of the nine-point formula in the time dependent case was also more accurate and converges faster than the numerical solution of the five-point formula for all comparative tests related to heat conduction problems in a nuclear fuel element

  7. Fundamental challenging problems for developing new nuclear safety standard computer codes

    International Nuclear Information System (INIS)

    Wong, P.K.; Wong, A.E.; Wong, A.

    2005-01-01

    Based on the claims of the US Basic patents number 5,084,232; 5,848,377 and 6,430,516 that can be obtained from typing the Patent Numbers into the Box of the Web site http://164.195.100.11/netahtml/srchnum.htm and their associated published technical papers having been presented and published at International Conferences in the last three years and that all these had been sent into US-NRC by E-mail on March 26, 2003 at 2:46 PM., three fundamental challenging problems for developing new nuclear safety standard computer codes had been presented at the US-NRC RIC2003 Session W4. 2:15-3:15 PM. at the Washington D.C. Capital Hilton Hotel, Presidential Ballroom on April 16, 2003 in front of more than 800 nuclear professionals from many countries worldwide. The objective and scope of this paper is to invite all nuclear professionals to examine and evaluate all the current computer codes being used in their own countries by means of comparison of numerical data from these three specific openly challenging fundamental problems in order to set up a global safety standard for all nuclear power plants in the world. (authors)

  8. Major Cyber threat on Nuclear Facility and Key Entry Points of Malicious Codes

    International Nuclear Information System (INIS)

    Shin, Ickhyun; Kwon, Kookheui

    2013-01-01

    Cyber security incident explicitly shows that the domestic intra net system which is not connected to the Internet can be compromised by the USB based mal ware which was developed by the state-sponsored group. It also tells that the actor for cyber-attack has been changed from script kiddies to state's governments and the target has been changed to nation's main infrastructures such as electricity, transportation and etc. Since the cyber sabotage on nuclear facility has been proven to be possible and can be replicated again with same method, the cyber security on nuclear facility must be strengthened. In this paper, it is explained why the malicious code is the one of the biggest cyber threat in nuclear facility's digital I and C(Instrumentation and Controls) system by analyzing recent cyber attacks and well-known malicious codes. And a feasible cyber attack scenario on nuclear facility's digital I and C system is suggested along with some security measures for prevention of malicious code. As experienced from the cyber sabotage on Iranian nuclear facility in 2010, cyber attack on nuclear facility can be replicated by infecting the computer network with malicious codes. One of the cyber attack scenario on nuclear digital I and C computer network with using malicious code was suggested to help security manager establishing cyber security plan for prevention of malicious code. And some security measures on prevention of malicious code are also provided for reference

  9. Standard specification for nuclear-grade silver-indium-cadmium alloy

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2003-01-01

    1.1 This specification covers silver-indium-cadmium alloy for use as a control material in light-water nuclear reactors. 1.2 The scope of this specification excludes the use of this material in applications where material strength of this alloy is a prime requisite. Also, this material must be protected from the primary water by a corrosion and wear resistant cladding. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

  10. Standard protocol for conducting pre-operational environmental surveillance around nuclear facilities

    International Nuclear Information System (INIS)

    Hegde, A.G.; Verma, P.C.; Rajan, M.P.

    2009-02-01

    This document presents the standard procedures for evaluation of site specific environmental transfer factors around NPP sites. The scope of this document is to provide standard protocol to be followed for conducting pre-operational environmental surveillance around nuclear facilities. Such surveillances have been proposed to be carried out by university professionals under DAE-BRNS projects. This document contains a common methodology in terms of sampling, processing, measurements and analysis of elemental/radionuclides, while keeping the site specific requirements also in place. (author)

  11. Environmental Standard Review Plan for the review of license renewal applications for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    O' Brien, J.; Kim, T.J.; Reynolds, S.

    1991-08-01

    The Environmental Standard Review Plan for the Review of License Applications for Nuclear Power Plants (ESRP-LR) is to be used by the NRC staff when performing environmental reviews of applications for the renewal of power reactor licenses. The use of the ESRP-LR provides a framework for the staff to determine whether or not environmental issues important to license renewal have been identified and the impacts evaluated and provides acceptance standards to help the reviewers comply with the National Environmental Policy Act.

  12. Standard protocol for demographic and epidemiological survey to be carried out for nuclear facilities

    International Nuclear Information System (INIS)

    Joshi, M.L.; Datta, D.; Singh, Jitendra; Sardhi, I.V.; Verma, P.C.

    2007-11-01

    This document presents the standard procedures for conducting demographic and epidemiological studies for nuclear facilities. These studies are required to be carried out to prepare baseline data, the impact of the facility and the risk factors for the population residing in the vicinity of facility. This document includes the basic elements of these type surveys, their methodology and statistical analysis of the data collected during demographic and epidemiological surveillance. (author)

  13. A wearable point-of-care system for home use that incorporates plug-and-play and wireless standards.

    Science.gov (United States)

    Yao, Jianchu; Schmitz, Ryan; Warren, Steve

    2005-09-01

    A point-of-care system for continuous health monitoring should be wearable, easy to use, and affordable to promote patient independence and facilitate acceptance of new home healthcare technology. Reconfigurability, interoperability, and scalability are important. Standardization supports these requirements, and encourages an open market where lower product prices result from vendor competition. This paper first discusses candidate standards for wireless communication, plug-and-play device interoperability, and medical information exchange in point-of-care systems. It then addresses the design and implementation of a wearable, plug-and-play system for home care which adopts the IEEE 1073 Medical Information Bus (MIB) standards, and uses Bluetooth as the wireless communication protocol. This standards-based system maximizes user mobility by incorporating a three-level architecture populated by base stations, wearable data loggers, and wearable sensors. Design issues include the implementation of the MIB standards on microcontroller-driven embedded devices, low power consumption, wireless data exchange, and data storage and transmission in a reconfigurable body-area network.

  14. PHITS code improvements by Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority

    International Nuclear Information System (INIS)

    Goko, Shinji

    2017-01-01

    As for the safety analysis to be carried out when a nuclear power company applies for installation permission of facility or equipment, business license, design approval etc., the Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority continuously conducts safety research for the introduction of various technologies and their improvement in order to evaluate the adequacy of this safety analysis. In the field of the shielding analysis of nuclear fuel transportation materials, this group improved the code to make PHITS applicable to this field, and has been promoting the improvement as a tool used for regulations since FY2013. This paper introduced the history and progress of this safety research. PHITS 2.88, which is the latest version as of November 2016, was equipped with the automatic generation function of variance reduction parameters [T-WWG] etc., and developed as the tool equipped with many effective functions in practical application to nuclear power regulations. In addition, this group conducted the verification analysis against nuclear fuel packages, which showed a good agreement with the analysis by MCNP, which is extensively used worldwide and abundant in actual results. It also shows a relatively good agreement with the measured values, when considering differences in analysis and measurement. (A.O.)

  15. Standardization and Economics of Nuclear Spacecraft, Final Report, Phase I, Sense Study

    Energy Technology Data Exchange (ETDEWEB)

    1973-03-01

    Feasibility and cost benefits of nuclear-powered standardized spacecraft are investigated. The study indicates that two shuttle-launched nuclear-powered spacecraft should be able to serve the majority of unmanned NASA missions anticipated for the 1980's. The standard spacecraft include structure, thermal control, power, attitude control, some propulsion capability and tracking, telemetry, and command subsystems. One spacecraft design, powered by the radioisotope thermoelectric generator, can serve missions requiring up to 450 watts. The other spacecraft design, powered by similar nuclear heat sources in a Brayton-cycle generator, can serve missions requiring up to 21000 watts. Design concepts and trade-offs are discussed. The conceptual designs selected are presented and successfully tested against a variety of missions. The thermal design is such that both spacecraft are capable of operating in any earth orbit and any orientation without modification. Three-axis stabilization is included. Several spacecraft can be stacked in the shuttle payload compartment for multi-mission launches. A reactor-powered thermoelectric generator system, operating at an electric power level of 5000 watts, is briefly studied for applicability to two test missions of divers requirements. A cost analysis indicates that use of the two standardized spacecraft offers sizable savings in comparison with specially designed solar-powered spacecraft. There is a duplicate copy.

  16. Applicability of ISO 9001: 2000 standard to design and research activities in nuclear objectives and installations

    International Nuclear Information System (INIS)

    Stamatopol, M.; Patticu, C.

    2001-01-01

    The ISO 9001: 2000 standard contains the results of the latest studies concerning the design and implementation of quality management systems. The continuous improvement of these systems required a new approach, namely, the process-based approach. A process-based model of quality management is presented in terms of client request, input data, management responsibility, resource management, product realisation, measurement / analysis and optimization, product, output data and client request fulfilment. Thus, the quality management system becomes an ensemble of interconnected or interacting processes. Consequently, to implement such a system the necessary processes have to be identified and their ISO 9001: 2000 standard based management ensured. Process based approach also allows better evidencing the input and output data specific to each process. Such an approach grants a wider applicability to the design and research activities in nuclear objectives and installations. This work aims at identifying additional requirements implied in design and research activities in nuclear field, as stipulated in the following standards / documents: - IAEA SG Q8 'Quality assurance in research and development'; - IAEA SG Q10 'Quality assurance in design'; - CAN / CSA N 286.2 - 00 'Design Quality Assurance for Nuclear Power Plants'; CAN 3 - CSA Z 299.1 'Quality Assurance Program - Category 1'; - NQA - 1, SUPPLEMENT 3S-1 'Supplementary requirements for design control'

  17. Education and public information on nuclear power from a student's point of view

    International Nuclear Information System (INIS)

    Toma, Ruxandra Cristina; Arsene, Radu Cristian; Nistor, George Cristian; Tiba, Bogdan Florin; Prisecaru, Ilie

    2008-01-01

    By this paper we try to answer the frequently asked question among the people related to the nuclear field on how to improve actual communication ways with the general public and how to prove them that nuclear power is a component of the sustainable development. The complexity of this domain makes it more difficult to be understood by people who have no connection with it. We need to use all the possible means of communication to spread out our message. To change this situation and promote this domain we have made some suggestions like working with children, students, teachers, scientists and mass-media. The acceptance of nuclear power may not be easy to achieve but with appropriate education and means of information we hope people will realize that nuclear is the key to their continuous need of energy, even if they don't see it yet. (authors)

  18. The point of view of religious authorities and philosophers on nuclear energy - Judaism

    International Nuclear Information System (INIS)

    Anon.

    2016-01-01

    Judaism considers sciences and technological progress as tools to allow people to reach spiritual values, more easily. Nuclear technologies are seen as a valuable element of modern life because they provide huge quantities of energy through nuclear power plants and efficient diagnostic or treatment methods in nuclear medicine. All these advantages must be used to the well-being of the 7 billions people living on earth. The limit imposed on technologies is the respect of life and nature as they were created by God. The important feedback experience on nuclear power must allow people to weigh its pros and cons more clearly without being trapped in an ideology. Man appears to be the manager of a property that does not belong to him and he has to manage it with a benevolent attitude for the future generations. (A.C.)

  19. IAEA and NPT - The verification challenge. Challenging nuclear issues point the way forward

    International Nuclear Information System (INIS)

    Lodding, Jan; Rauf, Tariq

    2005-01-01

    Five years ago, member States of the global Treaty on the Non-Proliferation of Nuclear Weapons (NPT) agreed on a number of forward-looking elements for non-proliferation and disarmament and for the peaceful uses of nuclear technology. This was widely hailed as a major accomplishment for the global nuclear non-proliferation regime and for multilateral cooperation in this context. The NPT regime - a brainchild of the Cold War era - seemed strengthened and better adapted to meet the challenges of the 21st Century. The elements were contained in the Final Document adopted by consensus of the 187 States parties at the 2000 NPT Review Conference, the sixth such Conference since the NPT's entry into force in 1970. Among 62 references to IAEA safeguards in the Final Document, the Agency's verification system was acknowledged as a fundamental pillar of the nuclear non-proliferation regime, one that plays an indispensable role in the Treaty's implementation and helps to create an environment conducive to nuclear disarmament and to cooperation in the peaceful uses of nuclear energy. The NPT States recognized that IAEA safeguards provide assurance of compliance and assist States In demonstrating compliance with their relevant undertakings. They recognized the IAEA as the competent authority responsible for verifying and assuring compliance with safeguards agreements, and expressed its conviction that nothing should be done to undermine its authority in this regard. Member States having concerns regarding non-compliance with safeguards agreements were called upon to direct such concerns, along with supporting evidence to the Agency for its consideration. The Final Document also supported steps for strengthening the IAEA's safeguards system and for the possible application of IAEA verification in the context of future nuclear disarmament. In the past few years, some widely publicized nuclear issues have highlighted the IAEA's vital verification work in the context of the NPT

  20. Standard for administration of stable iodine pilulae. Standard of the nuclear safety commission, action for accident in TEPCO Fukushima-1 and recent European trends

    International Nuclear Information System (INIS)

    Ishihara, Hiroshi

    2011-01-01

    Preventive taking of stable-iodine tablets is effective to avoid thyroid gland disorder due to internal exposure to the radioactive iodine if radioactive iodine is released outside by any nuclear accident. In Japan, the Nuclear Safety Commission proposed the standard of the preventive taking in 2002, and, at the Fukushima Daiichi nuclear disaster, the head of the local task force instructed to take on the recommendation from the Commission. Author described the action principle of stable-iodine tablets, present concept for the preventive taking, recent change of the concept in Europe for the preventive taking, and some precepts which have shown in past Fukushima Daiichi nuclear disaster. (J.P.N.)

  1. Indian Point Nuclear Generating Plant Unit No. 3 (Docket No. 50-286): Final environmental statement: Volume 2

    International Nuclear Information System (INIS)

    1975-02-01

    This document contains nine appendices to Volume I, The Final Environmental Impact Statement for the Indian Point Nuclear Generating Plant Unit Number Three. Topics covered include thermal discharges to the Hudson River; supplemental information relating to biological models; radiation effects on aquatic biota; conditions, assumptions, and parameters used in calculating radioactive releases; meteorology for radiological dispersion calculations; life history information of important fish species in the Hudson River near Indian Point; additional information on cooling towers considered as alternatives; data and calculations for assessment of predicted electrical demand; and comments on draft environmental statement

  2. Topical opinion paper - Apparent Discrepancies Between Nuclear and Conventional Seismic Standards

    International Nuclear Information System (INIS)

    Donald, John; Smith, Ian

    2003-01-01

    The differences between nuclear and conventional seismic standards are considered and their potential significance discussed. The approach to the design of nuclear facilities is appropriately both more rigorous and conservative than that required by conventional seismic standards and codes. For nuclear seismic design the requirements can be presented as assessment principles, e.g., NII SAPs or a safety guide e.g. IAEA; Seismic Design and Qualification for Nuclear Power Plants. The adoption of novel methods or designs are required to be supported by appropriate research and development with the ability to cite a precedent within the industry being a powerful endorsement. The method adopted must reliably predict the seismic response of the item to be qualified, including the seismic response of attached or supported Structures, Systems and Components. (SSC's) The traditional method adopted for seismic qualification by analysis has been based on linear elastic analyses. This is justified on the basis that the response is reliably predicted and realistic, provided that the elements remain elastic. In contrast the benefit of ductile behaviour of conventional structures within the design envelope has long been recognised and used as the basis to justify significant reductions in the seismic demand. Provided the acceptance criteria are met, the SAPs do not preclude and the IAEA safety guide specifically permits non linear behaviour within the design envelope for category 1 items. Both the current nuclear practice and the current conventional seismic standards can be classified as 'force based'. The displacement based approach, also referred to as performance based engineering (PBE), has been developed as a powerful tool in the evaluation and seismic retrofit of existing structures. This approach could be equally valid to the design of new structures and can be used to represent elastic or non linear behaviour although the full benefit will only be realised in the latter

  3. Normal values and standardization of parameters in nuclear cardiology: Japanese Society of Nuclear Medicine working group database.

    Science.gov (United States)

    Nakajima, Kenichi; Matsumoto, Naoya; Kasai, Tokuo; Matsuo, Shinro; Kiso, Keisuke; Okuda, Koichi

    2016-04-01

    As a 2-year project of the Japanese Society of Nuclear Medicine working group activity, normal myocardial imaging databases were accumulated and summarized. Stress-rest with gated and non-gated image sets were accumulated for myocardial perfusion imaging and could be used for perfusion defect scoring and normal left ventricular (LV) function analysis. For single-photon emission computed tomography (SPECT) with multi-focal collimator design, databases of supine and prone positions and computed tomography (CT)-based attenuation correction were created. The CT-based correction provided similar perfusion patterns between genders. In phase analysis of gated myocardial perfusion SPECT, a new approach for analyzing dyssynchrony, normal ranges of parameters for phase bandwidth, standard deviation and entropy were determined in four software programs. Although the results were not interchangeable, dependency on gender, ejection fraction and volumes were common characteristics of these parameters. Standardization of (123)I-MIBG sympathetic imaging was performed regarding heart-to-mediastinum ratio (HMR) using a calibration phantom method. The HMRs from any collimator types could be converted to the value with medium-energy comparable collimators. Appropriate quantification based on common normal databases and standard technology could play a pivotal role for clinical practice and researches.

  4. Report from the research committee of digital imaging standardization in nuclear medicine

    International Nuclear Information System (INIS)

    Nakamura, Yutaka; Ise, Toshihide; Isetani, Osamu; Ichihara, Takashi; Ohya, Nobuyoshi; Kanaya, Shinichi; Fukuda, Toshio; Horii, Hitoshi.

    1994-01-01

    Since digital scintillation camera systems were developed in 1982, digital imaging is rapidly replacing analog imaging. During the first year, the research committee of digital imaging standardization has collected and analyzed basic data concerning digital examination equipment systems, display equipments, films, and hardware and software techniques to determine items required for the standardization of digital imaging. During the second year, it has done basic phantom studies to assess digital images and analyzed the results from both physical and visual viewpoints. On the basis of the outcome of the research committee's activities and the nationwide survey, the draft of digital imaging standardization in nuclear medicine has been presented. In this paper. the analytical data of the two-year survey, made by the research committee of digital imaging standardization, are presented. The descriptions are given under the following four items: (1) standardization digital examination techniques, (2) standardization of display techniques, (3) the count and pixel of digital images, and (4) standardization of digital imaging techniques. (N.K.)

  5. Developing glovebox robotics to meet the national robot safety standard and nuclear safety criteria

    International Nuclear Information System (INIS)

    McMahon, T.T.; Sievers, R.H.

    1991-09-01

    Development of a glove box based robotic system by the Lawrence Livermore National Laboratory (LLNL) is reported. Safety issues addressed include planning to meet the special constraints of operations within a hazardous material glove box and with hostile environments, compliance with the current and draft national robotic system safety standards, and eventual satisfaction of nuclear material handling requirements. Special attention has been required for the revision to the robot and control system models which antedate adoption of the present national safety standard. A robotic test bed, using non-radioactive surrogates is being activated at the Lawrence Livermore National Laboratory to develop the material handling system and the process interfaces for future special nuclear material processing applications. Part of this effort is to define, test, and revise adequate safety controls to ensure success when the system is eventually deployed at a DOE site. The current system is primarily for demonstration and testing, but will evolve into the baseline configuration from which the production system is to be derived. This results in special hazards associated with research activities which may not be present on a production line. Nuclear safety is of paramount importance and has been successfully addressed for 50 years in the DOE weapons production complex. It carries its particular requirements for robot systems and manual operations, as summarized below: Criticality must be avoided (materials cannot consolidate or accumulate to approach a critical mass). Radioactive materials must be confined. The public and workers must be protected from accountable radiation exposure. Nuclear material must be readily retrievable. Nuclear safety must be conclusively demonstrated through hazards analysis. 7 refs

  6. Calculation of electron and isotopes dose point kernels with FLUKA Monte Carlo code for dosimetry in nuclear medicine therapy

    CERN Document Server

    Mairani, A; Valente, M; Battistoni, G; Botta, F; Pedroli, G; Ferrari, A; Cremonesi, M; Di Dia, A; Ferrari, M; Fasso, A

    2011-01-01

    Purpose: The calculation of patient-specific dose distribution can be achieved by Monte Carlo simulations or by analytical methods. In this study, FLUKA Monte Carlo code has been considered for use in nuclear medicine dosimetry. Up to now, FLUKA has mainly been dedicated to other fields, namely high energy physics, radiation protection, and hadrontherapy. When first employing a Monte Carlo code for nuclear medicine dosimetry, its results concerning electron transport at energies typical of nuclear medicine applications need to be verified. This is commonly achieved by means of calculation of a representative parameter and comparison with reference data. Dose point kernel (DPK), quantifying the energy deposition all around a point isotropic source, is often the one. Methods: FLUKA DPKS have been calculated in both water and compact bone for monoenergetic electrons (10-3 MeV) and for beta emitting isotopes commonly used for therapy ((89)Sr, (90)Y, (131)I, (153)Sm, (177)Lu, (186)Re, and (188)Re). Point isotropic...

  7. New IEEE 11073 Standards for interoperable, networked Point-of-Care Medical Devices.

    Science.gov (United States)

    Kasparick, Martin; Schlichting, Stefan; Golatowski, Frank; Timmermann, Dirk

    2015-08-01

    Surgical procedures become more and more complex and the number of medical devices in an operating room (OR) increases continuously. Today's vendor-dependent solutions for integrated ORs are not able to handle this complexity. They can only form isolated solutions. Furthermore, high costs are a result of vendor-dependent approaches. Thus we present a service-oriented device communication for distributed medical systems that enables the integration and interconnection between medical devices among each other and to (medical) information systems, including plug-and-play functionality. This system will improve patient's safety by making technical complexity of a comprehensive integration manageable. It will be available as open standards that are part of the IEEE 11073 family of standards. The solution consists of a service-oriented communication technology, the so called Medical Devices Profile for Web Services (MDPWS), a Domain Information & Service Model, and a binding between the first two mechanisms. A proof of this concept has been done with demonstrators of real world OR devices.

  8. Specification for modular plug-in unit and standard 19-inch rack mounting unit based on NIM standard (for electronic nuclear instruments)

    International Nuclear Information System (INIS)

    1978-01-01

    The object is to define standard dimensions of a modular system based on NIM standard and comprising the plug-in unit Type N specified in IEC Publication 482, Dimensions of Electronic Instrument Modules (for Nuclear Electronic Instruments), the corresponding 19-inch rack mounting unit Type NC (conforming to IEC Publication 297, Dimensions of Panels and Racks) and the associated connectors. (author)

  9. Communication analysis and strategy for nuclear from a university student's point of view

    Energy Technology Data Exchange (ETDEWEB)

    Park, Min Ji [Ewha Womans University, Seoul (Korea, Republic of)

    2016-05-15

    Public awareness survey on nuclear in 2015, 94.4% of the nuclear information access was done through advertising and news media. TV, internet, and radio was the main source for advertising media. The media coverage was achieved through the selection of newspapers, magazines, transport media, outdoor media, and etc. For public relations by using these media- press releases, press conferences, contribution, inviting journalists, self-produced promotional materials, distribution of materials, holding events- were conducted. A use of the internet takes up a minimal piece on public relations of nuclear energy. The internet media used were the, blogs, mobile, SNS, and etc. In this paper, analysis on current trend in advertisements and suggestions towards building a good relationship with the public will be introduced. A popular trend and the trend-based advertisement was briefly analyzed to derive some nuclear advertising ideas. Strategy sought some concrete measures for mobile applications for nuclear information, celebrity ambassadors and use of SNS, college education and vending machines. Suggested tactics are a part of author's ideas.

  10. Communication analysis and strategy for nuclear from a university student's point of view

    International Nuclear Information System (INIS)

    Park, Min Ji

    2016-01-01

    Public awareness survey on nuclear in 2015, 94.4% of the nuclear information access was done through advertising and news media. TV, internet, and radio was the main source for advertising media. The media coverage was achieved through the selection of newspapers, magazines, transport media, outdoor media, and etc. For public relations by using these media- press releases, press conferences, contribution, inviting journalists, self-produced promotional materials, distribution of materials, holding events- were conducted. A use of the internet takes up a minimal piece on public relations of nuclear energy. The internet media used were the, blogs, mobile, SNS, and etc. In this paper, analysis on current trend in advertisements and suggestions towards building a good relationship with the public will be introduced. A popular trend and the trend-based advertisement was briefly analyzed to derive some nuclear advertising ideas. Strategy sought some concrete measures for mobile applications for nuclear information, celebrity ambassadors and use of SNS, college education and vending machines. Suggested tactics are a part of author's ideas

  11. Species trees for spiny lizards (genus Sceloporus): identifying points of concordance and conflict between nuclear and mitochondrial data.

    Science.gov (United States)

    Leaché, Adam D

    2010-01-01

    Spiny lizards (genus Sceloporus) represent one of the most diverse and species rich clades of squamate reptiles in continental North America. Sceloporus contains 90+ species, which are partitioned into 21 species groups containing anywhere from one to 15 species. Despite substantial progress towards elucidating the phylogeographic patterns for many species of Sceloporus, efforts to resolve the phylogenetic relationships among the major species groups remain limited. In this study, the phylogenetic relationships of 53 species of Sceloporus, representing all 21 species groups, are estimated based on four nuclear genes (BDNF, PNN, R35, RAG-1; >3.3 kb) and contrasted with a new mitochondrial DNA genealogy based on six genes (12S, ND1, ND4, and the histidine, serine, and leucine tRNA genes; >2.5 kb). Species trees estimated from the nuclear loci using data concatenation or a coalescent-based inference method result in concordant topologies, but the coalescent approach provides lower resolution and support. When comparing nuclear versus mtDNA-based topologies for Sceloporus species groups, conflicting relationships outnumber concordant relationships. Incongruence is not restricted to weak or unresolved nodes as might be expected under a scenario of rapid diversification, but extends to conflicts involving strongly support clades. The points of concordance and conflict between the nuclear and mtDNA data are discussed, and arguments for preferring the species trees estimated from the multilocus nuclear data are presented.

  12. The nuclear controversy from the sociological and psychological points of view

    International Nuclear Information System (INIS)

    Scharioth, J.

    1977-01-01

    The nuclear controversy has recently taken a dynamic turn full of tensions. This is particularly true of the FRG where, after many years of continuous speedy development and the erection of the first large commercial power stations, a tough resistance movement of citizens' initiatives, expecially a radical opposition of some groups, has been growing over the past six months. Since the peaceful uses of nuclear energy were first embarked upon in the Federal Republic in the mid-fifties also the economic situation and the wishes and objectives of the working population have undergone major changes. While, in the sixties, most people sought high grade, qualitatively demanding jobs, a wish which was catered to very much by the fundamentally new technology of the utilization of nuclear energy, the two major goals of the working population, i.e., job security and job quality, have meanwhile changed positions on the scale of values. (orig./HP) [de

  13. An open, interoperable, transdisciplinary approach to a point cloud data service using OGC standards and open source software.

    Science.gov (United States)

    Steer, Adam; Trenham, Claire; Druken, Kelsey; Evans, Benjamin; Wyborn, Lesley

    2017-04-01

    High resolution point clouds and other topology-free point data sources are widely utilised for research, management and planning activities. A key goal for research and management users is making these data and common derivatives available in a way which is seamlessly interoperable with other observed and modelled data. The Australian National Computational Infrastructure (NCI) stores point data from a range of disciplines, including terrestrial and airborne LiDAR surveys, 3D photogrammetry, airborne and ground-based geophysical observations, bathymetric observations and 4D marine tracers. These data are stored alongside a significant store of Earth systems data including climate and weather, ecology, hydrology, geoscience and satellite observations, and available from NCI's National Environmental Research Data Interoperability Platform (NERDIP) [1]. Because of the NERDIP requirement for interoperability with gridded datasets, the data models required to store these data may not conform to the LAS/LAZ format - the widely accepted community standard for point data storage and transfer. The goal for NCI is making point data discoverable, accessible and useable in ways which allow seamless integration with earth observation datasets and model outputs - in turn assisting researchers and decision-makers in the often-convoluted process of handling and analyzing massive point datasets. With a use-case of providing a web data service and supporting a derived product workflow, NCI has implemented and tested a web-based point cloud service using the Open Geospatial Consortium (OGC) Web Processing Service [2] as a transaction handler between a web-based client and server-side computing tools based on a native Linux operating system. Using this model, the underlying toolset for driving a data service is flexible and can take advantage of NCI's highly scalable research cloud. Present work focusses on the Point Data Abstraction Library (PDAL) [3] as a logical choice for

  14. Temperature calibration procedure for thin film substrates for thermo-ellipsometric analysis using melting point standards

    Energy Technology Data Exchange (ETDEWEB)

    Kappert, Emiel J.; Raaijmakers, Michiel J.T.; Ogieglo, Wojciech; Nijmeijer, Arian; Huiskes, Cindy; Benes, Nieck E., E-mail: n.e.benes@utwente.nl

    2015-02-10

    Highlights: • Facile temperature calibration method for thermo-ellipsometric analysis. • The melting point of thin films of indium, lead, zinc, and water can be detected by ellipsometry. • In-situ calibration of ellipsometry hot stage, without using any external equipment. • High-accuracy temperature calibration (±1.3 °C). - Abstract: Precise and accurate temperature control is pertinent to studying thermally activated processes in thin films. Here, we present a calibration method for the substrate–film interface temperature using spectroscopic ellipsometry. The method is adapted from temperature calibration methods that are well developed for thermogravimetric analysis and differential scanning calorimetry instruments, and is based on probing a transition temperature. Indium, lead, and zinc could be spread on a substrate, and the phase transition of these metals could be detected by a change in the Ψ signal of the ellipsometer. For water, the phase transition could be detected by a loss of signal intensity as a result of light scattering by the ice crystals. The combined approach allowed for construction of a linear calibration curve with an accuracy of 1.3 °C or lower over the full temperature range.

  15. Special points of health physics in connection with the operation of a nuclear power plant

    International Nuclear Information System (INIS)

    Samuel, T.

    1981-01-01

    The paper covers the origin of the radioactivity in nuclear power plants, the type of sources (open or sealed) encountered, and their methods of measurement. It covers the problem of personnel dosimetry, including contamination and incorporation, and the administrative methods used to avoid these. It outlines a general work philosophy, as developed in an actual power plant. (orig./RW)

  16. Export and import provisions for nuclear materials and power plants, from the legal point of view

    International Nuclear Information System (INIS)

    Shapar, H.K.

    1975-01-01

    This paper provides a general review of the legal bases for and the administrative procedures involved in the export and import licensing of nuclear power reactors, fuels, and other nuclear materials by the United States. The basic statutory provisions and requirements are briefly described, and the requirement of an agreement for cooperation reviewed. The regulations of the Nuclear Regulatory Commission are covered in greater detail as they apply to the export and import of power reactors, nuclear fuels, source materials and byproduct materials. The intra-governmental procedures for review of an application for an export license are described in detail. Problems encountered in the administration of the law and regulations are described and the methods of resolving them are noted. The paper concludes with a brief account of three current topics, 1) the preparation of an environmental impact statement for export programs, 2) the situation with respect to the export licensing of component parts of reactors by the U.S. Department of Commerce, and 3) the shipment of plutonium by air. (orig.) [de

  17. The problem of nuclear wastes. A possible point of conflict between Mexico and the United States

    International Nuclear Information System (INIS)

    Rosas Poblano, A.

    1993-01-01

    The objectives of this research were: a) To analyse the problem of nuclear wastes, and the importance of their safe handling; b) To investigate the best and safest technologies for the treatment of radioactive wastes and two relevant international laws or regulations; c) To study whether the wastes produced in the United States represent an environmental problem for Mexico

  18. Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel and Transuranic Radioactive Wastes (40 CFR Part 191)

    Science.gov (United States)

    This regulation sets environmental standards for public protection from the management and disposal of spent nuclear fuel, high-level wastes and wastes that contain elements with atomic numbers higher than uranium (transuranic wastes).

  19. A common high standard for nuclear power plant exports: overview and analysis of the Nuclear Power Plant Exporters' Principles of Conduct

    International Nuclear Information System (INIS)

    Perkovich, George; Radzinsky, Brian

    2012-01-01

    At this time, there is no overarching global framework to regulate the development of the nuclear power industry. Laws concerning the export of nuclear technology vary across jurisdictions, and politically-binding arrangements such as the Nuclear Suppliers Group (NSG) help ensure that weapons-usable or dual-use technologies are not exported, but no single international regime or agreement manages the gamut of potential risks that may arise from the export of civilian nuclear power plants. Accordingly in 2008, the Carnegie Endowment for International Peace convened internationally-recognised experts in nuclear energy to begin a dialogue with nuclear power plant vendors about defining common criteria for the socially responsible export of nuclear power plants. The goal was to articulate a comprehensive set of principles and best practices that would raise the overall standard of practice for exports of nuclear power plants while enjoying widespread support and adherence. The outcome of this process is the Nuclear Power Plant Exporters' Principles of Conduct - an export-oriented code of conduct for nuclear power plant vendors. The Principles of Conduct help ensure that the participating companies will proceed with the sale of a new nuclear power plant only after a careful assessment of the legal, political, and technical contexts surrounding potential customers. It comprises six 'principles' that each address a major area of concern involved in the export of a nuclear power plant: safety, physical security, environmental protection and spent fuel management, systems of compensation for nuclear damage, non-proliferation and safeguards, and business ethics. The Principles of Conduct entail vendor responsibilities to apply specific standards or engage in certain practices before signing contracts and during the marketing and construction phases of a nuclear power plant export project. Conformity with the Principles of Conduct is voluntary and not-legally binding, but the

  20. 10 CFR Appendix N to Part 50 - Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate...

    Science.gov (United States)

    2010-01-01

    ... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FACILITIES Pt. 50, App.N Appendix N to Part 50—Standardization of Nuclear Power Plant Designs: Permits To..., apply to construction permits and operating licenses subject to this appendix N. 2. Applications for...

  1. Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. Volume 2. Radiological health and related standards for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Nero, A.V.; Wong, Y.C.

    1977-01-01

    This report summarizes the status and basis of radiation protection standards, with a view to identifying how they particularly apply to nuclear power plants. The national and international organizations involved in the setting of standards are discussed, paying explicit attention to their jurisdictions and to the considerations they use in setting standards. The routine and accidental radioactive emissions from nuclear power plants are characterized, and the effect of these emissions on ambient radiation levels is discussed. The state of information on the relationship between radiation exposures and health effects is summarized.

  2. ASTM STANDARD GUIDE FOR EVALUATING DISPOSAL OPTIONS FOR REUSE OF CONCRETE FROM NUCLEAR FACILITY DECOMMISSIONING

    International Nuclear Information System (INIS)

    Phillips, Ann Marie; Meservey, Richard H.

    2003-01-01

    Within the nuclear industry, many contaminated facilities that require decommissioning contain huge volumes of concrete. This concrete is generally disposed of as low-level waste at a high cost. Much of the concrete is lightly contaminated and could be reused as roadbed, fill material, or aggregate for new concrete, thus saving millions of dollars. However, because of the possibility of volumetric contamination and the lack of a method to evaluate the risks and costs of reusing concrete, reuse is rarely considered. To address this problem, Argonne National Laboratory-East (ANL-E) and the Idaho National Engineering and Environmental Laboratory teamed to write a ''concrete protocol'' to help evaluate the ramifications of reusing concrete within the U.S. Department of Energy (DOE). This document, titled the Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Site (1) is based on ANL-E's previously developed scrap metal recycle protocols; on the 10-step method outlined in DOE's draft handbook, Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material (2); and on DOE Order 4500.5, Radiation Protection of the Public and the Environment (3). The DOE concrete protocol was the basis for the ASTM Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning, which was written to make the information available to a wider audience outside DOE. The resulting ASTM Standard Guide is a more concise version that can be used by the nuclear industry worldwide to evaluate the risks and costs of reusing concrete from nuclear facility decommissioning. The bulk of the ASTM Standard Guide focuses on evaluating the dose and cost for each disposal option. The user calculates these from the detailed formulas and tabulated data provided, then compares the dose and cost for each disposal option to select the best option that meets regulatory requirements. With this information

  3. A framework for regulatory requirements and industry standards for new nuclear power plants

    International Nuclear Information System (INIS)

    Duran, Felicia A.; Camp, Allen L.; Apostolakis, George E.; Golay, Michael W.

    2000-01-01

    This paper summarizes the development of a framework for risk-based regulation and design for new nuclear power plants. Probabilistic risk assessment methods and a rationalist approach to defense in depth are used to develop a framework that can be applied to identify systematically the regulations and standards required to maintain the desired level of safety and reliability. By implementing such a framework, it is expected that the resulting body of requirements will provide a regulatory environment that will ensure protection of the public, will eliminate the burden of requirements that do not contribute significantly to safety, and thereby will improve the market competitiveness of new plants. (author)

  4. Standard model for the safety analysis report of nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    1980-02-01

    This norm establishes the Standard Model for the Safety Analysis Report of Nuclear Fuel Reprocessing Plants, comprehending the presentation format, the detailing level of the minimum information required by the CNEN for evaluation the requests of Construction License or Operation Authorization, in accordance with the legislation in force. This regulation applies to the following basic reports: Preliminary Safety Analysis Report - PSAR, integrating part of the requirement of Construction License; and Final Safety Analysis Report (FSAR) which is the integrating part of the requirement for Operation Authorization

  5. Nuclear power investment and generating costs from a utility point of view

    International Nuclear Information System (INIS)

    Roth, B.F.

    1975-01-01

    Nuclear power stations presently in operation in the Federal Republic of Germany have electricity generating costs between 3.5 Pf/kWh and 4.5 Pf/kWh. The higher electricity generating costs are due mainly to the increased expenditure required for the protection of plants against airplane crashes, earthquakes and sabotage, and to the higher costs of the entire fuel cycle. (orig./RW) [de

  6. Safety Evaluation Report related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410)

    International Nuclear Information System (INIS)

    1987-07-01

    This report supplements the Safety Evaluation Report (NUREG-1047, February 1985) for the application filed by Niagara Mohawk Power Corporation, as applicant and co-owner, for the license to operate Nine Mile Point Nuclear Station, Unit 2 (Docket No. 50-410). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. This report supports the issuance of the full-power license for Nine Mile Point Nuclear Station, Unit No. 2

  7. Significance of nuclear force merger-point with {open_quotes}G{close_quotes}

    Energy Technology Data Exchange (ETDEWEB)

    Ayub, S.M.

    1993-10-01

    As published earlier, interesting phenomena are expected at this 10{sup -27.4} cms, 10{sup 33.5} eV point (beyond our present Energy resources, except in SPACE). With the shrinkage of {open_quote}fm{close_quote}, queer Fission/Fusion possibilities were predicted at the merger-point of N. and N.Weak Forces, preceding this, due to Synchronisations thus the Fission of sub-critical masses came to happen, with the new Technologies for minimizing {open_quote}fm{close_quote}. The N.Force merger-point with {open_quote}G{close_quote} can predict the mass of the Top Quark from the proportionality of {open_quote}fm{close_quote}/M, at this point. This calculates to {approx} 180GeV, more than those of W{sup {+-}}, Z{sub o}, experimental confirmation may come from the operation of the 20TeV, S.P, or maybe from SPACE. {open_quote}G{close_quote} becomes {open_quote}Super-G{close_quote} in N.Stars/Black Holes, and this approach explains massive particles like even the {approx} 10{sup 19} GeV, the unification one in SU(3). Thus, this point has significance in Physics.

  8. Solution standards for quality control of nuclear-material analytical measurements

    International Nuclear Information System (INIS)

    Clark, J.P.

    1981-01-01

    Analytical chemistry measurement control depends upon reliable solution standards. At the Savannah River Plant Control Laboratory over a thousand analytical measurements are made daily for process control, product specification, accountability, and nuclear safety. Large quantities of solution standards are required for a measurement quality control program covering the many different analytical chemistry methods. Savannah River Plant produced uranium, plutonium, neptunium, and americium metals or oxides are dissolved to prepare stock solutions for working or Quality Control Standards (QCS). Because extensive analytical effort is required to characterize or confirm these solutions, they are prepared in large quantities. These stock solutions are diluted and blended with different chemicals and/or each other to synthesize QCS that match the matrices of different process streams. The target uncertainty of a standard's reference value is 10% of the limit of error of the methods used for routine measurements. Standard Reference Materials from NBS are used according to special procedures to calibrate the methods used in measuring the uranium and plutonium standards so traceability can be established. Special precautions are required to minimize the effects of temperature, radiolysis, and evaporation. Standard reference values are periodically corrected to eliminate systematic errors caused by evaporation or decay products. Measurement control is achieved by requiring analysts to analyze a blind QCS each shift a measurement system is used on plant samples. Computer evaluation determines whether or not a measurement is within the +- 3 sigma control limits. Monthly evaluations of the QCS measurements are made to determine current bias correction factors for accountability measurements and detect significant changes in the bias and precision statistics. The evaluations are also used to plan activities for improving the reliability of the analytical chemistry measurements

  9. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium metal

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2004-01-01

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium metal to determine compliance with specifications.

  10. Coupling of standard condensing nuclear power stations to horizontal aluminium tubes multieffect distillation plants

    International Nuclear Information System (INIS)

    Adar, J.

    1977-01-01

    No large nuclear back-pressure turbines are available to-day. Standard condensing nuclear turbines could operate continuously with a back-pressure of up to 7'' Hg, exhausting huge amounts of steam at 56degC-64degC with a loss of electricity production of only 6%-10%. The horizontal aluminium tube multieffect distillation process developed by 'Israel Desalination Engineering Ltd' is very suitable for the use of such low-grade heat. A special flash-chamber loop constitutes a positive barrier against any possible contamination being carried over by the steam exhausted from the turbine to the desalination plant. The operation is designed to be flexible so that the power plant can be operated either in conjunction with the desalination plant or as a single purpose plant. Flow sheets, heat and mass balances have been prepared for eight different combinations of plants. Only standard equipment is being used in the power plant. The desalination plant consists of 6 to 12 parallel double lines, each of them similar to a large prototype now being designed. Water production varies between 50 and 123 MGD and water cost between 90 and 137 c/1000 gallons. Costs are based on actual bids

  11. Improvements and standardization of communication means for control room personnel in nuclear power plants

    International Nuclear Information System (INIS)

    Preuss, W.; Eggerdinger, C.; Sieber, R.

    1982-01-01

    This report describes the findings of an investigation into selected communication means for control room personnel in nuclear power stations. The study can be seen as a contribution to the systematic analysis of major problem areas which were identified in the general study 'Human factors in the nuclear power plant'. The subjects under investigation were the 'Shift book', 'Simulation book', and 'Technical and organisational changes and their records'. It was intended to analyse both the communication, processes and the associated written documentation in order to determine areas for potential improvement and possibilities for standardization. Information was obtained by interviewing shift members and their supervisors, by general observation, and by compilation and evaluation of the extensive dokumentation. Assessment criteria were developed on a scientific basis and in the course of the investigation, in particular from ergonomic findings, as well as from standards and regulations and comparison between the plants. General practical suggestions were developed for the improvement of the communication forms and the formal design of the documents and their contents. The transfer of the recommendations to practical use in the plants presupposes the consideration of plant-specific frames of reference. The report includes a compilation and listing of suggestions for improvement in topical subdivisions. (orig.) [de

  12. AECB staff annual assessment of the Point Lepreau Nuclear Generating Station for the year 1995

    International Nuclear Information System (INIS)

    1996-06-01

    The Atomic Energy Control Board conducts a staff assessment of safety at Point Lepreau Generating Station for 1995. On-site Project Officers and Ottawa based specialists monitored the station throughout the year. Point Lepreau operated safely during 1995 which was an unusual year for the station. The station was shut down for a planned five month outage to allow NB Power to complete maintenance on the reactor's pressure tubes. NB Power failed to comply with the terms of the Operating Licence we issue on fourteen occasions in 1995. In addition, NB Power reported an unusually large number of events. None of the events themselves directly affected public safety, if this level of performance continues unchecked, it might result in increased risk from operation in the future. Human error was an important feature of these problems. NB Power had already introduced safety culture training for their staff, but they will need to undertake further work urgently to resolve the problems. Three of Point Lepreau's special safety systems failed to meet their availability targets during 1995. NB Power's safety analysis program progress slowed during 1995, due to the additional workload from the outage. The Point Lepreau's training, quality assurance and safeguards related activities continued to function satisfactorily. They have assigned additional resources to emergency preparedness planning, which should enable them to take a more pro-active approach in this area. 7 tabs., 5 figs

  13. Research on a methodology for standardization of engineering data in nuclear power plant design

    International Nuclear Information System (INIS)

    Kang, K. D.; Moon, C. K.; Baik, J. H.

    1999-01-01

    The standardization of data and the integration of system are emerging as important issues since each company should handle various kinds of information which is originated from the distributed resources due to rapid development of information technology. Especially for the case of nuclear power plant, the integration of data is very essential since all the data generated during plant lifetime of 40 to 60 years should be maintained and various entities participated in the phase of design, construction and operation of the plant. It is desirable to adopt SGML as a standard in a long-term base for the standardization of NPP engineering data, however there are some difficulties to apply it in current stage. So it is a viable approach to utilize XML as an interim base. In the case of drawings, it is desirable to apply STEP in a long-term base and to apply CAD system in a near term, which can support IGES. Also IGES can be applied in order to store and exchange the drawings. Furthermore, it can be considered to use VRML as a standard for the three dimensional drawings due to the rapid expansion of internet in recent years

  14. Study by electronic structure calculations of the radiation damage in the UO2 nuclear fuel: behaviour of the point defects and fission gases

    International Nuclear Information System (INIS)

    Vathonne, Emerson

    2014-01-01

    Uranium dioxide (UO 2 ) is worldwide the most widely used fuel in nuclear plants in the world and in particular in pressurized water reactors (PWR). In-pile the fission of uranium nuclei creates fission products and point defects in the fuel. The understanding of the evolution of these radiation damages requires a multi-scale modelling approach of the nuclear fuel, from the scale of the pellet to the atomic scale. We used an electronic structure calculation method based on the density functional theory (DFT) to model radiation damage in UO 2 at the atomic scale. A Hubbard-type Coulomb interaction term is added to the standard DFT formalism to take into account the strong correlations of the 5f electrons in UO 2 . This method is used to study point defects with various charge states and the incorporation and diffusion of krypton in uranium dioxide. This study allowed us to obtain essential data for higher scale models but also to interpret experimental results. In parallel of this study, three ways to improve the state of the art of electronic structure calculations of UO 2 have been explored: the consideration of the spin-orbit coupling neglected in current point defect calculations, the application of functionals allowing one to take into account the non-local interactions such as van der Waals interactions important for rare gases and the use of the Dynamical Mean Field Theory combined to the DFT method in order to take into account the dynamical effects in the 5f electron correlations. (author) [fr

  15. The evolution of IRRR nuclear standards from the single failure criterion and their impact on system design

    International Nuclear Information System (INIS)

    Clark, D.H.

    1978-01-01

    One of the first industry standards developed in the United States to meet regulatory agency criteria for the design and installation of nuclear power plant control and instrumentation systems was prepared by the Institute of Electrical and Electronics Engineers, Inc., abbreviated IEEE. This was IEEE Std. 279, first issued in 1968. It was subsequently revised and reissued as IEEE Std. 279-1971 ''IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations''. Not only has the implementation of this standard had a tremendous impact on nuclear power plant design in the United States, it has been the base document from which subsequent IEEE nuclear standards have been developed. Three major concepts which are addressed by IEEE 279, and which have had a major impact upon control and instrumentation systems in nuclear power plants are the following : 1) Single failure criterion. 2) Equipment qualification. 3) Channel independence. Each of these concepts has resulted in the development of subsequent IEEE Nuclear Standards. The impact of some of these on control and instrumentation systems are discussed. (author)

  16. Differences in safety margins between nuclear and conventional design standards with regards to seismic hazard definition and design criteria

    International Nuclear Information System (INIS)

    Elgohary, M.; Saudy, A.; Orbovic, N.; Dejan, D.

    2006-01-01

    With the surging interest in new build nuclear all over the world and a permanent interest in earthquake resistance of nuclear plants, there is a need to quantify the safety margins in nuclear buildings design in comparison to conventional buildings in order to increase the public confidence in the safety of nuclear power plants. Nuclear (CAN3-N289 series) and conventional (NBCC 2005) seismic standards have different approaches regarding the design of civil structures. The origin of the differences lays in the safety philosophy behind the seismic nuclear and conventional standards. Conventional seismic codes contain the minimal requirement destined primarily to safeguard against major structural failure and loss of life. It doesn't limit damage to a certain acceptable degree or maintain function. Nuclear seismic code requires that structures, systems and components important to safety, withstand the effects of earthquakes. The requirement states that for equipment important to safety, both integrity and functionality should be ascertained. The seismic hazard is generally defined on the basis of the annual probability of exceedence (return period). There is a major difference on the return period and the confidence level for design earthquakes between the conventional and the nuclear seismic standards. The seismic design criteria of conventional structures are based on the use of Force Modification Factors to take into account the energy dissipation by incursion in non-elastic domain and the reserve of strength. The use of such factors to lower intentionally the seismic input is consistent with the safety philosophy of the conventional seismic standard which is the 'non collapse' rather than the integrity and/or the operability of the structures or components. Nuclear seismic standard requires that the structure remain in the elastic domain; energy dissipation by incursion in non-elastic domain is not allowed for design basis earthquake conditions. This is

  17. Search for the QCD critical point in nuclear collisions at the CERN SPS

    CERN Document Server

    Anticic, T.; Barna, D.; Bartke, J.; Betev, L.; Bialkowska, H.; Blume, C.; Boimska, B.; Botje, M.; Bracinik, J.; Buncic, P.; Cerny, V.; Christakoglou, P.; Chung, P.; Chvala, O.; Cramer, J.G.; Dinkelaker, P.; Eckardt, V.; Fodor, Z.; Foka, P.; Friese, V.; Gazdzicki, M.; Genchev, V.; Grebieszkow, K.; Hohne, C.; Kadija, K.; Karev, A.; Kolesnikov, V.I.; Kowalski, M.; Kreps, M.; Laszlo, A.; Lacey, R.; van Leeuwen, M.; Lungwitz, B.; Makariev, M.; Malakhov, A.I.; Mateev, M.; Melkumov, G.L.; Mitrovski, M.; Mrowczynski, St.; Nicolic, V.; Palla, G.; Panagiotou, A.D.; Petridis, A.; Peryt, W.; Pikna, M.; Pluta, J.; Prindle, D.; Puhlhofer, F.; Renfordt, R.; Roland, C.; Roland, G.; Rybczynski, M.; Rybicki, A.; Sandoval, A.; Schmitz, N.; Schuster, T.; Seyboth, P.; Sikler, F.; Sitar, B.; Skrzypczak, E.; Slodkowski, M.; Stefanek, G.; Stock, R.; Strobele, H.; Susa, T.; Szuba, M.; Varga, D.; Vassiliou, M.; Veres, G.I.; Vesztergombi, G.; Vranic, D.; Wlodarczyk, Z.; Antoniou, N.G.; Diakonos, F.K.; Mavromanolakis, G.

    2010-01-01

    Pion production in nuclear collisions at the SPS is investigated with the aim to search, in a restricted domain of the phase diagram, for power-laws in the behaviour of correlations which are compatible with critical QCD. We have analysed interactions of nuclei of different size (p+p, C+C, Si+Si, Pb+Pb) at 158A GeV adopting, as appropriate observables, scaled factorial moments in a search for intermittent fluctuations in transverse dimensions. The analysis is performed for $\\pi^+\\pi^-$ pairs with invariant mass very close to the two-pion threshold. In this sector one may capture critical fluctuations of the sigma component in a hadronic medium, even if the $\\sigma$-meson has no well defined vacuum state. Our results indicate the presence of power-law fluctuations in the freeze-out state of the Si+Si system approaching in size the prediction of critical QCD.

  18. Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia

    Energy Technology Data Exchange (ETDEWEB)

    Park, Joo Hyun; Hwang, In Koo; Lee, Dong Young

    2005-04-15

    This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian standards however provide only conceptual definitions and requirements in the seismic related aspects. Therefore, it is conceived that any equipment or system qualified seismically in accordance with Korean standards should additionally provide technical evidence that it is satisfactory with Russian standards as well. In electromagnetic interference qualification, because Russian standard requires more testing items than the current Korean standard, the additional qualification tests are necessary to meet the Russian requirements. However, these additional test items are based on IEC(International Electrotechnical Commission), therefore it is not a problem to perform those tests in a Korean testing facility.

  19. Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia

    International Nuclear Information System (INIS)

    Park, Joo Hyun; Hwang, In Koo; Lee, Dong Young

    2005-04-01

    This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian standards however provide only conceptual definitions and requirements in the seismic related aspects. Therefore, it is conceived that any equipment or system qualified seismically in accordance with Korean standards should additionally provide technical evidence that it is satisfactory with Russian standards as well. In electromagnetic interference qualification, because Russian standard requires more testing items than the current Korean standard, the additional qualification tests are necessary to meet the Russian requirements. However, these additional test items are based on IEC(International Electrotechnical Commission), therefore it is not a problem to perform those tests in a Korean testing facility

  20. Severe Accident Mitigation by using Core Catcher applicable for Korea standard nuclear power plant

    International Nuclear Information System (INIS)

    Park, Hae Kyun; Kim, Sang Nyung

    2013-01-01

    Nuclear power plants have been designed and operated in order to prevent severe accident because of their risk that contains tremendous radioactive materials that are potentially hazardous. Moreover, the government requested the nuclear industry to implement a severe accident management strategy for existing reactors to mitigate the risk of potential severe accidents. However, Korea standard nuclear power plant(APR-1400 and OPR-1000) are much more vulnerable for severe accident management than that of developed countries. Due to the design feature of reactor cavity in Korea standard nuclear power plant, inequable and serious Molten Core-Concrete Interaction(MCCI) may cause considerable safety problem to the reactor containment liner. At worst, it brings the release of radioactive materials to the environment. This accident applies to the fourth level of defense in depth(IAEA 1996), 'severe accident'. This study proposes and designs the 'slope' to secure reactor containment liner integrity when the corium spreads out from the destroyed reactor vessel to the reactor cavity due to the core melting accident. For this, make the initial corium distribution evenly exploit the 'slope' on the basis of the study of Ex-vessel corium behavior to prevent inequable and serious MCCI, in order to mitigate severe accident. The viscosity has a dominant position in the calculation. According to the result, the spread out distance on the slope is 10.7146841m, considering the rough surface of the concrete(slope) and margin of reactor cavity end(under 11m). Easy to design, production and economic feasibility are the advantage of the designed slope in this study. However, the slope design may unsuitable when the sequences of the accidents did not satisfy the assumptions as mentioned. Despite of those disadvantages, the slope will show a great performance to mitigate the severe accident. As mentioned in assumption, the corium releasing time property was conservatively calculated

  1. Start-up support for New Brunswick Electric's Point Lepreau nuclear steam generators

    International Nuclear Information System (INIS)

    Schneider, W.; Leroux, A.

    1983-05-01

    The start-up of the 600 MW Point Lepreau reactor provided the opportunity for direct involvement in the important low and medium power start-up phase which was of particular interest because this was a first-of-a-kind reactor type incorporating a new steam generator design. Support included test assistance and test results interpretation for the thermal hydraulic performance of the steam generators and in particular, investigation of water level response to operating pressure, power and feed flow. This work resulted in both a greatly improved understanding of transient characteristics and in a number of beneficial refinements in the control methods

  2. Los Alamos National Laboratory new generation standard nuclear material storage container - the SAVY4000 design

    International Nuclear Information System (INIS)

    Stone, Timothy Amos

    2010-01-01

    Incidents involving release of nuclear materials stored in containers of convenience such as food pack cans, slip lid taped cans, paint cans, etc. has resulted in defense board concerns over the lack of prescriptive performance requirements for interim storage of nuclear materials. Los Alamos National Laboratory (LANL) has shared in these incidents and in response proactively moved into developing a performance based standard involving storage of nuclear material (RD003). This RD003 requirements document has sense been updated to reflect requirements as identified with recently issued DOE M 441.1-1 'Nuclear Material Packaging Manual'. The new packaging manual was issued at the encouragement of the Defense Nuclear Facilities Safety Board with a clear directive for protecting the worker from exposure due to loss of containment of stored materials. The Manual specifies a detailed and all inclusive approach to achieve a high level of protection; from package design and performance requirements, design life determinations of limited life components, authorized contents evaluations, and surveillance/maintenance to ensure in use package integrity over time. Materials in scope involve those stored outside an approved engineered-contamination barrier that would result in a worker exposure of in excess of 5 rem Committed Effective Does Equivalent (CEDE). Key aspects of meeting the challenge as developed around the SAVY-3000 vented storage container design will be discussed. Design performance and acceptance criteria against the manual, bounding conditions as established that the user must ensure are met to authorize contents in the package (based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide), interface as a safety class system within the facility under the LANL plutonium facility DSA, design life determinations for limited life components, and a sense of design specific surveillance program

  3. Differences in Approach between Nuclear and Conventional Seismic Standards with regard to Hazard Definition - CSNI Integrity And Ageing Working Group

    International Nuclear Information System (INIS)

    Djaoudi, Ali; Labbe, Pierre; Murphy, Andrew; Kitada, Yoshio

    2008-01-01

    The Committee on the safety of Nuclear Installations (CSNI) of the OECD-NEA co-ordinates the NEA activities related to maintaining and advancing the scientific and technological knowledge base of the safety of nuclear installations. The Integrity and Ageing of Components and Structures Working Group of the CSNI is responsible for work related to the development and use of methods, data and information to assess the behaviour of materials and structures. It has three sub-groups, dealing with the integrity of metal components and structures, ageing of concrete structures, and the seismic behaviour of structures. The CSNI, at its meeting in June 2003, agreed to initiate an activity aimed to identify any difference between nuclear and non-nuclear conventional standards and their potential significance with regard to seismic hazards and design methods. There was a perception, mainly in some of the European countries that nuclear seismic hazard and design standards may be lagging behind developments in similar standards for conventional facilities. Adequate answer to such perception, need the examination of the following aspects and their significance on the seismic assessment of structures and components: - The safety philosophy behind the seismic nuclear and conventional standards. - The differences in approach regarding the seismic hazard definition. - The difference in approach regarding the design and the methods of analysis. These topics are examined in this report. Appendices A to H of this report contain a brief description of the conventional and the nuclear approaches in the NEA member countries: Belgium, Canada, Czech Republic, Germany, Japan, South Korea, Spain,and USA. The following general conclusions can be drawn: - The approach adopted by the nuclear seismic standards is more conservative and more reliable (in particular for meeting the continued operation criteria) than the recommended by the currently applicable force based conventional seismic codes

  4. A basis for standardized seismic design (SSD) for nuclear power plants/critical facilities

    International Nuclear Information System (INIS)

    O'Hara, T.F.; Jacobson, J.P.; Bellini, F.X.

    1991-01-01

    US Nuclear Power Plants (NPP's) are designed, engineered and constructed to stringent standards. Their seismic adequacy is assured by compliance with regulatory standards and demonstrated by both probabilistic risk assessments (PRAs) and seismic margin studies. However, present seismic siting criteria requires improvement. Proposed changes to siting criteria discussed here will provide a predictable licensing process and a stable regulatory environment. Two recent state-of-the-art studies evaluate the seismic design for all eastern US (EUS) NPP'S: a Lawrence Livermore National Labs study (LLNL, 1989) funded by the NRC and similar research by the Electric Power Research Institute (EPRI, 1989) supported by the utilities. Both confirm that Appendix A 10CFR Part 100 has not provided consistent seismic design levels for all sites. Standardized Seismic Design (SSD) uses a probabilistic framework to accommodate alternative deterministic interpretations. It uses seismic hazard input from EPRI or LLNL to produce consistent bases for future seismic design. SSD combines deterministic and probabilistic insights to provide a comprehensive approach for determining a future site's acceptable seismic design basis

  5. Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.

  6. Consequences and problems which arose from the application of the Spanish laws about quality criteria in radiodiagnostic, nuclear medicine and radiotherapy from the point of view of radiophysicists

    International Nuclear Information System (INIS)

    Hernandez Vitoria, A.; Fernandez Gonzalez, B.; Marti Climent, J.; Perez Calatayud, J.

    2001-01-01

    New laws about quality criteria in radiodiagnostic, nuclear medicine and radiotherapy have been recently issued in Spain, concerning radiological protection to patients in each of these medical specialities. The present work deals briefly with the needs, consequences and problems arising in these three fields from their being put into effect, from the point of view of radiophysicists. In the diagnostic area the main difficulties arise from organization aspects to carry out the Quality Control programme in a fluid way. In nuclear medicine, the most difficult task is related to the dose estimation in each patient treated with radiopharmaceuticals. In radiotherapy, difficulties are connected with the specified tests to establish the initial reference state of the equipment as well as those for the quality control programme. In particular, in brachytherapy the main problem comes from the compulsory calibration in standard laboratories of the detectors used to measure the air kerma rate free in air for all types of employed sources. In this paper, these and other difficulties are discussed, as well as some actions taken in order to solve them. (author)

  7. Nuclear binding around the RP-process waiting points $^{68}$Se and $^{72}$Kr

    CERN Multimedia

    2002-01-01

    Encouraged by the success of mass determinations of nuclei close to the Z=N line performed at ISOLTRAP during the year 2000 and of the recent decay spectroscopy studies on neutron-deficient Kr isotopes (IS351 collaboration), we aim to measure masses and proton separation energies of the bottleneck nuclei defining the flow of the astrophysical rp-process beyond A$\\sim$70. In detail, the program includes mass measurements of the rp-process waiting point nuclei $^{68}$Se and $^{72}$Kr and determination of proton separation energies of the proton-unbound $^{69}$Br and $^{73}$Rb via $\\beta$-decays of $^{69}$Kr and $^{73}$Sr, respectively. The aim of the project is to complete the experimental database for astrophysical network calculations and for the liquid-drop type of mass models typically used in the modelling of the astrophysical rp process in the region. The first beamtime is scheduled for the August 2001 and the aim is to measure the absolute mass of the waiting-point nucleus $^{72}$Kr.

  8. Enforced standards of competence, full disclosure, and public control for the U.S. Nuclear Power Industry

    International Nuclear Information System (INIS)

    Wood, L.D.

    1976-01-01

    Some of the past faults of the nuclear power industry to properly inform the public concerning the risks and benefits of nuclear power or to seek the advice and consent of the public or their elected representatives concerning the matters of nuclear policy are pointed out. Some related problems concerning how to ensure that information which the public needs for evaluation of nuclear energy is disclosed publicly and how the will of this informed public should influence the construction of nuclear power plants are discussed. The facts of the case, In the Matter of Virginia Electric and Power Company (''North Anna Decision'') which was significant for its innovation in nuclear regulatory law, are set forth; and the holdings of law from the Atomic Safety and Licensing Board's (ASLB) of the U.S. Nuclear Regulatory Commission's (NRC) decision in the case are reviewed. A brief discussion of the benefits and risks which the nuclear power industry presents for Americans and their environment is included. Certain dangerous tendencies of the nuclear industry as a whole are examined. The specific issue of disclosure of information by the nuclear industry to the NRC is examined in order to make clear the imperative necessity for full disclosure. Problems related to disclosure to the public by the nuclear power industry and by NRC are examined. The article takes the stand, after a discussion of the public hearings which the NRC conducts concerning nuclear power plant construction and operating licenses, that these public hearings do not now adequately serve to inform and consult the public, and that NRC hearing requirements should be modified by Congress. On the premise that full disclosure is important, consideration is given to how both existing and recommended disclosure requirements can be enforced. Finally, governmental mechanisms by which the American people can gain significant control over the siting and construction of nuclear power plants are discussed

  9. Corrosion at Nuclear Power Plant from Mössbauer Spectroscopy Point of View

    Science.gov (United States)

    Slugeň, V.; Lipka, J.; Dekan, J.; Tóth, I.; Smieško, I.

    2010-07-01

    Steam generators of four VVER-440 units at nuclear power plants V-1 and V-2 in Jaslovske Bohunice (Slovakia) were gradually changed by new original "Bohunice" design in the 1994-1998 period. Corrosion processes before and after these design and material changes in Bohunice secondary circuit were studied using Mössbauer spectroscopy during the last 25 years. Innovations in the feed water pipeline design as well as material composition improvements were evaluated positively. Mössbauer spectroscopy studies of phase composition of corrosion products were performed on real specimens scrapped from water pipelines or in the form of filters deposits. The corrosion of new feed water pipelines system (from austenitic steel) in combination to innovated operation regimes goes dominantly to magnetite. The hematite presence is mostly on the internal surface of steam generator body and its concentration increases towards the top of the body. In the results interpretation it is necessary to consider also erosion as well as scope and type of maintenance activities. The long-term study of phase composition of corrosion products at VVER reactors is one of precondition for the safe operation over the projected NPP lifetime. Keywords: Enter Keywords here. Text should remain 10-pt.

  10. Shielding design for a Cs-137 rod-type standard point source for well chamber constancy checks.

    Science.gov (United States)

    Sabet, Mahsheed; Cryer, David; Waterhouse, David

    2016-12-01

    Well type chambers are used for radioactive source calibrations in brachytherapy, but do not provide radiation shielding. Routine constancy checks on a well chamber are required between periodic secondary standard laboratory calibrations to ensure consistent device performance, and ultimately to ensure accurate patient dose delivery. In this work, a method is described to provide suitable shielding for a Cs-137 rod-type point source to enable use for constancy checks. A novel plunger-type shielded housing was designed and constructed for the Cs-137 source that when combined with a suitably shielded well-chamber container minimised user exposure during constancy checks. The designed shielding proved effective, and a constancy test routine was established and used for the past 16 months. The well chamber showed consistent performance (0.12 ± 0.18 % from the baseline) and no increased exposure was reported on users' radiation badges.

  11. 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

  12. Development of alarm cause tracking system for Korea standard nuclear power plant

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Kim, Jung Taek; Park, Jae Chang; Lee, Hyun Chul; Park, Joong Pal

    2004-05-01

    The proposed system, the ACTS(Alarm Cause Tracking System), in the 1st and 2nd development period(2001. 7 ∼ 2003. 6), tracks and displays the causes of alarms on-line from computerized logic diagrams. And the system highlights the specific procedures related the causes in the procedure of the alarm. In this period(2003. 7 ∼ 2004. 4), we developed the ACTS for Korea standard nuclear power plant. Also, we computerized control logic diagrams and alarm procedures for the ACTS. A long-term target is to apply the ACTS at the real power plant, and a short-term target is to connect the ACTS with the ITF(Intergrated Test Facility) in KAERI site to develop other applications

  13. Toward Global Standards on Peaceful uses of Space Nuclear Reactor Power Systems

    Science.gov (United States)

    El-Genk, M. S.

    Space reactor power systems are enabling to future space exploration and outposts on the Moon, Mars and other celestial bodies. They could provide for electrical propulsion, thermal propulsion and bimodal operation of thermal propulsion and electrical power generation. The much higher specific impulse of nuclear thermal and electric propulsion, compared to chemical rockets, could significantly shorten the travel time to Mars and farthest destinations, reducing the exposure of equipment and astronauts to the harmful space radiation. This article addresses safety issues relevant to the design, operation and end-of-life storage of these systems in an attempt to stimulate a discussion of the need to establish specific and globally agreed upon safety standards and guidelines for future peaceful uses.

  14. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2011-01-01

    1.1 These test methods cover procedures for subsampling and for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride UF6. Most of these test methods are in routine use to determine conformance to UF6 specifications in the Enrichment and Conversion Facilities. 1.2 The analytical procedures in this document appear in the following order: Note 1—Subcommittee C26.05 will confer with C26.02 concerning the renumbered section in Test Methods C761 to determine how concerns with renumbering these sections, as analytical methods are replaced with stand-alone analytical methods, are best addressed in subsequent publications. Sections Subsampling of Uranium Hexafluoride 7 - 10 Gravimetric Determination of Uranium 11 - 19 Titrimetric Determination of Uranium 20 Preparation of High-Purity U3O 8 21 Isotopic Analysis 22 Isotopic Analysis by Double-Standard Mass-Spectrometer Method 23 - 29 Determination of Hydrocarbons, Chlorocarbons, and Partially Substitut...

  15. Reliability study: digital engineered safety feature actuation system of Korean Standard Nuclear Power Plant

    International Nuclear Information System (INIS)

    Sudarno; Kang, H. G.; Jang, S. C.; Eom, H. S.; Ha, J. J.

    2003-04-01

    The usage of digital Instrumentation and Control (I and C) in a nuclear power plant becomes more extensive, including safety related systems. The PSA application of these new designs are very important in order to evaluate their reliability. In particular, Korean Standard Nuclear Power Plants (KSNPPs), typically Ulchin 5 and 6 (UCN 5 and 6) reactor units, adopted the digital safety-critical systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS). In this research, we developed fault tree models for assessing the unavailability of the DESFAS functions. We also performed an analysis of the quantification results. The unavailability results of different DESFAS functions showed that their values are comprised from 5.461E-5 to 3.14E-4. The system unavailability of DESFAS AFAS-1 is estimated as 5.461E-5, which is about 27% less than that of analog system if we consider the difference of human failure probability estimation between both analyses. The results of this study could be utilized in risk-effect analysis of KSNPP. We expect that the safety analysis result will contribute to design feedback

  16. International Image Concordance Study to Compare a Point-of-Care Tampon Colposcope With a Standard-of-Care Colposcope.

    Science.gov (United States)

    Mueller, Jenna L; Asma, Elizabeth; Lam, Christopher T; Krieger, Marlee S; Gallagher, Jennifer E; Erkanli, Alaattin; Hariprasad, Roopa; Malliga, J S; Muasher, Lisa C; Mchome, Bariki; Oneko, Olola; Taylor, Peyton; Venegas, Gino; Wanyoro, Anthony; Mehrotra, Ravi; Schmitt, John W; Ramanujam, Nimmi

    2017-04-01

    Barriers to cervical cancer screening in low-resource settings include lack of accessible, high-quality services, high cost, and the need for multiple visits. To address these challenges, we developed a low-cost, intravaginal, optical cervical imaging device, the point-of-care tampon (POCkeT) colposcope and evaluated whether its performance is comparable with a standard-of-care colposcope. There were 2 protocols, which included 44 and 18 patients. For the first protocol, white-light cervical images were collected in vivo, blinded by device, and sent electronically to 8 physicians from high-, middle-, and low-income countries. For the second protocol, green-light images were also collected and sent electronically to the highest performing physician from the first protocol who has experience in both a high- and low-income country. For each image, physicians completed a survey assessing cervix characteristics and severity of precancerous lesions. Corresponding pathology was obtained for all image pairs. For the first protocol, average percent agreement between devices was 70% across all physicians. The POCkeT and standard-of-care colposcope images had 37% and 51% agreement with pathology for high-grade squamous intraepithelial lesions (HSILs), respectively. Investigation of HSIL POCkeT images revealed decreased visibility of vascularization and lack of contrast in lesion margins. After changes were made for the second protocol, the 2 devices achieved similar agreement to pathology for HSIL lesions (55%). Based on the exploratory study, physician interpretation of cervix images acquired using a portable, low-cost POCkeT colposcope was comparable to a standard-of-care colposcope.

  17. The Next Generation Nuclear Plant - Insights Gained from the INEEL Point Design Studies

    Energy Technology Data Exchange (ETDEWEB)

    Philip E. MacDonald; A. M. Baxter; P. D. Bayless; J. M. Bolin; H. D. Gougar; R. L. Moore; A. M. Ougouag; M. B. Richards; R. L. Sant; J. W. Sterbentz; W. K. Terry

    2004-08-01

    This paper provides the results of an assessment of two possible versions of the Next Generation Nuclear Plant (NGNP), a prismatic fuel type helium gas-cooled reactor and a pebble-bed fuel helium gas reactor. Insights gained regarding the strengths and weaknesses of the two designs are also discussed. Both designs will meet the three basic requirements that have been set for the NGNP: a coolant outlet temperature of 1000 C, passive safety, and a total power output consistent with that expected for commercial high-temperature gas-cooled reactors. Two major modifications of the current Gas Turbine- Modular Helium Reactor (GT-MHR) design were needed to obtain a prismatic block design with a 1000 C outlet temperature: reducing the bypass flow and better controlling the inlet coolant flow distribution to the core. The total power that could be obtained for different core heights without exceeding a peak transient fuel temperature of 1600 °C during a high or low-pressure conduction cooldown event was calculated. With a coolant inlet temperature of 490 °C and 10% nominal core bypass flow, it is estimated that the peak power for a 10-block high core is 686 MWt, for a 12-block high core is 786 MWt, and for a 14-block core is about 889 MWt. The core neutronics calculations showed that the NGNP will exhibit strongly negative Doppler and isothermal temperature coefficients of reactivity over the burnup cycle. In the event of rapid loss of the helium gas, there is negligible core reactivity change. However, water or steam ingress into the core coolant channels can produce a relatively large reactivity effect. Two versions of an annular pebble-bed NGNP have also been developed, a 300 and a 600 MWt module. From this work we learned how to design passively safe pebble bed reactors that produce more than 600 MWt. We also found a way to improve both the fuel utilization and safety by modifying the pebble design (by adjusting the fuel zone radius in the pebble to optimize the fuel

  18. Development of departmental standard for traceability of measured activity for I-131 therapy capsules used in nuclear medicine

    OpenAIRE

    Ravichandran, Ramamoorthy; Binukumar, JP

    2011-01-01

    International Basic Safety Standards (International Atomic Energy Agency, IAEA) provide guidance levels for diagnostic procedures in nuclear medicine indicating the maximum usual activity for various diagnostic tests in terms of activities of injected radioactive formulations. An accuracy of ± 10% in the activities of administered radio-pharmaceuticals is being recommended, for expected outcome in diagnostic and therapeutic nuclear medicine procedures. It is recommended that the l...

  19. AECB staff annual assessment of the Point Lepreau Nuclear Generating Station for the year 1994

    International Nuclear Information System (INIS)

    1995-06-01

    This report is the Atomic Energy Control Board assessment of safety at Point Lepreau Generating Station for 1994. AECB on-site Project Officers, and Ottawa based specialists monitored the station throughout the year. The station operated safely during 1994. Performance of the special safety systems was very good, and NB Power made important progress improving the safety management of these systems. NB Power staff failed to comply with the conditions of our Operating Licence seven times during 1994. This is an improvement from last year, but the number of compliance problems is still too high. NB Power introduced safety culture training for its staff last year. AECB is optimistic that this will help to improve compliance. The station fully met the radiation safety requirements during the year. Releases of radioactive material to the environment are well below the limits set. Radiation exposure to workers are being well controlled, and AECB believe that NB Power is maintaining these exposures 'As Low As Reasonably Achievable' for this reactor type

  20. Problems and solutions in application of IEEE standards at Savannah River Site, Department of Energy (DOE) nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Y.S.; Bowers, T.L.; Chopra, B.J.; Thompson, T.T.; Zimmerman, E.W.

    1993-01-01

    The Department of Energy (DOE) Nuclear Material Production Facilities at the Savannah River Site (SRS) were designed, constructed, and placed into operation in the early 1950's, based on existing industry codes/standards, design criteria, analytical procedures. Since that time, DOE has developed Orders and Polices for the planning, design and construction of DOE Nuclear Reactor Facilities which invoke or reference commercial nuclear reactor codes and standards. The application of IEEE reactor design requirements such as Equipment Qualification, Seismic Qualification, Single Failure Criteria, and Separation Requirement, to non-reactor facilities has been a problem since the IEEE reactor criteria do not directly confirm to the needs of non-reactor facilities. SRS Systems Engineering is developing a methodology for the application of IEEE Standards to non-reactor facilities at SRS

  1. Address Points, Address points were attributed according to NENA standards and field verfied between the dates of June 2008 thru August 2008. The address points were then matched to the Verizon Telco database with a 99% hit rate in October of 2008., Published in 2006, 1:1200 (1in=100ft) scale, Eastern Shore Regional GIS Cooperative.

    Data.gov (United States)

    NSGIC Regional | GIS Inventory — Address Points dataset current as of 2006. Address points were attributed according to NENA standards and field verfied between the dates of June 2008 thru August...

  2. Procurement and characterization of LEU special nuclear materials standards for PERLA

    International Nuclear Information System (INIS)

    Guardini, S.; Mousty, F.; Nonneman, S.; Schillebeeckx, P.; Gerard, J.; Vanaken, K.; Aigner, H.; Bagliano, G.; Deron, S.; Vandevelde, L.

    1995-01-01

    A major activity of PERLA, the PERformance LAboratory of the Joint Research Center of the European Union is to select, procure and characterize Uranium and Plutonium working reference materials representative of the nuclear materials, subject to safeguards verification measurements by means of increasingly precise NDA techniques. These reference materials ensure the traceability of the measurements back to international standard units. They are used to develop, improve and calibrate the NDA instruments and to train the inspectors to operate these instruments correctly. The paper describes the approach adopted for the procurement, production and characterization plans of LEU standards in the form of UO 2 pellets, U 3 O 8 powders, pins and a mock up PWR fuel element. Homogeneity tests, weighing protocols, humidity checks and impurity analysis were performed on the feed materials (UO 2 powders) and on the final product materials (U 3 O 8 powders and UO 2 pellets). The sampling and the analytical scheme followed for the characterization and the analytical results obtained are presented and statistically evaluated. The characterization of these reference materials carried out by four experienced analytical laboratories allows a certification of the uranium content and isotopic abundance with small confidence intervals in a minimal time and minimal analytical effort

  3. Standard Practice for Determining NeutronExposures for Nuclear Reactor Vessel Support Structures

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active core. This practice includes guidelines for: 1.1.1 Selecting appropriate dosimetric sensor sets and their proper installation in reactor cavities. 1.1.2 Making appropriate neutronics calculations to predict neutron radiation exposures. 1.2 This practice is applicable to all pressurized water reactors whose vessel supports will experience a lifetime neutron fluence (E > 1 MeV) that exceeds 1 × 1017 neutrons/cm2 or 3.0 × 10−4 dpa. (See Terminology E 170.) 1.3 Exposure of vessel support structures by gamma radiation is not included in the scope of this practice, but see the brief discussion of this issue in 3.2. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and h...

  4. Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2002-01-01

    1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists. 1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1) from ...

  5. Application of the dynamic control rod reactivity measurement method to Korea standard nuclear power plants

    International Nuclear Information System (INIS)

    Lee, E. K.; Shin, H. C.; Bae, S. M.; Lee, Y. G.

    2004-01-01

    To measure and validate the worth of control bank or shutdown bank, the dynamic control rod reactivity measurement (DCRM) technique has been developed and applied to six cases of Low Power Physics Tests of PWRs including Korea Standard Nuclear Power plant (KSNP) based on the CE System 80 NSSS. Through the DORT results for each two ex-ore detector response and the three dimensional core transient simulations for rod movements, the key parameters of DCRM method are determined to implement into the Direct Digital Reactivity Computer System (DDRCS). A total of 9 bank worths of two KSNP plants were measured to compare with the worths of the conventional rod worth measurement method. The results show that the average error of DCRM method is nearly the same as the conventional Rod Swap and Boron Dilution Method but lower standard deviation. It takes about twenty minutes from the beginning of rod movement to final estimation of the integral static worth of a control bank. (authors)

  6. Calculation of electron and isotopes dose point kernels with FLUKA Monte Carlo code for dosimetry in nuclear medicine therapy.

    Science.gov (United States)

    Botta, F; Mairani, A; Battistoni, G; Cremonesi, M; Di Dia, A; Fassò, A; Ferrari, A; Ferrari, M; Paganelli, G; Pedroli, G; Valente, M

    2011-07-01

    The calculation of patient-specific dose distribution can be achieved by Monte Carlo simulations or by analytical methods. In this study, FLUKA Monte Carlo code has been considered for use in nuclear medicine dosimetry. Up to now, FLUKA has mainly been dedicated to other fields, namely high energy physics, radiation protection, and hadrontherapy. When first employing a Monte Carlo code for nuclear medicine dosimetry, its results concerning electron transport at energies typical of nuclear medicine applications need to be verified. This is commonly achieved by means of calculation of a representative parameter and comparison with reference data. Dose point kernel (DPK), quantifying the energy deposition all around a point isotropic source, is often the one. FLUKA DPKS have been calculated in both water and compact bone for monoenergetic electrons (10-3 MeV) and for beta emitting isotopes commonly used for therapy (89Sr, 90Y, 131I 153Sm, 177Lu, 186Re, and 188Re). Point isotropic sources have been simulated at the center of a water (bone) sphere, and deposed energy has been tallied in concentric shells. FLUKA outcomes have been compared to PENELOPE v.2008 results, calculated in this study as well. Moreover, in case of monoenergetic electrons in water, comparison with the data from the literature (ETRAN, GEANT4, MCNPX) has been done. Maximum percentage differences within 0.8.RCSDA and 0.9.RCSDA for monoenergetic electrons (RCSDA being the continuous slowing down approximation range) and within 0.8.X90 and 0.9.X90 for isotopes (X90 being the radius of the sphere in which 90% of the emitted energy is absorbed) have been computed, together with the average percentage difference within 0.9.RCSDA and 0.9.X90 for electrons and isotopes, respectively. Concerning monoenergetic electrons, within 0.8.RCSDA (where 90%-97% of the particle energy is deposed), FLUKA and PENELOPE agree mostly within 7%, except for 10 and 20 keV electrons (12% in water, 8.3% in bone). The

  7. Comparative study of Malaysian and Philippine regulatory infrastructures on radiation and nuclear safety with international standards

    International Nuclear Information System (INIS)

    Cayabo, Lynette B.

    2013-06-01

    This study presents the results of the critical reviews, analysis, and comparison of the regulatory infrastructures for radiation and nuclear safety of Malaysis and the Philippines usi ng the IAEA safety requirements, GSR Part 1, G overnment, Legal and Regulatory Framework for Safety'' as the main basis and in part, the GSR Part 3, R adiation Protection and Safety of Radiation Sources: International Basic Safety Standards . The scope of the comparison includes the elements of the relevant legislations, the regulatory system and processes including the core functions of the regulatory body (authorization, review and assessment, inspection and enforcement, development of regulations and guides); and the staffing and training of regulatory body. The respective availabe data of the Malaysian and Philippine regulatory infrastructures and current practices were gathered and analyzed. Recommendations to fill the gaps and strengthen the existing regulatory infrastructure of each country was given using as bases relevant IAEA safety guides. Based on the analysis made, the main findings are: the legislations of both countries do not contain al the elements of teh national policy and strategy for safety as well as those of teh framework for safety in GR Part I. Among the provision that need to be included in the legislations are: emergency planning and response; decommissioning of facilities safe management of radioactive wastes and spent fuel; competence for safety; and technical sevices. Provisions on coordination of different authorities with safety responsibilities within the regulatory framework for safety as well as liaison with advisory bodies and support organizations need to be enhanced. The Philippines needs to establish an independent regulatory body, ie. separate from organizations charged with promotion of nuclear technologies and responsible for facilitiesand activities. Graded approach on the system of notification and authorization by registration and

  8. A real-time computer simulation of nuclear simulator software using standard PC hardware and linux environments

    International Nuclear Information System (INIS)

    Cha, K. H.; Kweon, K. C.

    2001-01-01

    A feasibility study, which standard PC hardware and Real-Time Linux are applied to real-time computer simulation of software for a nuclear simulator, is presented in this paper. The feasibility prototype was established with the existing software in the Compact Nuclear Simulator (CNS). Throughout the real-time implementation in the feasibility prototype, we has identified that the approach can enable the computer-based predictive simulation to be approached, due to both the remarkable improvement in real-time performance and the less efforts for real-time implementation under standard PC hardware and Real-Time Linux envrionments

  9. Conceptual design study: Standard Floating Nuclear Power Plant on Inshore Site and Modified Floating Nuclear Power Plant on Upriver Site

    International Nuclear Information System (INIS)

    1982-02-01

    Both plants/designs are technically feasible. Both compare favorably with conventional nuclear plants with respect to licensability, quality of construction, reliability of operation, and safety. Both offer considerable reductions in construction schedule over conventional nuclear plants. It has been estimated that if project durations were reduced by three years the cost of a 1100 MWe nuclear unit could be decreased by $260 million to $450 million. The allowance for funds during construction (AFDC) was estimated to be $929 million for a 1260 MWe nuclear plant with a commercial operation date in 1992. Reducing the schedule from 12 to 9 years, a reduction of 25%, implies a savings in AFDC alone of approximately $230 million

  10. Low melting point agarose beads as a standard method for plantlet regeneration from protoplasts within the Cichorium genus.

    Science.gov (United States)

    Deryckere, Dieter; Eeckhaut, Tom; Van Huylenbroeck, Johan; Van Bockstaele, Erik

    2012-12-01

    A standard method has been developed with which we are able to fully regenerate protoplasts of different Cichorium species. For the first time, endive protoplasts have been regenerated into plantlets. Protoplast regeneration is essential for somatic hybridizations. In this study, a standard method for plantlet regeneration from Cichorium protoplasts was developed. We evaluated the effect of the low melting point agarose (LMPA) bead technique on the regeneration capacity of protoplasts of seven C. intybus and four C. endivia genotypes. The LMPA bead technique was more efficient than culture in liquid or solid medium and allowed us to obtain plating efficiencies up to 4.9 % in C. intybus genotypes and efficiencies of up to 0.7 % in C. endivia genotypes. Moreover, the LMPA bead technique offers great advantages over liquid and solid culture systems: the media can be readily refreshed, protoplasts can be monitored separately, and microcalli can easily be removed from the beads. This increased efficiency was observed for all of the 11 Cichorium genotypes tested. Shoot formation was induced more efficiently when using 0.5 mg l(-1) indole-3-acetic acid-enriched medium (up to 87.5 % of the protoplast-derived calli started shoot development) compared to 1-naphthaleneacetic acid-enriched medium. The LMPA bead technique optimized in this study enabled for the first time the full plantlet regeneration from protoplasts of C. endivia genotypes and increased the protoplast regenerating ability in other Cichorium species. This fine-tuned LMPA bead technique can therefore be applied for protoplast regeneration after protoplast fusions of the genus Cichorium.

  11. The adequacy of current occupational standards for protecting the health of nuclear workers.

    Science.gov (United States)

    Lambert, B E

    1991-01-01

    It will be clear from the aforegoing that occupational standards have varied over the past 30-40 years since the beginnings of the nuclear industry. Our perception of risk rates for cancer mortality and genetic effects has changed, such that the rates have been constantly revised upwards. Logically, dose limits should have been reduced in proportion, but this assumes a constant approach to the "tolerability" or "acceptability" of risk and this has not been demonstrated. Dose limits are not seen by management in the nuclear industry as the only plank in the structure of radiation protection; emphasis is also being given to the "optimization" ethic. In these circumstances a good test of the efficacy of the system of radiation control in limiting health effects is needed. As can be seen, no such study is available and, given the doses received and the numbers of workers involved, it is unlikely that any epidemiologic study, apart from studies on miners, will have sufficient statistical power to be totally unequivocal. However, some studies have shown cancer mortality associations with radiation exposure that are significant. Probably the best way to mitigate the inherent drawbacks in these studies is to pool data-sets, and this is being done. Other improvements will include estimates of cancer incidence in countries with cancer registries (e.g., U.K., Canada, and Sweden) and to perhaps go beyond epidemiologic data to consider sensitive biologic markers as indices of exposure. Overall the conclusion must be that the radiation industry cannot be complacent and for some tasks in the processes involved (e.g., uranium mining) there is strong evidence of a history of unacceptable health effects occurring.

  12. Transmutation of All German Transuranium under Nuclear Phase Out Conditions - Is This Feasible from Neutronic Point of View?

    Directory of Open Access Journals (Sweden)

    Bruno Merk

    Full Text Available The German government has decided for the nuclear phase out, but a decision on a strategy for the management of the highly radioactive waste is not defined yet. Partitioning and Transmutation (P&T could be considered as a technological option for the management of highly radioactive waste, therefore a wide study has been conducted. In the study group objectives for P&T and the boundary conditions of the phase out have been discussed. The fulfillment of the given objectives is analyzed from neutronics point of view using simulations of a molten salt reactor with fast neutron spectrum. It is shown that the efficient transmutation of all existing transuranium isotopes would be possible from neutronic point of view in a time frame of about 60 years. For this task three reactors of a mostly new technology would have to be developed and a twofold life cycle consisting of a transmuter operation and a deep burn phase would be required. A basic insight for the optimization of the time duration of the deep burn phase is given. Further on, a detailed balance of different isotopic inventories is given to allow a deeper understanding of the processes during transmutation in the molten salt fast reactor. The effect of modeling and simulation is investigated based on three different modeling strategies and two different code versions.

  13. DEVELOPMENT OF THE MODEL OF GALACTIC INTERSTELLAR EMISSION FOR STANDARD POINT-SOURCE ANALYSIS OF FERMI LARGE AREA TELESCOPE DATA

    Energy Technology Data Exchange (ETDEWEB)

    Acero, F.; Ballet, J. [Laboratoire AIM, CEA-IRFU/CNRS/Université Paris Diderot, Service d’Astrophysique, CEA Saclay, F-91191 Gif sur Yvette (France); Ackermann, M.; Buehler, R. [Deutsches Elektronen Synchrotron DESY, D-15738 Zeuthen (Germany); Ajello, M. [Department of Physics and Astronomy, Clemson University, Kinard Lab of Physics, Clemson, SC 29634-0978 (United States); Albert, A.; Baldini, L.; Bloom, E. D.; Bottacini, E.; Caliandro, G. A.; Cameron, R. A. [W. W. Hansen Experimental Physics Laboratory, Kavli Institute for Particle Astrophysics and Cosmology, Department of Physics and SLAC National Accelerator Laboratory, Stanford University, Stanford, CA 94305 (United States); Barbiellini, G. [Istituto Nazionale di Fisica Nucleare, Sezione di Trieste, I-34127 Trieste (Italy); Bastieri, D. [Istituto Nazionale di Fisica Nucleare, Sezione di Padova, I-35131 Padova (Italy); Bellazzini, R. [Istituto Nazionale di Fisica Nucleare, Sezione di Pisa, I-56127 Pisa (Italy); Bissaldi, E. [Istituto Nazionale di Fisica Nucleare, Sezione di Bari, I-70126 Bari (Italy); Bonino, R. [Istituto Nazionale di Fisica Nucleare, Sezione di Torino, I-10125 Torino (Italy); Brandt, T. J.; Buson, S. [NASA Goddard Space Flight Center, Greenbelt, MD 20771 (United States); Bregeon, J. [Laboratoire Univers et Particules de Montpellier, Université Montpellier, CNRS/IN2P3, Montpellier (France); Bruel, P., E-mail: isabelle.grenier@cea.fr, E-mail: casandjian@cea.fr [Laboratoire Leprince-Ringuet, École polytechnique, CNRS/IN2P3, Palaiseau (France); and others

    2016-04-01

    Most of the celestial γ rays detected by the Large Area Telescope (LAT) on board the Fermi Gamma-ray Space Telescope originate from the interstellar medium when energetic cosmic rays interact with interstellar nucleons and photons. Conventional point-source and extended-source studies rely on the modeling of this diffuse emission for accurate characterization. Here, we describe the development of the Galactic Interstellar Emission Model (GIEM), which is the standard adopted by the LAT Collaboration and is publicly available. This model is based on a linear combination of maps for interstellar gas column density in Galactocentric annuli and for the inverse-Compton emission produced in the Galaxy. In the GIEM, we also include large-scale structures like Loop I and the Fermi bubbles. The measured gas emissivity spectra confirm that the cosmic-ray proton density decreases with Galactocentric distance beyond 5 kpc from the Galactic Center. The measurements also suggest a softening of the proton spectrum with Galactocentric distance. We observe that the Fermi bubbles have boundaries with a shape similar to a catenary at latitudes below 20° and we observe an enhanced emission toward their base extending in the north and south Galactic directions and located within ∼4° of the Galactic Center.

  14. Development of the Model of Galactic Interstellar Emission for Standard Point-Source Analysis of Fermi Large Area Telescope Data

    Science.gov (United States)

    Acero, F.; Ackermann, M.; Ajello, M.; Albert, A.; Baldini, L.; Ballet, J.; Barbiellini, G.; Bastieri, D.; Bellazzini, R.; Brandt, T. J.; hide

    2016-01-01

    Most of the celestial gamma rays detected by the Large Area Telescope (LAT) on board the Fermi Gamma-ray Space Telescope originate from the interstellar medium when energetic cosmic rays interact with interstellar nucleons and photons. Conventional point-source and extended-source studies rely on the modeling of this diffuse emission for accurate characterization. Here, we describe the development of the Galactic Interstellar Emission Model (GIEM),which is the standard adopted by the LAT Collaboration and is publicly available. This model is based on a linear combination of maps for interstellar gas column density in Galactocentric annuli and for the inverse-Compton emission produced in the Galaxy. In the GIEM, we also include large-scale structures like Loop I and the Fermi bubbles. The measured gas emissivity spectra confirm that the cosmic-ray proton density decreases with Galactocentric distance beyond 5 kpc from the Galactic Center. The measurements also suggest a softening of the proton spectrum with Galactocentric distance. We observe that the Fermi bubbles have boundaries with a shape similar to a catenary at latitudes below 20deg and we observe an enhanced emission toward their base extending in the north and south Galactic directions and located within approximately 4deg of the Galactic Center.

  15. Review of the Commission program for standardization of nuclear power plants and recommendations to improve standardization concepts

    International Nuclear Information System (INIS)

    1978-02-01

    This is a report of a staff study describing the need and utility of specific changes to the Commission's standardization program. The various matters considered in the study include: (1) A discussion of industry use to date of the standardization program. (2) A discussion of the experience to date with each of the standardization concepts. (3) A review of public comments on the standardization program and the staff response to each principal comment. (4) A review of the need for standardization considering the likely number of license applications to be submitted in the coming years. (5) A discussion of the reference system concept, including review of applicable experience and recommended changes to the concept. (6) A discussion of the duplicate plant concept, including review of applicable experience and recommended changes to the concept. (7) A discussion of the manufacturing license concept, including review of applicable experience and recommended changes to the concept. (8) A discussion of the replicate plant concept, including review of applicable experience and recommended changes to the concept. (9) A discussion of the effective periods for approved designs under all four standardization concepts. (10) A description of continuing staff activities related to the standardization program

  16. Ensuring safe and quality medication use in nuclear medicine: a collaborative team achieves compliance with medication management standards.

    Science.gov (United States)

    Beach, Trent A; Griffith, Karen; Dam, Hung Q; Manzone, Timothy A

    2012-03-01

    As hospital nuclear medicine departments were established in the 1960s and 1970s, each department developed detailed policies and procedures to meet the specialized and specific handling requirements of radiopharmaceuticals. In many health systems, radiopharmaceuticals are still unique as the only drugs not under the control of the health system pharmacy; however, the clear trend--and now an accreditation requirement--is to merge radiopharmaceutical management with the overall health system medication management system. Accomplishing this can be a challenge for both nuclear medicine and pharmacy because each lacks knowledge of the specifics and needs of the other field. In this paper we will first describe medication management standards, what they cover, and how they are enforced. We will describe how we created a nuclear medicine and pharmacy team to achieve compliance, and we will present the results of their work. We will examine several specific issues raised by incorporating radiopharmaceuticals in the medication management process and describe how our team addressed those issues. Finally, we will look at how the medication management process helps ensure ongoing quality and safety to patients through multiple periodic reviews. The reader will gain an understanding of medication management standards and how they apply to nuclear medicine, learn how a nuclear medicine and pharmacy team can effectively merge nuclear medicine and pharmacy processes, and gain the ability to achieve compliance at the reader's own institution.

  17. Nordic Nuclear Safety Research 1994 - 2008: From standardized 4-year classics to customized R and B

    International Nuclear Information System (INIS)

    Bennerstedt, T.N.O.

    2011-10-01

    This is a presentation of NKS (Nordic Nuclear Safety Research), its work and achievements in the years 1994 - 2008, during which the author served as Nordic secretary and (later) as coordinator. NKS and the Nordic perspective are briefly introduced together with the NKS support structure, organization and administration: Owners, Board, Nordic secretary, Bureau and Secretariat. The author then embarks on a journey through the modern history of NKS work. The last two of the six fixed 4-year programs are described as regards planning, contents, project work, administration, dissemination of results, evaluations and conclusions. The trip continues to the land of R and B and the present (2011) structure of two general frameworks, namely, NKS-R: reactor safety, and NKS-B: emergency preparedness; each consisting of a set of flexible activities; hence, R and B. The reasoning behind this makeover is touched upon together with the new organization and simpler administration that developed. Major activities and the produced results are introduced and the evaluations summarized. The author's own conclusions and recommendations are followed by a short and subjective list of references. In a number of appendices some important background material has been compiled: bullet point versions of minutes of Owners Group and Board meetings; economic contributions and budgets; the NKS policy document; an overview of all NKS programs and evaluations; lists of R and B activities and funding; the author's personal remarks; a list of some NKS documents (other than technical reports and minutes); and a list of acronyms used in this report. (Author)

  18. Nuclear reactors. Use of the protection system for non-safety purposes (International Electrotechnical Commission Standard Publication 639:1979)

    International Nuclear Information System (INIS)

    Stefanik, J.

    1996-01-01

    This standard applies to the protection system of a nuclear reactor and, more especially, to all interconnections between a reactor protection system (as defined and explained in International Electrotechnical Commission Publication 231 A, first supplement to Publication 231, General Principles of Nuclear Reactor Instrumentation) and all other systems and equipment not part of the protection system, except: a) the physical connection between sensors of the protection system and the physical variables that they monitor, such as for example, thermo wells, moderating medium for neutron sensors, etc.; b) the electrical connection between the protection system and the reactor control rods or other safety mechanism; c) the electrical and pneumatic connections to the power distribution system (mains) and pneumatic supplies that supply power to the protection system. Although many clauses relate to all reactor protection systems, this standard applies mainly to protection systems in nuclear power reactors

  19. Managing medical treatment waste and effluent: the point of view of a nuclear medicine practitioner; Gestion des dechets et effluents issus de traitements medicaux: le point de vue d'un praticien de medecine nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Karcher, G. [Chef du Service de medecine nucleaire de l' Hopital d' adultes de Brabois - CHU, 54 - Nancy (Meurthe-et-Moselle) (France)

    2011-02-15

    The nuclear medicine department of the Nancy CHU hospital is one of the largest in France: 16.000 patients are welcomed each year and 4.000 persons undergo a tomography there. 5 shielded and isolated rooms, dedicated to Iodine{sup 131} treatment, allow the care of 150 to 200 patients each year. The head of the nuclear medicine department gives his meaning about the new regulation on the management of radioactive effluents. According to him, regulations are necessary but the values of the imposed thresholds have to be scientifically justified. Another point is that a lot of money is spent on radiation protection issues while the radioactive risks are almost null, which leads to wasting money. The elaboration of the radioprotection regulations must be made not as a whole but on a specific basis according to the domain: nuclear power plants, research reactors or nuclear medicine, it applies. (A.C.)

  20. Final Environmental Statement related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410)

    International Nuclear Information System (INIS)

    1985-05-01

    This Final Environmental Statement contains the assessment of the environmental impact associated with the operation of the Nine Mile Point Nuclear Station, Unit 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs

  1. Millimeter length micromachining using a heavy ion nuclear microprobe with standard magnetic scanning

    Energy Technology Data Exchange (ETDEWEB)

    Nesprías, F. [Gerencia de Investigación y Aplicaciones, Comisión Nacional de Energía Atómica, Av. Gral Paz 1499 (1650), San Martín, Buenos Aires (Argentina); Debray, M.E., E-mail: debray@tandar.cnea.gov.ar [Gerencia de Investigación y Aplicaciones, Comisión Nacional de Energía Atómica, Av. Gral Paz 1499 (1650), San Martín, Buenos Aires (Argentina); Escuela de Ciencia y Tecnología. Universidad Nacional de Gral. San Martín, M. De Irigoyen 3100 (1650), San Martín, Buenos Aires (Argentina); Davidson, J. [Gerencia de Investigación y Aplicaciones, Comisión Nacional de Energía Atómica, Av. Gral Paz 1499 (1650), San Martín, Buenos Aires (Argentina); CONICET, Avda. Rivadavia 1917 (C1033AAJ), Ciudad Autónoma de Buenos Aires (Argentina); Kreiner, A.J. [Gerencia de Investigación y Aplicaciones, Comisión Nacional de Energía Atómica, Av. Gral Paz 1499 (1650), San Martín, Buenos Aires (Argentina); Escuela de Ciencia y Tecnología. Universidad Nacional de Gral. San Martín, M. De Irigoyen 3100 (1650), San Martín, Buenos Aires (Argentina); CONICET, Avda. Rivadavia 1917 (C1033AAJ), Ciudad Autónoma de Buenos Aires (Argentina); and others

    2013-04-01

    In order to increase the scanning length of our microprobe, we have developed an irradiation procedure suitable for use in any nuclear microprobe, extending at least up to 400% the length of our heavy ion direct writing facility using standard magnetic exploration. Although this method is limited to patterns of a few millimeters in only one direction, it is useful for the manufacture of curved waveguides, optical devices such Mach–Zehnder modulators, directional couplers as well as channels for micro-fluidic applications. As an example, this technique was applied to the fabrication of 3 mm 3D-Mach–Zehnder modulators in lithium niobate with short Y input/output branches and long shaped parallel-capacitor control electrodes. To extend and improve the quality of the machined structures we developed new scanning control software in LabView™ platform. The new code supports an external dose normalization, electrostatic beam blanking and is capable of scanning figures at 16 bit resolution using a National Instruments™ PCI-6731 High-Speed I/O card. A deep and vertical micromachining process using swift {sup 35}Cl ions 70 MeV bombarding energy and direct write patterning was performed on LiNbO{sub 3}, a material which exhibits a strong natural anisotropy to conventional etching. The micromachined structures show the feasibility of this method for manufacturing micro-fluidic channels as well.

  2. Implantation of a new Beta Secondary Standard system at Centro de Desenvolvimento da Tecnologia Nuclear

    International Nuclear Information System (INIS)

    Reynaldo, Sibele Reis

    2005-01-01

    The crescent use of beta radiation sources in medical, industrial and research applications has increased the need for higher accuracy in beta dosimetry. As the first Beta Secondary Standard system (BSS1) was developed about 20 years ago, a new BSS2 system was made commercially available to fulfill new metrological demands and to follow the technological development. The BSS2 has a new positioning set-up, high activity and long half-life beta radiation sources and a special safety system. The Centro de Desenvolvimento da Tecnologia Nuclear is the first laboratory in Latin America that has got a BSS2. This work describes the BSS2 and it compares its advantages in relation to BSS1; results of the beam uniformity tests of the radiation fields from 90 Sr/ 90 Y, 85 Kr and 147 Pm sources, that were measured with an ionization chamber and with thermoluminescent detectors, are also shown. Results show that the beta radiation fields are considered to be uniform for diameters between 8 and 20 cm according to the chosen source. (author)

  3. Reliability study: digital reactor protection system of Korean standard nuclear power plant

    International Nuclear Information System (INIS)

    Kang, H. G.; Jang, S. C.; Eom, H. S.; Jeong, H. S.

    2003-02-01

    Digital safety-critical systems which are now installed in Korean Standard Nuclear Power Plants (KSNPP) would be quantitatively evaluated in order to prove the safety. In this study, we quantify the safety of the digital reactor protection system in KSNPPs using PSA technology. This study also includes the detailed investigation of the target system operation. The Fault Tree (FT) models were constructed for 15 reactor trip parameters. For digital parts, because the operation data for the same type PWR was unavailable, we used the data provided by vendors. On the other hand, for the conventional analog/mechanical parts, we used experience data presented in KAERI/TR-2164/2002.The result of quantification shows that the system unavailability varies from 4.36E-5 to 8.96E-4 according to the trip parameter. Main contributor to the difference from the conventional analysis would be the difference in human failure probability estimation. Generally, the system unavailability depends on several important factors: Human failure probability, software failure probability, watchdog timer coverage, and common cause failure estimation

  4. Earthquakes and aseismatic design standard for nuclear power stations in F.R. Germany

    International Nuclear Information System (INIS)

    Ide, Akira

    1976-01-01

    Brief history of the earthquakes in F.R. Germany for the period from 1000 to 1969 is reviewed, and comparison of the aseismatic design of nuclear power stations between F.R. Germany and Japan is made. Earthquakes of intensity 7 (maximum acceleration value of 70 to 220 gal) and 8 (that of 150 to 300 gal) could be expected to occur in F.R. Germany, according to European seismic committee. The definitions of safety earthquake (Sicherheitserdbeben) and design earthquake (Auslegungserdbeben) are compared with the Japanese terms, S-2 (maximum possible earthquake giving the strongest vibration to site base) and S-1 (maximum probable earthquake giving the strongest vibration to site base). The total area of F.R. Germany is classified into four zones according to dangerousness. Aseismatic design in F.R. Germany is classified into two classes, whereas that in Japan into three or four classes. In F.R. Germany, either dynamic analysis, simple analysis, or omission of analysis is employed. F.R. Germany employs the waves of E1-centro, Taft, etc. of USA as standard, referring to U.S.N.R.C. 1.60 and Housner's equation. The attenuation coefficient and the allowable stress are also compared. A power plant to be exported to Iran is designed at SE of 500 gal and AE of 250 gal, which are approximately equal to the maximum earthquake acceleration for design in Japan. (Iwakiri, K.)

  5. Construction of APR1000 nuclear power information management system based on international standards

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Seung Hwan [Korea Electric Power Research Institute, Daejeon (Korea, Republic of); Song, Deok Yong; Han, Byung Sub [Enesys Co., Daejeon (Korea, Republic of); An, Kyung Ik; Hwang, Jin Sang [PartDB Co., Daejeon (Korea, Republic of)

    2010-10-15

    In recent years, due to speedy rise of international oil prices, orders of nuclear power plant construction have been in progress by many countries to solve the stable supply of power. Our country has continued to perform nuclear power construction. As only a few developed countries like Japan and European countries have its own nuclear power construction technology, competition among them is keen. Our country has awarded the contract of UAE nuclear power plants based on the accumulated nuclear power plant construction technologies so far. In this regard, KEPCO has recognized the needs of information management system to manage nuclear power information and proceeded the implementation of nuclear power information management system for export-model

  6. How to manage flexible nuclear power plants in a deregulated electricity market from the point of view of social welfare?

    International Nuclear Information System (INIS)

    Lykidi, Maria; Gourdel, Pascal

    2015-01-01

    Flexible nuclear power plants can adjust their electricity production to the predicted evolution of demand. Under certain conditions, flexible operation is necessary to ensure the stability of the electricity system. However, despite the potential advantages of nuclear energy including the flexibility of nuclear reactors, the social acceptance of nuclear has reduced after the Fukushima accident, leading some countries to reduce or even phase out nuclear (e.g. Germany). So, a question that arises is how flexible nuclear power plants have to be operated in order to maximize social welfare. The French nuclear fleet gives an illustration of flexible management while social acceptance of nuclear is questioned; this was reflected in the new French Energy Transition law. Theoretically and numerically, we found that the production behavior that maximizes social welfare is characterized by a constant thermal production and a totally flexible nuclear production given sufficient nuclear capacity. - Highlights: • We determine the management of flexible nuclear plants to maximize social welfare. • We model the nuclear fuel stock as a “reservoir” of energy. • Social optimum is given by a totally flexible management of the nuclear production. • The level of thermal production of the optimal solution is always constant. • We need to invest in nuclear energy to ensure social optimum within our model

  7. Safety Evaluation Report related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410)

    International Nuclear Information System (INIS)

    1985-02-01

    The Safety Evaluation Report for the application filed by the Niagara Mohawk Power Corporation, as applicant and co-owner, for a license to operate the Nine Mile Point Nuclear Station, Unit 2 (Docket No. 50-410), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  8. What should be learned from the 2011 off the Pacific coast of Tohoku Earthquake to formulate the standard seismic motion of a nuclear power plant

    International Nuclear Information System (INIS)

    Nozu, Atsushi

    2017-01-01

    Although inter plate earthquake is also taken into account in the formulation of standard seismic motion of a nuclear power plant, the lessons of the 2011 off the Pacific coast of Tohoku Earthquake are not fully utilized in the evaluation of the strong motion record. This paper discussed the following three points. (1) During the 2011 off the Pacific coast of Tohoku Earthquake, sharp pulses generated from a narrow area (SPGA: strong motion pulse generation area) on the fault plane determined the maximum amplitude of the earthquake ground motion at the nuclear power plant. (2) In order to accurately calculate this pulse, the current SMGA model is insufficient. (3) The seismic motion evaluated on the assumption that the SPGA is close to a nuclear power plant can exceed the assumption made by power companies. From the studies so far, it is clear that the current SMGA model cannot accurately calculate pulse waves with a time width of 1 to 2 seconds that is technically important, and its causes are clear. For this reason, the SMGA model is not suitable as a seismic source model for establishing the standard seismic motion of a nuclear power plant. It is necessary to have a model that can reproduce the earthquake ground motion due to the 2011 off the Pacific coast of Tohoku Earthquake, in an accuracy of SPGA model or higher. Pulse waves with a time width of 1 to 2 seconds that simultaneously bring about large accelerations and speeds are likely accompany plasticization and cause major damage. (A.O.)

  9. Nordic Nuclear Safety Research 1994 - 2008: From standardized 4-year classics to customized R and B

    Energy Technology Data Exchange (ETDEWEB)

    Bennerstedt, T.N.O. (TeknoTelje HB, Torhamn (Sweden))

    2011-10-15

    This is a presentation of NKS (Nordic Nuclear Safety Research), its work and achievements in the years 1994 - 2008, during which the author served as Nordic secretary and (later) as coordinator. NKS and the Nordic perspective are briefly introduced together with the NKS support structure, organization and administration: Owners, Board, Nordic secretary, Bureau and Secretariat. The author then embarks on a journey through the modern history of NKS work. The last two of the six fixed 4-year programs are described as regards planning, contents, project work, administration, dissemination of results, evaluations and conclusions. The trip continues to the land of R and B and the present (2011) structure of two general frameworks, namely, NKS-R: reactor safety, and NKS-B: emergency preparedness; each consisting of a set of flexible activities; hence, R and B. The reasoning behind this makeover is touched upon together with the new organization and simpler administration that developed. Major activities and the produced results are introduced and the evaluations summarized. The author's own conclusions and recommendations are followed by a short and subjective list of references. In a number of appendices some important background material has been compiled: bullet point versions of minutes of Owners Group and Board meetings; economic contributions and budgets; the NKS policy document; an overview of all NKS programs and evaluations; lists of R and B activities and funding; the author's personal remarks; a list of some NKS documents (other than technical reports and minutes); and a list of acronyms used in this report. (Author)

  10. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solutions

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1999-01-01

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solution to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Determination of Uranium 7 Specific Gravity by Pycnometry 15-20 Free Acid by Oxalate Complexation 21-27 Determination of Thorium 28 Determination of Chromium 29 Determination of Molybdenum 30 Halogens Separation by Steam Distillation 31-35 Fluoride by Specific Ion Electrode 36-42 Halogen Distillate Analysis: Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 43 Determination of Chloride and Bromide 44 Determination of Sulfur by X-Ray Fluorescence 45 Sulfate Sulfur by (Photometric) Turbidimetry 46 Phosphorus by the Molybdenum Blue (Photometric) Method 54-61 Silicon by the Molybdenum Blue (Photometric) Method 62-69 Carbon by Persulfate Oxidation-Acid Titrimetry 70 Conversion to U3O8 71-74 Boron by ...

  11. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Plutonium by Controlled-Potential Coulometry Plutonium by Amperometric Titration with Iron(II) Plutonium by Diode Array Spectrophotometry Free Acid by Titration in an Oxalate Solution 8 to 15 Free Acid by Iodate Precipitation-Potentiometric Titration Test Method 16 to 22 Uranium by Arsenazo I Spectrophotometric Test Method 23 to 33 Thorium by Thorin Spectrophotometric Test Method 34 to 42 Iron by 1,10-Phenanthroline Spectrophotometric Test Method 43 to 50 Impurities by ICP-AES Chloride by Thiocyanate Spectrophotometric Test Method 51 to 58 Fluoride by Distillation-Spectrophotometric Test Method 59 to 66 Sulfate by Barium Sulfate Turbidimetric Test Method 67 to 74 Isotopic Composition by Mass Spectrom...

  12. A REVIEW ON DEVELOPING INDUSTRIAL STANDARDS TO INTRODUCE DIGITAL COMPUTER APPLICATION FOR NUCLEAR I&C AND HMIT IN JAPAN

    Directory of Open Access Journals (Sweden)

    HIDEKAZU YOSHIKAWA

    2013-04-01

    In Japan, the Fukushima Daiichi accident that occurred on March 11, 2011 has great impact on nuclear regulation and nuclear industries where concerns by the general public about safety have heightened significantly. However for the part of HF design and software reliability maintenance of digital I&C and HMIT for NPP, the author believes that the past practice of Japanese activities with the related technical standards can be successfully inherited in the future, by reinforcing the technical preparedness for the prevention and mitigation against any types of severe accident occurrence.

  13. [The first exploration of a minimally invasive lysis subcutaneouly for the treatment of gluteal muscle contracture based on relatively safe region around standard injection point of gluteal muscle].

    Science.gov (United States)

    Xiao, Ying; Tang, Zhi-hong; Zhang, Si-rong; Zou, Guo-yao; Xiao, Rong-chi; Liu, Rui-duan; Hu, Jun-zu

    2011-06-01

    To explore the solution of choosing the minimally invasive incision site for gluteal muscle contracture patient based on standard injection point of gluteal muscle. from September 2008 to August 2010, 25 patients (14 males and 11 females with an average of 16.5 years, ranging from 12 to 26 years) with injected gluteal muscle contracture were prospectively studied. The course of disease was from 6 to 12 years. Firstly, the connective skin Surface line from anterior superior iliac spine to coccyx (line AD) was delineated and the point (point O) was marked out as the standard gluteal muscle injection site which was on the one-third of the distance from the anterior superior iliac spine(point A) to the coccyx (point D). Secondly, the anterior and posterior edge lines of surface projection of the gluteal muscle contracture banding (line a, line p) were delineated. Thirdly, the distance from B to O and C to O (B is the point of intersection of line a and line AD,C is the point of intersection of line P and line AD)were measured which was the intersection of line a,p and line AD to point O. Lastly, the minimally invasive surgery was operformed via the skin entry of point C. OB = (0 +/- 0.76) cm, OC = (2.86 +/- 0.78) cm, BC = (2.86 +/- 1.01) cm,the mean postoperative drainage was less than 10 ml,there was no nerve damage,hematoma and other complications. All patients achieved the function of squatting in 4 to 6 days. The solution of choosing the minimally invasive incision site based on standard injection point of gluteal muscle has advantages of positioning precisely,handling easily, recoverying quickly, less trauma and safety, etc.

  14. Insights of the periodic reviews regarding the physical protection of nuclear power plants designed to earlier standards

    International Nuclear Information System (INIS)

    Hagemann, A.

    2001-01-01

    Among other prerequisites for licensing a nuclear activity, the German Atomic Energy Act stipulates that the necessary physical protection against malevolent acts has to be approved before granting a license. This is required for nuclear power plants in paragraph 7 of the Atomic Energy Act. The licenses for nuclear power plants designed to earlier standards were granted about 20 years ago and more. All NPPs are under the supervision of the Supervisory Authority in order to ensure that all conditions of the license are met during the whole plant operation period. The 'Periodic Safety Review', PSR, is designated to provide the Supervisory Authority with additional information on the safety status. One part of the PSR is the 'Deterministic Security Analysis', DSA. The subject of the DSA is the actual physical protection of a NPP. The following document outlines the experiences gained during the evaluation of DSA reports by GRS as an external expert organisation under contract of the Supervisory Authorities. (author)

  15. Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

    International Nuclear Information System (INIS)

    Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

    1978-10-01

    The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems

  16. Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

    Energy Technology Data Exchange (ETDEWEB)

    Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L. (eds.)

    1978-10-01

    The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems.

  17. Standard guide for application of radiation monitors to the control and physical security of special nuclear material

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1999-01-01

    1.1 This guide briefly describes the state-of-the-art of radiation monitors for detecting special nuclear material (SNM) (see 3.1.11) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms. 1.2 Dependable operation of SNM radiation monitors rests on selecting appropriate monitors for the task, operating them in a hospitable environment, and conducting an effective program to test, calibrat...

  18. Study of the effects of a tornado on a nuclear plant(from the point of view of civil engineering); Estudio de los efectos de un tornado sobre una central nuclear (desde el punto de vista de la ingenieria civil)

    Energy Technology Data Exchange (ETDEWEB)

    Melendro, J.

    2010-07-01

    is to analyze the applicability of Regulatory Guide 1.76 {sup d}esign basis Tornado and Tornado Missiles for Nuclear Power Plants{sup ,} assessing the guide / standard compliance of a nuclear facility with respect to it, identifying the actions required for the compliance if applicable and valuation, with engineering judgment, the benefits for the plant would total or partial implantation of the guide.

  19. Development of departmental standard for traceability of measured activity for I-131 therapy capsules used in nuclear medicine

    Directory of Open Access Journals (Sweden)

    Ravichandran Ramamoorthy

    2011-01-01

    Full Text Available International Basic Safety Standards (International Atomic Energy Agency, IAEA provide guidance levels for diagnostic procedures in nuclear medicine indicating the maximum usual activity for various diagnostic tests in terms of activities of injected radioactive formulations. An accuracy of ± 10% in the activities of administered radio-pharmaceuticals is being recommended, for expected outcome in diagnostic and therapeutic nuclear medicine procedures. It is recommended that the long-term stability of isotope calibrators used in nuclear medicine is to be checked periodically for their performance using a long-lived check source, such as Cs-137, of suitable activity. In view of the un-availability of such a radioactive source, we tried to develop methods to maintain traceability of these instruments, for certifying measured activities for human use. Two re-entrant chambers [(HDR 1000 and Selectron Source Dosimetry System (SSDS] with I-125 and Ir-192 calibration factors in the Department of Radiotherapy were used to measure Iodine-131 (I-131 therapy capsules to establish traceability to Mark V isotope calibrator of the Department of Nuclear Medicine. Special nylon jigs were fabricated to keep I-131 capsule holder in position. Measured activities in all the chambers showed good agreement. The accuracy of SSDS chamber in measuring Ir-192 activities in the last 5 years was within 0.5%, validating its role as departmental standard for measuring activity. The above method is adopted because mean energies of I-131 and Ir-192 are comparable.

  20. Comparison between technical requirements in different standards on synthesis of design ground motion history for nuclear power plants

    International Nuclear Information System (INIS)

    Li Zhongcheng; Tianjin Univ., Tianjin; Zhao Fengxin

    2006-01-01

    The main technical requirements in several domestic and American Standards, Codes and Guides involved in the seismic analysis and design activities of nuclear power plants (NPPs) in China are construed in detail . Based on better understanding of the technical backgrounds and resultant requirements on the synthesis of design ground motion history for NPPs, some discussions and viewpoints in application are conducted together with the engineering in practice. Some conclusions can be provided for reference to conduct the seismic safety evaluation, seismic analysis and design of NPPs. And the suggestions in this paper can be employed in the revision and refinement of the relevant Standards, Codes and Guides in China. (authors)

  1. Protective coatings (paints) for the nuclear industry - approved standard 1974 - (revision and redesignation of N5.9-1967)

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    A standard is presented which provides a common basis on which protective coatings (paints) for surfaces in a nuclear complex may be compared and selected by reproducible tests. The environmental conditions of these complexes are such that a paint may be deteriorated by exposure to any, all, or a combination of the following conditions: ionizing radiation; contamination by radioactive nuclides and decontamination processes, chemicals; immersion in highly purified water; and abrasion or wear. This standard specifically applies to the surfaces of such facilities as reactors, fuel reprocessing plants, and laboratories and hot cells

  2. $\\beta$-asymmetry measurements in nuclear $\\beta$-decay as a probe for non-standard model physics

    CERN Multimedia

    Roccia, S

    2002-01-01

    We propose to perform a series of measurements of the $\\beta$-asymmetry parameter in the decay of selected nuclei, in order to investigate the presence of possible time reversal invariant tensor contributions to the weak interaction. The measurements have the potential to improve by a factor of about four on the present limits for such non-standard model contributions in nuclear $\\beta$-decay.

  3. Standard practice for determining coating contractor qualifications for nuclear powered electric generation facilities

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    This practice provides a criteria guide and procedural method to assist utility owners, architects, engineers, constructors, and other selection agencies in determining the overall qualifications of a coating contractor to execute coating work for the primary containment and other safety-related facilities of light-water nuclear power plants. The qualification criteria and requirements address the essential basic capability of a contractor to execute nuclear coating work. Obviously, the specific capability to execute those requirements unique to a given project must also be carefully considered. The evaluation procedure contained in this practice is designed to be adaptive to this detailed final qualification process. Variation or simplification of the practice is appropriate for non safety-related areas of nuclear power plants, fossil fueled facilities, and other industrial projects. The overall capability of a contractor to successfully execute the varied and complex requirements of nuclear coating work is dependent upon competency in a variety of essential categories

  4. Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2006-01-01

    1.1 Nuclear Research Emulsions (NRE) have a long and illustrious history of applications in the physical sciences, earth sciences and biological sciences (1,2) . In the physical sciences, NRE experiments have led to many fundamental discoveries in such diverse disciplines as nuclear physics, cosmic ray physics and high energy physics. In the applied physical sciences, NRE have been used in neutron physics experiments in both fission and fusion reactor environments (3-6). Numerous NRE neutron experiments can be found in other applied disciplines, such as nuclear engineering, environmental monitoring and health physics. Given the breadth of NRE applications, there exist many textbooks and handbooks that provide considerable detail on the techniques used in the NRE method. As a consequence, this practice will be restricted to the application of the NRE method for neutron measurements in reactor physics and nuclear engineering with particular emphasis on neutron dosimetry in benchmark fields (see Matrix E706). 1...

  5. The Study for the Establishment of the Korea Nuclear Liability System complying with International Standards

    International Nuclear Information System (INIS)

    Lee, D. S.; Chung, W. S.; Yun, S. W.; Kim, H. J.; Lee, J. H.

    2011-06-01

    This study is for making system of the fast and adequate compensation to the victim in the nuclear accident of domestic and foreign country. As a method to come true the purpose we reviewed Convention on Supplementary Compensation for Nuclear Damage (hereinafter 'CSC') and designed enabling laws for joining the CSC. Moreover international workshop regarding the CSC was hold as a main assignment of this study for sharing knowledge and information with neighboring countries. Convention relating to Civil Liability in the Field of Maritime Carriage on Nuclear Material, 1971 shall be analyzed in this study. Legal approach to the CSC and designing enabling laws for joining the CSC were enclosed to this study. As a result of the international workshop this study shows how U.S. (CSC member country) deals with CSC and mandatory obligation of donating the public funds. Finally Convention relating to Civil Liability in the Field of Maritime Carriage on Nuclear Material, 1971 is analyzed legally

  6. French regulations in the nuclear field and standards related to nuclear pressure equipment; Reglementation francaise dans le domaine nucleaire et normes relatives aux equipements sous pression nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Mourlon, S.; Limousin, S.; Van Hoecke, J.C. [Autorite de surete nucleaire 6, place du Colonel Bourgoin 75012 Paris (France)

    2007-07-01

    French regulations on nuclear pressure equipment have been updated with the December 12, 2005 Order related to Nuclear Pressure Equipment, so-called 'ESPN Order'. This Order is at the junction of regulations covering safety on the one hand and pressure equipment on the other hand. As regards manufacturing, the ESPN Order extends to nuclear pressure equipment the approach and essential requirements of the European Pressure Equipment Directive (PED - transposed in France by the December 13, 1999 Decree) while adding specific nuclear and radiation safety requirements. For in-service inspection, it sets additional provisions to those of the December 13, 1999 Decree so that the nuclear and radiation safety requirements applying in nuclear facilities are also taken into account for those equipment. The specific case of PWR main primary and secondary systems is covered by the November 10, 1999 Order. The ESPN Order leaves a major part to industrial codes and standards. Its publication makes it necessary to check that the codes used for nuclear pressure equipment comply with the new requirements and may induce modifications of the codes. Furthermore, as the market for operators of nuclear facilities and manufacturers of mechanical equipment is becoming global, these evolutions should be considered in a worldwide context. Last, the Nuclear Transparency and Security Act of June 13, 2006 - which created the Nuclear safety authority (ASN) with competence over nuclear and radiation safety, covering specifically nuclear pressure equipment - will induce further amendments of regulations. (authors) [French] La reglementation francaise en matiere d equipements sous pression nucleaires a ete refondee avec la parution de l arrete du 12 decembre 2005 relatif aux equipements sous pression nucleaires, dit 'arrete ESPN'. Ce texte se situe a l intersection des reglementations en matiere de surete, d une part, et d equipements sous pression, d autre part. En matiere de

  7. Development in France of nuclear safety technical regulations and standards used in the licensing procedure

    International Nuclear Information System (INIS)

    Lebouleux, P.

    1983-04-01

    Initially, the Commissariat a l'Energie Atomique was the overall structure which encompassed all nuclear activities in France, including those connected with radiological protection and nuclear safety. As other partners appeared, the Authorities have laid down national regulations relative to nuclear installations since 1963. These regulations more particularly provide for the addition of prescriptions with which the applicant must comply to obtain the necessary licenses and the establishment of General Technical Regulations pertaining to nuclear safety. The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operation of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridical sense; they are called ''Regles Fondamentales de Surete'' (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation practice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. A RFS, or a letter, can also give the result of the examination of the constructor and operator codes (RCC) by safety authorities

  8. Review of the development of nuclear power in the Western World from the Russian point of view

    International Nuclear Information System (INIS)

    Kotler, V.R.

    1981-01-01

    A general representation of the state of affairs in the field of nuclear powerstations is given, supported by figures on nuclear power generation from plant in operation and under construction. The data refer to the state of affairs in mid-1980. (UA) [de

  9. Safety Analysis of 'Older/Aged' Handling and Transportation Equipment for Heavy Loads, Radioactive Waste and Materials in Accordance with German Nuclear Standards KTA 3902, 3903 and 3905

    International Nuclear Information System (INIS)

    Macias, P.; Prucker, E.; Stang, W.

    2006-01-01

    The purpose of this paper is to present a general safety analysis of important handling and transportation processes and their related equipment ('load chains' consisting of cranes, load-bearing equipment and load-attaching points). This project was arranged by the responsible Bavarian ministry for environment, health and consumer protection (StMUGV) in agreement with the power plant operators of all Bavarian nuclear power plants to work out potential safety improvements. The range of the equipment (e.g. reactor building, crane, refuelling machine, load-bearing equipment and load-attaching points) covers the handling and transportation of fuel elements (e. g. with fuel flasks), heavy loads (e.g. reactor pressure vessel closure head, shielding slabs) and radioactive materials and waste (e.g. waste flasks, control elements, fuel channels, structure elements). The handling equipment was subjected to a general safety analysis taking into account the ageing of the equipment and the progress of standards. Compliance with the current valid requirements of the state of science and technology as required by German Atomic Act and particularly of the nuclear safety KTA-standards (3902, 3903 and 3905) was examined. The higher protection aims 'safe handling and transportation of heavy loads and safe handling of radioactive materials and waste' of the whole analysis are to avoid a criticality accident, the release of radioactivity and inadmissible effects on important technical equipment and buildings. The scope of the analysis was to check whether these protection aims were fulfilled for all important technical handling and transportation processes. In particularly the design and manufacturing of the components and the regulations of the handling itself were examined. (authors)

  10. Near term feasibility of nuclear reactor for sea-water desalting: coupling of standard condensing nuclear power stations to low grade heat multieffect distillation plants

    International Nuclear Information System (INIS)

    Adar, J.; Manor, S.; Schaal, M.

    1977-01-01

    Commercial nuclear power reactors exist only in standard sizes and designs. No large nuclear back-pressure turbines are available today. Therefore, near term large scale nuclear desalination plants must be tailored to the NSSS sizes and available turbines and not the contrary. Standard condensing nuclear turbines could operate continuously with a back-presure of up to 5-7'' Hg (depending on the supplier). It means that they can exhaust huge amounts of steam at 56 0 C - 64 0 C with a loss of electricity production of 6% - 10% when compared to 2 1/2'' Hg normal condensing pressure. The horizontal aluminium tube multi-effect distillation process developed by ''Israel Desalination Engineering'' Ltd. is very suitable for the use of such low-grade heat: 4 to 9 effects can operate within these temperature ranges. A special flash-chamber constitutes a positive barrier against any possible contamination being carried over by the steam exhausted from the turbine to the desalination plant. Flow sheets, heat and mass balances have been prepared for two standard sizes of NSSS and turbines (1882sup(Mwth) and 2785sup(Mwth)), two ''back-pressures'' (5 1/2'' and 7'' Hg), and corresponding desalination plants. Only standard equipment is being used in the steam and electricity producing plant. The desalination plant consists of 6 to 12 parallel double lines, each of them similar to a large prototype now being designed and which is going to be coupled to an old fossil power station. Water production varies between 50 and 123 sup(us MGD) and water cost between 23 and 36 sup(cents)/M 3 . Total energy requirements of the desalination plant represent only 19 to 50% of the total water cost as against 75% for a single purpose plant. Costs are based on actual bids for the power plant and actual estimates for the desalination prototype. The operation is designed to be flexible so that the power plant can be operated either in conjunction with the desalination plant, or as a single purpose

  11. Standard model for the safety analysis report of nuclear fuel reprocessing plants; Modelo padrao para relatorio de analise de seguranca de usinas de reprocessamento de combustiveis nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-02-15

    This norm establishes the Standard Model for the Safety Analysis Report of Nuclear Fuel Reprocessing Plants, comprehending the presentation format, the detailing level of the minimum information required by the CNEN for evaluation the requests of Construction License or Operation Authorization, in accordance with the legislation in force. This regulation applies to the following basic reports: Preliminary Safety Analysis Report - PSAR, integrating part of the requirement of Construction License; and Final Safety Analysis Report (FSAR) which is the integrating part of the requirement for Operation Authorization.

  12. World Nuclear Association (WNA) internationally standardized reporting (checklist) on the sustainable development performance of uranium mining and processing sites

    International Nuclear Information System (INIS)

    Harris, F.

    2014-01-01

    The World Nuclear Association (WNA) has developed internationally standardized reporting (‘Checklist’) for uranium mining and processing sites. This reporting is to achieve widespread utilities/miners agreement on a list of topics/indicators for common use in demonstrating miners’ adherence to strong sustainable development performance. Nuclear utilities are often required to evaluate the sustainable development performance of their suppliers as part of a utility operational management system. In the present case, nuclear utilities are buyers of uranium supplies from uranium miners and such purchases are often achieved through the utility uranium or fuel supply management function. This Checklist is an evaluation tool which has been created to collect information from uranium miners’ available annual reports, data series, and measurable indicators on a wide range of sustainable development topics to verify that best practices in this field are implemented throughout uranium mining and processing sites. The Checklist has been developed to align with the WNA’s policy document Sustaining Global Best Practices in Uranium Mining and Processing: Principles for Managing Radiation, Health and Safety, and Waste and the Environment which encompasses all applicable aspects of sustainable development to uranium mining and processing. The eleven sections of the Checklist are: 1. Adherence to Sustainable Development; 2. Health, Safety and Environmental Protection; 3. Compliance; 4. Social Responsibility and Stakeholder Engagement; 5. Management of Hazardous Materials; 6. Quality Management Systems; 7. Accidents and Emergencies; 8. Transport of Hazardous Materials; 9. Systematic Approach to Training; 10. Security of Sealed Radioactive Sources and Nuclear Substances; 11. Decommissioning and Site Closure. The Checklist benefits from many years of nuclear utility experience in verifying the sustainable development performance of uranium mining and processing sites. This

  13. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach Nuclear Power Plant, Units 1 and 2

    International Nuclear Information System (INIS)

    Laudenbach, D.H.

    1979-03-01

    The technical evaluation is presented for the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach nuclear power plant, Units 1 and 2. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Support Program being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore Laboratory

  14. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach Nuclear Power Plant, Units 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Laudenbach, D.H.

    1979-03-01

    The technical evaluation is presented for the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach nuclear power plant, Units 1 and 2. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Support Program being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore Laboratory.

  15. Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 2: Data standardization for tank calibration

    International Nuclear Information System (INIS)

    2007-01-01

    Measurements of the volume and height of liquid in a process accountancy tank are often made in order to estimate or verify the tank's calibration or volume measurement equation. The calibration equation relates the response of the tank's measurement system to some independent measure of tank volume. The ultimate purpose of the calibration exercise is to estimate the tank's volume measurement equation (the inverse of the calibration equation), which relates tank volume to measurement system response. In this part of ISO 18213, it is assumed that the primary measurement-system response variable is liquid height and that the primary measure of liquid content is volume. This part of ISO 18213 presents procedures for standardizing a set of calibration data to a fixed set of reference conditions so as to minimize the effect of variations in ambient conditions that occur during the measurement process. The procedures presented herein apply generally to measurements of liquid height and volume obtained for the purpose of calibrating a tank (i.e. calibrating a tank's measurement system). When used in connection with other parts of ISO 18213, these procedures apply specifically to tanks equipped with bubbler probe systems for measuring liquid content. The standardization algorithms presented herein can be profitably applied when only estimates of ambient conditions, such as temperature, are available. However, the most reliable results are obtained when relevant ambient conditions are measured for each measurement of volume and liquid height in a set of calibration data. Information is provided on scope, physical principles, data required, calibration data, dimensional changes in the tank, multiple calibration runs and results on standardized calibration data. Four annexes inform about density of water, buoyancy corrections for mass determination, determination of tank heel volume and statistical method for aligning data from several calibration runs. A bibliography is

  16. Activity on non-destructive testing as constituent element of the quality management in accordance with ISO 9001:2000 standard at The Institute of Nuclear Physics, Kazakhstan

    International Nuclear Information System (INIS)

    Kadyrzhanov, K.K.; Kislitsin, S.B.; Ablanov, M.B.

    2004-01-01

    An increase of technical and public safety requirements for facilities of nuclear industries, an efficient quality control based on non-destructive testing (NDT) techniques is crucial. Therefore, Institute of Nuclear Physics (INP) through NDT Division makes efforts towards a competent NDT inspection of its facilities starting from research reactor of WWR-K type with a further activity according to the National Program for Development in Nuclear Industry. The additional objective is to harmonize the present codes and standards for Nuclear Industry as an integral part of the INP policy in a quality management according ISO 9001:2000 Standard. (author)

  17. An introduction and overview of DRAFT CSA Standard N288.7 Groundwater Protection at Class I Nuclear Facilities and Uranium Mines and Mills

    Energy Technology Data Exchange (ETDEWEB)

    DeWilde, J., E-mail: john_dewilde@golder.com [Golder Associates Ltd., Whitby, ON (Canada); Klukas, M.; Audet, M., E-mail: marc.audet@cnl.ca [Canadian Nuclear Laboratories, Chalk River, ON (Canada)

    2015-07-01

    The DRAFT CSA Standard N288.7 entitled Groundwater Protection at Class I Nuclear Facilities and Uranium Mines and Mills is currently under development and is anticipated to publish in June of 2015. This draft standard identifies a process for the protection and monitoring of groundwater at nuclear facilities but may also be used at any facility (i.e. nuclear facilities that are not Class I or non-nuclear facilities). The paper discusses the background to the draft standard, the formalized methodology described in the draft standard and provides some input on implementation. The paper is intended for people that have responsibilities related to groundwater protection at facilities that may need to comply with the draft standard or any site/facility that has some form of groundwater monitoring program. (author)

  18. Investigating the cut points of CCQ, CAT and MMRC according to gold 2013 with SGRQ as standard

    NARCIS (Netherlands)

    Alma, H.; De Jong, C.; Jelusic, D.; Wittmann, M.; Schuler, M.; Schultz, K.; Tsiligianni, I.; Kocks, J.; Van Der Molen, T.

    2014-01-01

    Rationale In the Global Initiative for Chronic Obstructive Lung Disease (GOLD) 2013 strategy document, assessment of symptoms is advised to be performed by the Clinical COPD Questionnaire (CCQ), COPD Assessment Test (CAT), or modified Medical Research Council (mMRC). Cut points of resp. CCQ≥1,

  19. Nuclear power in the United States of America and in Europe - a market survey from a vendor's point of view

    International Nuclear Information System (INIS)

    Christopher, T.A.; Gueldner, R.

    2002-01-01

    A world population continuing to grow must be provided with sufficient energy supplies at acceptable prices and so as to affect the environment and the climate as little as possible. A growing energy requirement can be met sustainably by a diversified energy mix. Globally, there is a reassessment of nuclear power. Under aspects of the economy, protection of the environment and the climate, geological availability, and geopolitics, nuclear power will make valuable contributions to a solution. In the United States, the use of nuclear power has become attractive again in the course of deregulation and as a result of massive increases in plant availability. The nuclear power plants currently in operation offer a promising outlook for the future, also because of the current price increases for natural gas. As a consequence of the Green Paper by the EU Commission on the continuity of supply, nuclear power is being reassessed also in Europe. As a result of deregulation of the electricity market, efforts have been made to increase the competitiveness of existing generating capacities. In accordance with changed market conditions, producers have adapted to the requirements of the market by establishing strategic partnerships. The envisaged construction of a nuclear power plant in Finland shows that also new nuclear power plants can be attractive in deregulated European markets and that, e.g., also the problems of spent fuel and waste management can be solved if the political will exists to do so. In Germany, on the other hand, the political framework conditions for nuclear power continue to be difficult. Unless Germany is willing to fall behind internationally in power generation, all available types of power generation will have to be advanced and combined into a mix serving future needs also in this country. There must be no disruption of technological know-how. Nuclear power must be an important option kept open under reasonable political boundary conditions. (orig.) [de

  20. Requirements of quality standards

    International Nuclear Information System (INIS)

    Mueller, J.

    1977-01-01

    The lecture traces the development of nuclear standards, codes, and Federal regulations on quality assurance (QA) for nuclear power plants and associated facilities. The technical evolution of the last twelve years, especially in the area of nuclear technology, led to different activities and regulatory initiatives, and the present result is: several nations have their own homemade standards. The lecture discusses the former and especially current activities in standard development, and gives a description of the requirements of QA-standards used in USA and Europe, especially Western Germany. Furthermore the lecture attempts to give a comparison and an evaluation of the international quality standards from the author's viewpoint. Finally the lecture presents an outlook for the future international implications of QA-standards. There is an urgent need within the nuclear industry for simplification and standardization of QA-standards. The relationship between the various standards, and the applicability of the standards need clarification and a better transparancy. To point out these problems is the purpose of the lecture. (orig.) [de

  1. 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

  2. Standard guide for qualification of laboratory analysts for the analysis of nuclear fuel cycle materials

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2003-01-01

    1.1 This guide covers the qualification of analysts to perform chemical analysis or physical measurements of nuclear fuel cycle materials. The guidance is general in that it is applicable to all analytical methods, but must be applied method by method. Also, the guidance is general in that it may be applied to initial qualification or requalification.

  3. The Number of Point Mutations in Induced Pluripotent Stem Cells and Nuclear Transfer Embryonic Stem Cells Depends on the Method and Somatic Cell Type Used for Their Generation.

    Science.gov (United States)

    Araki, Ryoko; Mizutani, Eiji; Hoki, Yuko; Sunayama, Misato; Wakayama, Sayaka; Nagatomo, Hiroaki; Kasama, Yasuji; Nakamura, Miki; Wakayama, Teruhiko; Abe, Masumi

    2017-05-01

    Induced pluripotent stem cells hold great promise for regenerative medicine but point mutations have been identified in these cells and have raised serious concerns about their safe use. We generated nuclear transfer embryonic stem cells (ntESCs) from both mouse embryonic fibroblasts (MEFs) and tail-tip fibroblasts (TTFs) and by whole genome sequencing found fewer mutations compared with iPSCs generated by retroviral gene transduction. Furthermore, TTF-derived ntESCs showed only a very small number of point mutations, approximately 80% less than the number observed in iPSCs generated using retrovirus. Base substitution profile analysis confirmed this greatly reduced number of point mutations. The point mutations in iPSCs are therefore not a Yamanaka factor-specific phenomenon but are intrinsic to genome reprogramming. Moreover, the dramatic reduction in point mutations in ntESCs suggests that most are not essential for genome reprogramming. Our results suggest that it is feasible to reduce the point mutation frequency in iPSCs by optimizing various genome reprogramming conditions. We conducted whole genome sequencing of ntES cells derived from MEFs or TTFs. We thereby succeeded in establishing TTF-derived ntES cell lines with far fewer point mutations. Base substitution profile analysis of these clones also indicated a reduced point mutation frequency, moving from a transversion-predominance to a transition-predominance. Stem Cells 2017;35:1189-1196. © 2017 AlphaMed Press.

  4. Draft environmental statement related to steam-generator repair at Point Beach Nuclear Plant, Unit No. 1. Docket No. 50-266

    International Nuclear Information System (INIS)

    1983-07-01

    The staff has considered the environmental impacts and economic costs of the proposed steam generator repair at the Point Beach Nuclear Plant Unit No. 1 along with reasonable alternatives to the proposed action. The staff has concluded that the proposed repair will not significantly affect the quality of the human environment and that there are no preferable alternatives to the proposed action. Furthermore, any impacts from the repair program are outweighed by its benefits

  5. Final environmental statement related to steam-generator repair at Point Beach Nuclear Plant, Unit No. 1 (Docket No. 50-266)

    International Nuclear Information System (INIS)

    1983-09-01

    The staff hhas considered the environental impacts and economic costs of the proposed steam generator repair at the Point Beach Nuclear Plant, Unit No. 1 along with reasonable alternatives to the proposed action. The staff has concluded that the proposed repair will not significantly affect the quality of the human environment and that there are no preferable alternatives to the proposed action. Furthermore, any impacts from the repair program are outweighed by its benefits

  6. The social effectiveness of small and medium-sized entities standard from the view point of Game Theory

    Directory of Open Access Journals (Sweden)

    Alexandre Gonzales

    2013-05-01

    Full Text Available Accounting has been undergoing significant changes, and among these changes is the creation of a standard for the accounting of small and medium enterprises, in line with international accounting standards for companies of this size. This rule arose from the development of a pronouncement by the Accounting Pronouncements Committee – CPC, which subsequently was approved by the Federal Accounting Council - CFC through specific resolutions. The present study aimed to analyze trends of accounting professionals and business managers concerning the adoption of Technical Pronouncement emitted by Accounting Pronouncements Committee for Small and Medium Enterprises. Considering the level of complexity of the operations performed by companies of this size, the lack of oversight by specific entities and the question of enforcement of these pronouncements, it was used the game theory to determine possible strategies adopted by the accountants and business managers regarding to the effective adoption of pronouncement for SMEs. The study was characterized as a descriptive research, using bibliographical and field research. With the use of surveys sought to identify the perceptions of accounting professionals regarding the adoption of the pronouncement. It was found that this statement constitutes a valid legal standard, endowed with legal effectiveness and technical efficiency, but lacking social effectiveness, due to the low level of efforts for its adoption, both by accounting professionals and by firms.

  7. Standard test methods for chemical and spectrochemical analysis of nuclear-Grade silver-indium-cadmium alloys

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1990-01-01

    1.1 These test methods cover procedures for the chemical and spectrochemical analysis of nuclear grade silver-indium-cadmium (Ag-In-Cd) alloys to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Silver, Indium, and Cadmium by a Titration Method 7-15 Trace Impurities by Carrier-Distillation Spectro- chemical Method 16-22 1.3 The values stated in SI units are to be regarded as the standard. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. For specific hazard and precautionary statements, see Section 5 and Practices E50. 7.1 This test method is applicable to the determination of silver, indium, and cadmium in alloys of approximately 80 % silver, 15 % indium, and 5 % cadmium used in nuclear reactor control r...

  8. CAE meteorological database for the PC CREAM program. Atmospheric dilution factor in different points of the CAE (Centro Atomico Ezeiza) and of the argentine nuclear power plants

    International Nuclear Information System (INIS)

    Amado, Valeria A.

    2007-01-01

    In the first part of this work, the EZEIZA.MET file, with the meteorological database of the surroundings of the Ezeiza Atomic Center, is prepared and incorporated into the library of the PC CREAM program. This program was developed by the National Radiological Protection Board and the European Union. Information provided by the National Meteorological Service was used, corresponding to the Ezeiza Meteorological Station during the period 1996-2005. In the second part, a methodology to estimate the atmospheric dilution factor at a point using the PLUME module of the PC CREAM, is presented. The developed methodology was used to estimate the dilution factor at points close to the Ezeiza Atomic Center and nuclear power plants Atucha I and Embalse. The developed methodology was used to estimate the dilution factor at points close to the Ezeiza Atomic Center and nuclear power plants Atucha I and Embalse. In the first case the file with the generated meteorological database is used, whereas for the nuclear power plants the already existing ATUCHALO.MET and EMBALSE.MET files are used. The dilution factors obtained are compared with those obtained in previous work. The proposed methodology is a useful tool to estimate the dilution factors in a simple and systematic way, and simultaneously allows the update of the meteorological information used in the estimations. (author) [es

  9. The IAEAs incident and emergency centre: the global focal point for nuclear and radiological emergency preparedness and response

    International Nuclear Information System (INIS)

    Buglova, E.

    2016-01-01

    The continuous use of nuclear power to generate electricity and the continued threat of radioactive materials being used for nefarious reasons reminds us of the importance to stay prepared to respond to nuclear or radiological emergencies. Stringent nuclear safety and nuclear security requirements, the training of personnel, operational checks and legal frameworks cannot always prevent radiation-related emergencies. Though these events can range in severity, each has the potential to cause harm to the public, employees, patients, property and the environment. Until the Chernobyl nuclear accident in 1986, there was no international information exchange system. Immediately following that accident, the international community negotiated the so-called Emergency Conventions to ensure that the country suffering an accident with an international transboundary release of radioactive material would issue timely, authenticated information, while the States that could field technical support, would do so in a coordinated fashion. The Conventions also place specific legal obligations on the International Atomic energy Agency (IAEA) with regard to emergency preparedness and response. (Author)

  10. The IAEAs incident and emergency centre: the global focal point for nuclear and radiological emergency preparedness and response

    Energy Technology Data Exchange (ETDEWEB)

    Buglova, E.

    2016-08-01

    The continuous use of nuclear power to generate electricity and the continued threat of radioactive materials being used for nefarious reasons reminds us of the importance to stay prepared to respond to nuclear or radiological emergencies. Stringent nuclear safety and nuclear security requirements, the training of personnel, operational checks and legal frameworks cannot always prevent radiation-related emergencies. Though these events can range in severity, each has the potential to cause harm to the public, employees, patients, property and the environment. Until the Chernobyl nuclear accident in 1986, there was no international information exchange system. Immediately following that accident, the international community negotiated the so-called Emergency Conventions to ensure that the country suffering an accident with an international transboundary release of radioactive material would issue timely, authenticated information, while the States that could field technical support, would do so in a coordinated fashion. The Conventions also place specific legal obligations on the International Atomic energy Agency (IAEA) with regard to emergency preparedness and response. (Author)

  11. U Y 105 standard use of non sealed radioactive sources in nuclear medicine: approve for Industry energy and Mining Ministry 28/6/2002 Resolution

    International Nuclear Information System (INIS)

    2002-01-01

    Establish minimal requirements radiological safety for use non sealed radioactive sources in nuclear medicine.The present standard is used in operation or nuclear medicine practices using non sealed radioactive sources with diagnostic and therapeutic purposes in vivo and in vitro

  12. Standard specification for wrought zirconium and zirconium alloy seamless and welded tubes for nuclear service

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    Specifications are described for three grades of seamless and welded wrought zirconium and zirconium-alloy tubes for nuclear applications. These grades are designated as reactor grade zirconium R-1, and zirconium-tin alloys RA-1 and RA-2. Basis of purchase, manufacture, inspection, and packaging and marketing are specified. Chemical requirements and mechanical properties specifications are tabulated. Permissible variations in diameter, wall thickness, and ovality measured at any location on the tube are also tabulated

  13. Quality assurance of the French nuclear market - IAEA code and standardization

    International Nuclear Information System (INIS)

    Pavaux, F.

    1980-06-01

    The fact that Quality Assurance was imported from abroad and our reticence to reach agreement on single and accurate texts explain, if not excuse, the abundance of reference requirements existing on the French nuclear market with respect to Quality Assurance Programmes. But all is not lost, since the IAEA Good Practice Code is perhaps the solution that, in a few years time, will enable all French industrialists to work and be assessed by their customers, according to the same reference text [fr

  14. A nuclear fuel cycle operator's point of view on the applicability of the new ICRP recommendations to aspects of nuclear safety

    International Nuclear Information System (INIS)

    Sheppard, G.T.; Berry, R.J.; Henry, P.

    1991-01-01

    The first section of the Paper deals with the ICRP recommendations, and makes general comments. The next two sections deal with the implications of the new recommendations on design and operation of Nuclear Fuel Cycle Facilities. The following conclusions are drawn: - The reductions in annual dose limits proposed in the new ICRP recommendations can be accommodated in the majority of modern nuclear fuel cycle facilities, and are less stringent than current design objectives. There are significant national differences between the UK and France in ability to accommodate the new ICRP recommendations on risk limitation from potential exposure situations (accidents). The French view is that it is not realistic to base the safety of industrial installations on risk limits expressed in terms of probability of deaths, while UK experience largely gained in the chemical and other industries, as well as in the nuclear industry, suggests that nuclear fuel cycle facilities will have no difficulty in demonstrating compliance with risk limits currently proposed by ICRP. It is unlikely that underground uranium mining operations, however sophisticated, will be able to operate within the new ICRP recommended dose limits

  15. Study on the standard establishment for the integrity assessment of nuclear fuel cladding Materials

    Energy Technology Data Exchange (ETDEWEB)

    Kang, S. S.; Kim, S. H.; Jung, Y. K.; Yang, C. Y.; Kim, I. G.; Choi, Y. H.; Kim, H. J.; Kim, M. W.; Rho, B. H. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2007-02-15

    Fuel cladding material plays important role as a primary structure under the high temperature, high pressure and neutron environment of nuclear power plant. According to this environment, cladding material can be experienced several type aging phenomena including the neutron irradiation embrittlement. On the other hand, although the early nuclear power plant was designed to fitting into the 40MWd/KgU burn-up, the currently power plant intends to go to the high burn-up range. In this case, the safety criteria which was established at low burn-up needs to conform the applicability at the high burn-up. In this study, the safety criteria of fuel cladding material was reviewed to assess the cladding material integrity, and the material characteristics of cladding were reviewed. The current LOCA criterial was also reviewed, and the basic study for re-establishment of LOCA criteria was performed. The time concept safety criteria was also discussed to prevent the breakaway oxidation. Through the this study, safety issues will be produced and be helpful for integrity insurance of nuclear fuel cladding material. This report is 2nd term report.

  16. Study on the Standard Establishment for the Integrity Assessment of Nuclear Fuel Cladding Materials

    Energy Technology Data Exchange (ETDEWEB)

    Kang, S-S; Kim, S-H; Jung, Y-K; Yang, C-Y; Kim, I-G; Choi, Y-H; Kim, H-J; Kim, M-W; Rho, B-H [KINS, Daejeon (Korea, Republic of)

    2008-02-15

    Fuel cladding material plays important role as a primary structure under the high temperature, high pressure and neutron environment of nuclear power plant. According to this environment, cladding material can be experienced several type aging phenomena including the neutron irradiation embrittlement. On the other hand, although the early nuclear power plant was designed to fitting into the 40MWd/KgU burn-up, the currently power plant intends to go to the high burn-up range. In this case, the safety criteria which was established at low burn-up needs to conform the applicability at the high burn-up. In this study, the safety criteria of fuel cladding material was reviewed to assess the cladding material integrity, and the material characteristics of cladding were reviewed. The current LOCA criterial was also reviewed, and the basic study for re-establishment of LOCA criteria was performed. The time concept safety criteria was also discussed to prevent the breakaway oxidation. Through the this study, safety issues will be produced and be helpful for integrity insurance of nuclear fuel cladding material. This report is the final report.

  17. Seismic design of nuclear power plants in Japan with consideration of standardization

    International Nuclear Information System (INIS)

    Watabe, M.; Tanaka, H.; Kato, M.; Tohdo, M.

    1981-01-01

    This paper presents the aseismic design approach and process for prototypes of the standard Light Water Reactor, which have been conducted in the committee of the Ministry of International Trade and Industry. (orig./HP)

  18. Near-term feasibility of nuclear reactors for seawater desalting. Coupling of standard condensing nuclear power stations to low-grade heat multieffect distillation plants

    International Nuclear Information System (INIS)

    Adar, J.; Manor, S.; Schaal, M.

    1977-01-01

    The paper describes the horizontal aluminium tube, multieffect distillation process developed by Israel Desalination Engineering Ltd., which is very suitable for the use of low-grade heat from standard condensing nuclear turbines operating at increased back-pressure. A special flash-chamber constitutes a positive barrier against any possible contamination being carried over by the steam exhausted from the turbine to the desalination plant. Flow sheets, heat and mass balances have been prepared for two standard sizes of NSSS and turbines, two back-pressures, and corresponding desalination plants. Only standard equipment is being used in the steam and electricity-producing plant. The desalination plant consists of 6 to 12 parallel double lines, each of them similar to a large prototype now being designed and which will be coupled to an old fossil-fuel power station. Total energy requirements of the desalination plant represent only 19 to 50% of the total water cost as against 75% for a single-purpose plant. Costs are based on actual bids for the power plant and actual estimates for the desalination prototype. The operation is designed to be flexible so that the power plant can be operated either in conjunction with the desalination plant, or as a single-purpose plant. (author)

  19. Validation of two point-of-care tests against standard lab measures of NO in saliva and in serum.

    Science.gov (United States)

    Modi, Ashwin; Morou-Bermudez, Evangelia; Vergara, Jose; Patel, Rakesh P; Nichols, Alexandria; Joshipura, Kaumudi

    2017-04-01

    Nitric oxide (NO) is an endogenous signaling molecule, which plays important roles in cardiometabolic health. A significant source of NO is dietary nitrate (NO 3 ), which is initially metabolized by oral bacteria into nitrite (NO 2 - ) and is subsequently converted into NO once digested in the acidic gastric environment. Inexpensive non-invasive tests for measuring nitrite from saliva have been developed as a means for individuals to monitor their NO bioavailability. However, few studies exist in the literature validating and comparing these products with standard lab assays. The objective of this study was to validate two commonly used commercial strips: Nitric Oxide Test Strips (Berkeley Test) and Nitric Oxide Indicator Strips (Neogenesis) against standard lab measures for saliva and serum nitrite/nitrate. A stratified random sample of 20 non-smoking, overweight or obese participants between 40 to 65 years of age, were selected for this study from the baseline data of the San Juan Overweight Adults Longitudinal Study (SOALS). There was a significant correlation between the measures from the two nitrite-detecting-strips after controlling for the stratification variables (metabolic syndrome, and mouthwash use) (r = 0.75). Measurements from both strips correlated significantly with salivary nitrite levels (r = 0.76 for Berkeley strips; r = 0.59 for Neogenesis). Neither of the strips had a significant correlation with the levels of saliva nitrate, serum nitrite and serum nitrate. In conclusion, commercially available Berkeley and Neogenesis strips provide a reasonable surrogate for salivary, but not for systemic nitrite levels. Copyright © 2017 Elsevier Inc. All rights reserved.

  20. 75 FR 4426 - Florida Power and Light Company; Turkey Point Nuclear Generating Units 3 and 4; Environmental...

    Science.gov (United States)

    2010-01-27

    ... proposed action does not result in changes to land use or water use, or result in changes to the quality or... the human environment. Accordingly, the NRC has determined not to prepare an environmental impact... Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering the issuance of an Exemption...

  1. Development of a standard methodology for optimizing remote visual display for nuclear maintenance tasks

    Science.gov (United States)

    Clarke, M. M.; Garin, J.; Prestonanderson, A.

    A fuel recycle facility being designed at Oak Ridge National Laboratory involves the Remotex concept: advanced servo-controlled master/slave manipulators, with remote television viewing, will totally replace direct human contact with the radioactive environment. The design of optimal viewing conditions is a critical component of the overall man/machine system. A methodology was developed for optimizing remote visual displays for nuclear maintenance tasks. The usefulness of this approach was demonstrated by preliminary specification of optimal closed circuit TV systems for such tasks.

  2. Development, validation and application of multi-point kinetics model in RELAP5 for analysis of asymmetric nuclear transients

    Energy Technology Data Exchange (ETDEWEB)

    Pradhan, Santosh K., E-mail: santosh@aerb.gov.in [Nuclear Safety Analysis Division, Atomic Energy Regulatory Board, Mumbai 400094 (India); Obaidurrahman, K. [Nuclear Safety Analysis Division, Atomic Energy Regulatory Board, Mumbai 400094 (India); Iyer, Kannan N. [Department of Mechanical Engineering, IIT Bombay, Mumbai 400076 (India); Gaikwad, Avinash J. [Nuclear Safety Analysis Division, Atomic Energy Regulatory Board, Mumbai 400094 (India)

    2016-04-15

    Highlights: • A multi-point kinetics model is developed for RELAP5 system thermal hydraulics code. • Model is validated against extensive 3D kinetics code. • RELAP5 multi-point kinetics formulation is used to investigate critical break for LOCA in PHWR. - Abstract: Point kinetics approach in system code RELAP5 limits its use for many of the reactivity induced transients, which involve asymmetric core behaviour. Development of fully coupled 3D core kinetics code with system thermal-hydraulics is the ultimate requirement in this regard; however coupling and validation of 3D kinetics module with system code is cumbersome and it also requires access to source code. An intermediate approach with multi-point kinetics is appropriate and relatively easy to implement for analysis of several asymmetric transients for large cores. Multi-point kinetics formulation is based on dividing the entire core into several regions and solving ODEs describing kinetics in each region. These regions are interconnected by spatial coupling coefficients which are estimated from diffusion theory approximation. This model offers an advantage that associated ordinary differential equations (ODEs) governing multi-point kinetics formulation can be solved using numerical methods to the desired level of accuracy and thus allows formulation based on user defined control variables, i.e., without disturbing the source code and hence also avoiding associated coupling issues. Euler's method has been used in the present formulation to solve several coupled ODEs internally at each time step. The results have been verified against inbuilt point-kinetics models of RELAP5 and validated against 3D kinetics code TRIKIN. The model was used to identify the critical break in RIH of a typical large PHWR core. The neutronic asymmetry produced in the core due to the system induced transient was effectively handled by the multi-point kinetics model overcoming the limitation of in-built point kinetics model

  3. Joint American Nuclear Society and Health Physics Society Conference: Applicability of Radiation Response Models to Low Dose Protection Standards.

    Science.gov (United States)

    Glines, Wayne M; Markham, Anna

    2018-05-01

    Seventy-five years after the Hanford Site was initially created as the primary plutonium production site for atomic weapons development under the Manhattan Project, the American Nuclear Society and the Health Physics Society are sponsoring a conference from 30 September through 3 October 2018, in Pasco, Washington, titled "Applicability of Radiation Response Models to Low Dose Protection Standards." The goal of this conference is to use current scientific data to update the approach to regulating low-level radiation doses; i.e., to answer a quintessential question of radiation protection-how to best develop radiation protection standards that protect human populations against detrimental effects while allowing the beneficial uses of radiation and radioactive materials. Previous conferences (e.g., "Wingspread Conference," "Arlie Conference") have attempted to address this question; but now, almost 20 y later, the key issues, goals, conclusions, and recommendations of those two conferences remain and are as relevant as they were then. Despite the best efforts of the conference participants and increased knowledge and understanding of the science underlying radiation effects in human populations, the bases of current radiation protection standards have evolved little. This 2018 conference seeks to provide a basis and path forward for evolving radiation protection standards to be more reflective of current knowledge and understanding of low dose response models.

  4. Nuclear power plants - Instrumentation and control systems important for safety - Classification (International Electrotechnical Commission Standard Publication 1226:1993)

    International Nuclear Information System (INIS)

    Stefanik, J.

    1996-01-01

    This international standard established a method of classification of the information and command functions for nuclear power plants, and the I and C and equipment that provide those functions, into categories that designate the importance for safety of the functions, and the associated systems and equipment. The resulting classification then determines relevant design criteria. The design criteria are the measures of quality by which the adequacy of each functions, and the associated systems and equipment in relation to its importance to plant safety is ensured. In this standard, the criteria are those of functionality, reliability, performance, environmental durability and quality assurance. This standard is applicable to all the information and command functions, and the instrumentation and control systems and equipment that provide those functions. The functions, systems and equipment under consideration provide automated protection, closed or open loop control, and information to the operating staff. They keep the NPP conditions inside the safe operating envelope and provide automatic actions, or enable manual actions, that mitigate accidents or prevent or minimize radioactive releases to the site or wider environment. The functions, and the associated systems and equipment that fulfill these roles safeguard the health and safety of the NPP operators and the public. This standard complements, and does not replace or supersede, the Safety Guides and Codes of Practice published by the International Atomic Energy Agency

  5. Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and the initial schedule for evaluation of materials. 1.2 This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum fast neutron fluence (E > 1 MeV) at the end of license (EOL) exceeds 1 × 1021 neutrons/m2 (1 × 1017 n/cm2) at the inside surface of the reactor vessel. 1.3 This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels. 1.4 This practice does not provide specific procedures for monitoring the radiation induced cha...

  6. CSER-98-002: Criticality analysis for the storage of special nuclear material sources and standards in the WRAP Facility

    Energy Technology Data Exchange (ETDEWEB)

    Goldberg, H.J.

    1998-06-22

    The Waste Receiving and Processing (WRAP) Facility will store uranium and transuranic (TRU) sources and standards for certification that WRAP meets the requirements of the Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP). In addition, WRAP must meet internal requirements for testing and validation of measuring instruments for nondestructive assay (NDA). In order to be certified for WIPP, WRAP will participate in the NDA Performance Demonstration Program (PDP). This program is a blind test of the NDA capabilities for TRU waste. It is intended to ensure that the NDA capabilities of this facility satisfy the requirements of the quality assurance program plan for the WIPP. The PDP standards have been provided by the Los Alamos National Laboratory (LANL) for this program. These standards will be used in the WRAP facility. To internally check the accuracy and sensitivity of the NDA instruments, a further set of sources and standards will also be used by the facility. Each sealed source or standard will be referred to herein as a unit. Various combinations of these units will be placed in test drums and/or boxes which will be subject to their own limits until unloaded. There will be two sealed test drums with five grams of weapons grade plutonium loaded in them. These drums will be appropriately marked and will be subject to the unit limits rather than the drum limits. This analysis shows that the storage and use of special nuclear material sources and standards within the limited control facility of WRAP (Rooms 101 and 104) is safe from a criticality standpoint. With the form, geometry, and masses involved with this evaluation, a criticality is not possible. The limits given in Section 2 should be imposed on facility operations.

  7. Standard and prototype tests of hotwater- and steam-valves for nuclear power stations

    International Nuclear Information System (INIS)

    Dernbach, B.

    1977-11-01

    More than 150 standard and prototype valves have been tested in a special valve test facility (VTF) for reactor valve tests under working conditions. Approximately 85% of the valves performed well for the given task, in some cases however only after numerous improvements jointly done with the manufactures; 15% turned out to be unserviceable. (orig.) [de

  8. Standard for design criteria for decommissioning of nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Graham, H.B.

    1976-01-01

    This paper was developed by the ANSI Standards Committee N46. Deactivation or shutdown followed by continued operation on the same site does not constitute decommissioning. It is felt that abandonment with entombment of the highly radioactive parts of the plant is the only economically feasible alternative

  9. Standard specification for nuclear-grade aluminum oxide-boron carbide composite pellets

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2005-01-01

    1.1 This specification applies to pellets composed of mixtures of aluminum oxide and boron carbide that may be ultimately used in a reactor core, for example, in neutron absorber rods. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

  10. Standardization of administered activities in pediatric nuclear medicine: a report of the first nuclear medicine global initiative project, part 1-statement of the issue and a review of available resources.

    Science.gov (United States)

    Fahey, Frederic H; Bom, Henry Hee-Seong; Chiti, Arturo; Choi, Yun Young; Huang, Gang; Lassmann, Michael; Laurin, Norman; Mut, Fernando; Nuñez-Miller, Rodolfo; O'Keeffe, Darin; Pradhan, Prasanta; Scott, Andrew M; Song, Shaoli; Soni, Nischal; Uchiyama, Mayuki; Vargas, Luis

    2015-04-01

    The Nuclear Medicine Global Initiative (NMGI) was formed in 2012 and consists of 13 international organizations with direct involvement in nuclear medicine. The underlying objectives of the NMGI were to promote human health by advancing the field of nuclear medicine and molecular imaging, encourage global collaboration in education, and harmonize procedure guidelines and other policies that ultimately lead to improvements in quality and safety in the field throughout the world. For its first project, the NMGI decided to consider the issues involved in the standardization of administered activities in pediatric nuclear medicine. This article presents part 1 of the final report of this initial project of the NMGI. It provides a review of the value of pediatric nuclear medicine, the current understanding of the carcinogenic risk of radiation as it pertains to the administration of radiopharmaceuticals in children, and the application of dosimetric models in children. A listing of pertinent educational and reference resources available in print and online is also provided. The forthcoming part 2 report will discuss current standards for administered activities in children and adolescents that have been developed by various organizations and an evaluation of the current practice of pediatric nuclear medicine specifically with regard to administered activities as determined by an international survey of nuclear medicine clinics and centers. Lastly, the part 2 report will recommend a path forward toward global standardization of the administration of radiopharmaceuticals in children. © 2015 by the Society of Nuclear Medicine and Molecular Imaging, Inc.

  11. Participation of the national industry within a nuclear power plant program by technology transfer from the point of view of the main contractor

    International Nuclear Information System (INIS)

    Kopp, H.

    1986-04-01

    The broad scope of components needed in a nuclear power plant with various technical requirements offer a big opportunity for the participation of local industries in the construction of such plants. Depending on the existing capability of the industrial enterprises, the scope of national participation can be increased by technology transfer on all technical areas to be applied for the construction of NPPs. Such technology requires as basis a nuclear program of the country determined and supported by the government and the utilities. This program has to be defined as realistic as even possible adjoined to the future energy demand of the country. Furthermore the available capability, existing qualifications and equipment of the national industry have to be considered. On the basis of these fundamental requirements a tailormade technology transfer program has to be elaborated in close cooperation with an experienced main contractor of the plant and his partners for such technology transfer and should be established afterwards. This program has to consider not only the goal to achieve finally the independent production of components and equipment for NPPs or the construction of complete power plant units itself, but also the economic benefit of such a program for the country. The costs of technology transfer and the necessary investment of the national industry required for the manufacture of nuclear components have to be thoroughly investigated, based on the expected scope of products to be manufactured for the nuclear power plants according to the nuclear program. Furthermore the application of the technology transferred for other components e.g. for conventional power stations, mineral-oil or chemical industrial plants has to be considered. By a tailormade nuclear technology transfer program, executed by qualified and experienced partners not only the quality of the products of the national industry for NPPs will be improved, but also the general standard regarding

  12. "Delirium Day": a nationwide point prevalence study of delirium in older hospitalized patients using an easy standardized diagnostic tool.

    Science.gov (United States)

    Bellelli, Giuseppe; Morandi, Alessandro; Di Santo, Simona G; Mazzone, Andrea; Cherubini, Antonio; Mossello, Enrico; Bo, Mario; Bianchetti, Angelo; Rozzini, Renzo; Zanetti, Ermellina; Musicco, Massimo; Ferrari, Alberto; Ferrara, Nicola; Trabucchi, Marco

    2016-07-18

    To date, delirium prevalence in adult acute hospital populations has been estimated generally from pooled findings of single-center studies and/or among specific patient populations. Furthermore, the number of participants in these studies has not exceeded a few hundred. To overcome these limitations, we have determined, in a multicenter study, the prevalence of delirium over a single day among a large population of patients admitted to acute and rehabilitation hospital wards in Italy. This is a point prevalence study (called "Delirium Day") including 1867 older patients (aged 65 years or more) across 108 acute and 12 rehabilitation wards in Italian hospitals. Delirium was assessed on the same day in all patients using the 4AT, a validated and briefly administered tool which does not require training. We also collected data regarding motoric subtypes of delirium, functional and nutritional status, dementia, comorbidity, medications, feeding tubes, peripheral venous and urinary catheters, and physical restraints. The mean sample age was 82.0 ± 7.5 years (58 % female). Overall, 429 patients (22.9 %) had delirium. Hypoactive was the commonest subtype (132/344 patients, 38.5 %), followed by mixed, hyperactive, and nonmotoric delirium. The prevalence was highest in Neurology (28.5 %) and Geriatrics (24.7 %), lowest in Rehabilitation (14.0 %), and intermediate in Orthopedic (20.6 %) and Internal Medicine wards (21.4 %). In a multivariable logistic regression, age (odds ratio [OR] 1.03, 95 % confidence interval [CI] 1.01-1.05), Activities of Daily Living dependence (OR 1.19, 95 % CI 1.12-1.27), dementia (OR 3.25, 95 % CI 2.41-4.38), malnutrition (OR 2.01, 95 % CI 1.29-3.14), and use of antipsychotics (OR 2.03, 95 % CI 1.45-2.82), feeding tubes (OR 2.51, 95 % CI 1.11-5.66), peripheral venous catheters (OR 1.41, 95 % CI 1.06-1.87), urinary catheters (OR 1.73, 95 % CI 1.30-2.29), and physical restraints (OR 1.84, 95 % CI 1.40-2.40) were associated with delirium. Admission

  13. Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide discusses test procedures that can be used in conjunction with, but not as alternatives to, those required by Practices E185 and E2215 for the surveillance of nuclear reactor vessels. The supplemental mechanical property tests outlined permit the acquisition of additional information on radiation-induced changes in fracture toughness, notch ductility, and yield strength properties of the reactor vessel steels. 1.2 This guide provides recommendations for the preparation of test specimens for irradiation, and identifies special precautions and requirements for reactor surveillance operations and postirradiation test planning. Guidance on data reduction and computational procedures is also given. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition.

  14. Fabrication of advanced targets for laser driven nuclear fusion reactions through standard microelectronics technology approaches.

    Czech Academy of Sciences Publication Activity Database

    Picciotto, A.; Crivellari, M.; Bellutti, P.; Barozzi, M.; Kucharik, M.; Krása, Josef; Swidlovsky, A.; Malinowska, A.; Velyhan, Andriy; Ullschmied, Jiří; Margarone, Daniele

    2017-01-01

    Roč. 12, October (2017), č. článku P10001. ISSN 1748-0221 Grant - others:OP VK 2 LaserGen(XE) CZ.1.07/2.3.00/20.0087; LaserZdroj (OP VK 3)(XE) CZ.1.07/2.3.00/20.0279 Institutional support: RVO:61389021 ; RVO:68378271 Keywords : Nuclear instruments and methods for hot plasma diagnostics * Plasma generation (laserproduced, RF, x ray-produced) * Plasma diagnostics - charged-particle spectroscopy Subject RIV: BL - Plasma and Gas Discharge Physics; BL - Plasma and Gas Discharge Physics (FZU-D) OBOR OECD: 2.11 Other engineering and technologies; 2.11 Other engineering and technologies (FZU-D) Impact factor: 1.220, year: 2016 http://iopscience.iop.org/article/10.1088/1748-0221/12/10/P10001/meta

  15. Standard guide for characterization of spent nuclear fuel in support of geologic repository disposal

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This guide provides guidance for the types and extent of testing that would be involved in characterizing the physical and chemical nature of spent nuclear fuel (SNF) in support of its interim storage, transport, and disposal in a geologic repository. This guide applies primarily to commercial light water reactor (LWR) spent fuel and spent fuel from weapons production, although the individual tests/analyses may be used as applicable to other spent fuels such as those from research and test reactors. The testing is designed to provide information that supports the design, safety analysis, and performance assessment of a geologic repository for the ultimate disposal of the SNF. 1.2 The testing described includes characterization of such physical attributes as physical appearance, weight, density, shape/geometry, degree, and type of SNF cladding damage. The testing described also includes the measurement/examination of such chemical attributes as radionuclide content, microstructure, and corrosion product c...

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

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2006-01-01

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

  17. Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2003-01-01

    1.1 This guide covers the general procedures to be considered for conducting an in-service thermal anneal of a light-water moderated nuclear reactor vessel and demonstrating the effectiveness of the procedure. The purpose of this in-service annealing (heat treatment) is to improve the mechanical properties, especially fracture toughness, of the reactor vessel materials previously degraded by neutron embrittlement. The improvement in mechanical properties generally is assessed using Charpy V-notch impact test results, or alternatively, fracture toughness test results or inferred toughness property changes from tensile, hardness, indentation, or other miniature specimen testing (1). 1.2 This guide is designed to accommodate the variable response of reactor-vessel materials in post-irradiation annealing at various temperatures and different time periods. Certain inherent limiting factors must be considered in developing an annealing procedure. These factors include system-design limitations; physical constrain...

  18. Development of a standard methodology for optimizing remote visual display for nuclear-maintenance tasks

    International Nuclear Information System (INIS)

    Clarke, M.M.; Garin, J.; Preston-Anderson, A.

    1981-01-01

    The aim of the present study is to develop a methodology for optimizing remote viewing systems for a fuel recycle facility (HEF) being designed at Oak Ridge National Laboratory (ORNL). An important feature of this design involves the Remotex concept: advanced servo-controlled master/slave manipulators, with remote television viewing, will totally replace direct human contact with the radioactive environment. Therefore, the design of optimal viewing conditions is a critical component of the overall man/machine system. A methodology has been developed for optimizing remote visual displays for nuclear maintenance tasks. The usefulness of this approach has been demonstrated by preliminary specification of optimal closed circuit TV systems for such tasks

  19. Standard test methods for chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade boron carbide

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2004-01-01

    1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade boron carbide powder and pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Total Carbon by Combustion and Gravimetry 7-17 Total Boron by Titrimetry 18-28 Isotopic Composition by Mass Spectrometry 29-38 Chloride and Fluoride Separation by Pyrohydrolysis 39-45 Chloride by Constant-Current Coulometry 46-54 Fluoride by Ion-Selective Electrode 55-63 Water by Constant-Voltage Coulometry 64-72 Impurities by Spectrochemical Analysis 73-81 Soluble Boron by Titrimetry 82-95 Soluble Carbon by a Manometric Measurement 96-105 Metallic Impurities by a Direct Reader Spectrometric Method 106-114

  20. Standard Operation Procedure (SOP) on Planting and Curing of Stevia in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Norellia Bahari; Norazlina Noordin; Peng, C.S.

    2015-01-01

    Mutation breeding on stevia study was conducted at the Malaysian Nuclear Agency began in 2012 through the projects under auspices of Science Funs and MOSTI. This research involves the irradiation og gamma rays for acute and chronic tissue culture of stevia. The resulting plant from this tissue cultures process should be planted in a nursery fro the propagation of seedlings for the work of mutant screening potential. For this purpose, the SOP for planting, care and management of stevia has ben developed to ensure that this plant can grow in abundance, disease free and quality. This paper will discuss the SOP including acclimatization techniques of tissue culture plant lets, seedlings and planting in Bio Design Facility, fertilization using fertilizers and planting of trees in the plot for the purpose of potentially screening mutant breeding. (author)

  1. ENDF-UTILITY-CODES, codes to check and standardize data in the Evaluated Nuclear Data File (ENDF)

    International Nuclear Information System (INIS)

    Dunford, Charles L.

    2007-01-01

    1 - Description of program or function: The ENDF Utility Codes include 9 codes to check and standardize data in the Evaluated Nuclear Data File (ENDF). Four programs of this release, GETMAT, LISTEF, PLOTEF and SETMDC are no more maintained since release 6.13. The suite of ENDF utility codes includes: - CHECKR (version 7.01) is a program for checking that an evaluated data file conforms to the ENDF format. - FIZCON (version 7.02) is a program for checking that an evaluated data file has valid data and conforms to recommended procedures. - GETMAT (version 6.13) is designed to retrieve one or more materials from an ENDF formatted data file. The output will contain only the selected materials. - INTER (version 7.01) calculates thermal cross sections, g-factors, resonance integrals, fission spectrum averaged cross sections and 14.0 MeV (or other energy) cross sections for major reactions in an ENDF-6 or ENDF-5 format data file. - LISTEF (version 6.13) is designed to produce summary and annotated listings of a data file in either ENDF-6 or ENDF-5 format. - PLOTEF (version 6.13) is designed to produce graphical displays of a data file in either ENDF-5 or ENDF-6 format. The form of graphical output depends on the graphical devices available at the installation where this code will be used. - PSYCHE (version 7.02) is a program for checking the physics content of an evaluated data file. It can recognise the difference between ENDF-5 or ENDF-6 formats and performs its tests accordingly. - SETMDC (version 6.13) is a utility program that converts the source decks of programs to different computers (DOS, UNIX, LINUX, VMS, Windows). - STANEF (version 7.01) performs bookkeeping operations on a data file containing one or more material evaluations in ENDF format. The version 7.02 of the ENDF Utility Codes corrects all bugs reported to NNDC as of April 1, 2005 and supersedes all previous releases. Three codes CHECKR, STANEF, and INTER were actually ported from the 7.01 release

  2. Standard test method for determination of impurities in nuclear grade uranium compounds by inductively coupled plasma mass spectrometry

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This test method covers the determination of 67 elements in uranium dioxide samples and nuclear grade uranium compounds and solutions without matrix separation by inductively coupled plasma mass spectrometry (ICP-MS). The elements are listed in Table 1. These elements can also be determined in uranyl nitrate hexahydrate (UNH), uranium hexafluoride (UF6), triuranium octoxide (U3O8) and uranium trioxide (UO3) if these compounds are treated and converted to the same uranium concentration solution. 1.2 The elements boron, sodium, silicon, phosphorus, potassium, calcium and iron can be determined using different techniques. The analyst's instrumentation will determine which procedure is chosen for the analysis. 1.3 The test method for technetium-99 is given in Annex A1. 1.4 The values stated in SI units are to be regarded as standard. 1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish ...

  3. 42 CFR Appendix F to Part 75 - Standards for Licensing Radiographers, Nuclear Medicine Technologists, and Radiation Therapy...

    Science.gov (United States)

    2010-10-01

    ... licensed as Radiographers, Nuclear Medicine Technologists, or Radiation Therapy Technologists. 2. Licenses... radiography, nuclear medicine technology, or radiation therapy technology. 2. Special eligibility to take the...-referenced examination in radiography, nuclear medicine technology, or radiation therapy technology shall be...

  4. Investigations on vegetation of Grikinishkes landscape standard in the Ignalina Nuclear Power Plant region

    International Nuclear Information System (INIS)

    Balevichiene, J.; Lazdauskaite, Z.; Matulevichiute, D.; Stankevichiute, J.

    1995-01-01

    The vegetation of Grikinishkes landscape standard was investigated in 1994 according to the methodics of the European integrated monitoring. After a common prospect of the territory the representative geobotanical profile of 2 km length and 200 m width was found out. There were described 10 associations (classified according to Zurich-Montpellier school principles) including 134 plant species. The site of an intensive monitoring was selected and background investigations carried out. The investigation data indicated, that the state of vegetation is only satisfactory. Anthropogenic changes coursed by sinantropisation, defoliation and pyrogenesis of flora were observed. (author). 7 refs., 3 tabs., 1 fig

  5. Standard test method for splitting tensile strength for brittle nuclear waste forms

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1989-01-01

    1.1 This test method is used to measure the static splitting tensile strength of cylindrical specimens of brittle nuclear waste forms. It provides splitting tensile-strength data that can be used to compare the strength of waste forms when tests are done on one size of specimen. 1.2 The test method is applicable to glass, ceramic, and concrete waste forms that are sufficiently homogeneous (Note 1) but not to coated-particle, metal-matrix, bituminous, or plastic waste forms, or concretes with large-scale heterogeneities. Cementitious waste forms with heterogeneities >1 to 2 mm and 5 mm can be tested using this procedure provided the specimen size is increased from the reference size of 12.7 mm diameter by 6 mm length, to 51 mm diameter by 100 mm length, as recommended in Test Method C 496 and Practice C 192. Note 1—Generally, the specimen structural or microstructural heterogeneities must be less than about one-tenth the diameter of the specimen. 1.3 This test method can be used as a quality control chec...

  6. Standard criteria for disposal of liquid radioactive wastes from nuclear power plants into surface waters (river systems)

    International Nuclear Information System (INIS)

    Pisarev, V.V.; Tsybizov, I.S.

    1976-01-01

    Radioactive products discharge into natural water streams results in the necessity to regulate nuclear power plant discharges to ensure radiation safety (RS) for population using a river and surrounding river territory. To ensure RS it is necessary to set scientific-founded standards of permissible discharge level of liquid radioactive wastes (LRW) from nuclear power plant assuring observance of hygienic requirements for surface water puring. Volume of permissible LRW discharge into river systems must be set both with provision for concrete physical-geographycal conditions, specficity of utilizing the river and river valley and social-economical peculiarities of crtical population groups. The value of permissible LRW discharge into river systems is determined by three criterion groups: radiological, ecological and hydrological ones. By means of radiological group the internal and external irradiation doses for the whole body and its separate organs are set and RS of population is determined. Ecological criteria include a number of parameters (coefficients of accumulation, distribution and transition) determining quantitative ratios between radioactive element contents in water and separate links of biological chains: soil/water, fish/water, vegetables/water and others. Hydrological criteria determine the degree of waste dilution in rivers, control radioactive contamination of flood-lands areas and in common with ecological criteria determine radionuclide contents in soil and food products. A method of determining average annual values of LRW dilution in river waters is presented [ru

  7. Testing the Standard Model and Fundamental Symmetries in Nuclear Physics with Lattice QCD and Effective Field Theory

    Energy Technology Data Exchange (ETDEWEB)

    Walker-Loud, Andre [College of William and Mary, Williamsburg, VA (United States)

    2016-10-14

    The research supported by this grant is aimed at probing the limits of the Standard Model through precision low-energy nuclear physics. The work of the PI (AWL) and additional personnel is to provide theory input needed for a number of potentially high-impact experiments, notably, hadronic parity violation, Dark Matter direct detection and searches for permanent electric dipole moments (EDMs) in nucleons and nuclei. In all these examples, a quantitative understanding of low-energy nuclear physics from the fundamental theory of strong interactions, Quantum Chromo-Dynamics (QCD), is necessary to interpret the experimental results. The main theoretical tools used and developed in this work are the numerical solution to QCD known as lattice QCD (LQCD) and Effective Field Theory (EFT). This grant is supporting a new research program for the PI, and as such, needed to be developed from the ground up. Therefore, the first fiscal year of this grant, 08/01/2014-07/31/2015, has been spent predominantly establishing this new research effort. Very good progress has been made, although, at this time, there are not many publications to show for the effort. After one year, the PI accepted a job at Lawrence Berkeley National Laboratory, so this final report covers just a single year of five years of the grant.

  8. Summary of Preliminary Criticality Analysis for Peach Bottom Fuel in the DOE Standardized Spent Nuclear Fuel Canister

    International Nuclear Information System (INIS)

    Henrikson, D.J.

    1999-01-01

    The Department of Energy's (DOE's) National Spent Nuclear Fuel Program is developing a standardized set of canisters for DOE spent nuclear fuel (SNF). These canisters will be used for DOE SNF handling, interim storage, transportation, and disposal in the national repository. Several fuels are being examined in conjunction with the DOE SNF canisters. This report summarizes the preliminary criticality safety analysis that addresses general fissile loading limits for Peach Bottom graphite fuel in the DOE SNF canister. The canister is considered both alone and inside the 5-HLW/DOE Long Spent Fuel Co-disposal Waste Package, and in intact and degraded conditions. Results are appropriate for a single DOE SNF canister. Specific facilities, equipment, canister internal structures, and scenarios for handling, storage, and transportation have not yet been defined and are not evaluated in this analysis. The analysis assumes that the DOE SNF canister is designed so that it maintains reasonable geometric integrity. Parameters important to the results are the canister outer diameter, inner diameter, and wall thickness. These parameters are assumed to have nominal dimensions of 45.7-cm (18.0-in.), 43.815-cm (17.25-in), and 0.953-cm (0.375-in.), respectively. Based on the analysis results, the recommended fissile loading for the DOE SNF canister is 13 Peach Bottom fuel elements if no internal steel is present, and 15 Peach Bottom fuel elements if credit is taken for internal steel

  9. The history of nuclear decommissioning: an historical perspective from the view point of the International Atomic Energy Agency

    International Nuclear Information System (INIS)

    Laraia, M.

    2008-01-01

    The first IAEA report on the decommissioning of nuclear facilities in 1975 concluded that: 'There are no insurmountable technical problems to decommissioning at any stage, but considerations with respect to policy, planning, timing., costs, waste disposal, safety criteria and regulatory aspects need further development'. Since then much work has been done and substantial progress has been made - to the extent that decommissioning is now considered to be a generally mature industry. However, even a mature industry has to keep pace with evolving safety and environmental regulatory requirements, technological, progress, and also with changes in political perceptions and expectations. In addition, there are still technical areas needing improvement, and the experience and know-how should be transferred to countries that are now facing 'first of a kind' decommissioning projects. Therefore the above challenge, as identified in 1975, remains generally valid. Only the emphasis is shifting, with rather less need for new developments and a growing demand for optimization, common approaches and effective sharing of experiences. In many industrialized countries, the total, dismantling of major facilities was initially viewed by the operators and the government decision makers as an opportunity to demonstrate to the public that the decommissioning of major nuclear facilities can be conducted in a safe and cost effective manner. Equally importantly. these decommissioning efforts also served to test and optimize decontamination and disassembly techniques and to create 'decommissioning market' including specialized suppliers and contractors. Over two decades of major decommissioning activity, technology has advanced considerably and has benefited from parallel development in other industrial fields such as electronics, robotics and computing. New decommissioning techniques have emerged and are ready to face the challenges of the forthcoming years, when a number of large commercial

  10. Geologic disposal of spent nuclear fuel and nuclear waste: Ethical and technical bases for standards and criteria to protect public health

    International Nuclear Information System (INIS)

    Pigford, T.H.

    1999-01-01

    The proposed geologic repositories being designed in the US and in other countries that have nuclear power plants need well-defined goals and criteria to protect public health. The criteria must be stringent enough to build confidence in the adequacy of public health protection in the face of legal and political challenges. Yet, there are emerging pressures for relaxation of traditional approaches to protect public health when applied to buried radioactive waste. To build acceptance by the scientific community and the public, both the benefits and consequences of proposed relaxed standards must be dealt with openly and understandably. Arguments over safety standards center on six key issues. (1) For how long must public health protection be assured? Should protection be based on calculated radiation doses to people living for many tens of thousands of years in the future, until peak values of calculated radiation have appeared, or should the protection period be limited to a few thousand years? (2) Whom to protect? Should protection be based on protecting the critical group of future people who unknowingly eat food and drink water contaminated by released radioactivity or should it be based on limiting the average exposure, averaged over all persons projected to live within 'the vicinity' of the repository site? (3) How much radiation exposure should be allowed? Should future people be protected to the same level of radiation exposure as now required for licensed nuclear facilities, or should greater exposures be allowed because future people might be better protected by medical breakthroughs or by their taking remedial action to detect and clean up radioactivity that reaches the environment? (4) Can future people be excluded from using contaminated water drawn from near the site? Should protection of future people be based on doses calculated for ground water extracted from present farming wells, where distance and dilution resulted in lower calculated contaminant

  11. Estimation of the Fracture Resistance Curve for the Nuclear Piping Using the Standard Compact Tension Specimen

    International Nuclear Information System (INIS)

    Hur, Yong; Park, Hong Sun; Koo, Jae Mean; Seok, Chang Sung; Park, Jae Sil

    2009-01-01

    The estimation method of the fracture resistance curve for the pipe specimen was proposed using the load ratio method for the standard specimen. For this, the calculation method of the load - CMOD curve for the pipe specimen with the common format equation(CFE) was proposed by using data of the CT specimen. The proposed method agreed well with experimental data. The J-integral value and the crack extension were calculated from the estimated load - CMOD data. The fracture resistance curve was estimated from the calculated J-integral and the crack extension. From these results, it have been seen that the proposed method is reliable to estimate the J-R curve of the pipe specimen

  12. Estimation of the Fracture Resistance Curve for the Nuclear Piping Using the Standard Compact Tension Specimen

    Energy Technology Data Exchange (ETDEWEB)

    Hur, Yong; Park, Hong Sun; Koo, Jae Mean; Seok, Chang Sung [Sungkyunkwan University, Suwon (Korea, Republic of); Park, Jae Sil [Samsung Electronics Co., Suwon (Korea, Republic of)

    2009-09-15

    The estimation method of the fracture resistance curve for the pipe specimen was proposed using the load ratio method for the standard specimen. For this, the calculation method of the load - CMOD curve for the pipe specimen with the common format equation(CFE) was proposed by using data of the CT specimen. The proposed method agreed well with experimental data. The J-integral value and the crack extension were calculated from the estimated load - CMOD data. The fracture resistance curve was estimated from the calculated J-integral and the crack extension. From these results, it have been seen that the proposed method is reliable to estimate the J-R curve of the pipe specimen.

  13. Search for non Standard Model physics in nuclear-$\\beta$ decay with the WITCH experiment

    CERN Document Server

    Coeck, Sam

    In this work the WITCH experiment, which primarily aims for precision measurements of the beta-neutrino-angular correlation coefficient, is presented in detail. First a theoretical description of the beta-decay process is presented and it was shown how measurements of correlation coefficients can reveal the exact nature of the weak interaction. Although many experiments have already been conducted in this field, there is still considerable room for additional phenomena that are not included in the Standard Model. At WITCH the beta-neutrino-angular correlation coefficient will be obtained from precision measurements of the energy spectrum of the nuclei that recoil after beta-decay, thus avoiding the need to observe the neutrino. To enable a measurement of the recoiling ions, the setup uses a combination of two electromagnetic Penning traps and a retardation spectrometer. This allows one to construct the scattering free radioactive source that is needed as the recoiling ions have only a very small kinetic energ...

  14. Comparison of single point normalized and modified Gate's method for measurement of glomerular filtration rate by nuclear medicine

    International Nuclear Information System (INIS)

    Fonseca, L.M.B. da; Fonseca, N.M.; Martins, E.; Pereira, E.

    1992-01-01

    Glomerular filtration rate was measured in 22 patients (mean age 30 years) using a noninvasive modified Gates method and the results were compared to the one point normalized technique. The values obtained were 74-11.7 and 82-11.09 ml/min., respectively. The advantages of the method are its reliability, easy adaptation to small laboratories and the avoidance of blood and urine sampling. (author)

  15. Safety Evaluation Report related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410). Supplement No. 4

    International Nuclear Information System (INIS)

    1986-09-01

    This report supplements the Safety Evaluation Report (NUREG-1047, February 1985) for the application filed by Niagara Mohawk Power Corporation, as applicant and co-owner, for a license to operate Nine Mile Point Nuclear Station, Unit 2 (Docket No. 50-410). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. Supplement 1 to the Safety Evaluation Report was published in June 1985, and contained the report from the Advisory Committee on Reactor Safeguards as well as the resolution of a number of outstanding issues from the Safety Evaluation Report. Supplement 2 was published in November 1985, and contained the resolution of a number of outstanding and confirmatory issues. Supplement 3 was published in July 1986, and contained the resolution of a number of outstanding and confirmatory items, one new confirmatory item, the evaluation of the Engineering Assurance Program, and evaluation of a number of exemption requests

  16. Accuracy of Gallagher’s Classification in Detecting Overweightness and Obesity on the Basis of World Health Organization Gold Standards Cutoff Points

    Directory of Open Access Journals (Sweden)

    A.S. Jahanlou

    2015-04-01

    Full Text Available Introduction & Objective: In the year 2000, Gallagher presented a new classification for body mass on the basis of the Percentile of Body Fat (PBF, age, and sex. The World Health Organization defines gold standard for obesity as PBF>25% in men and >35% in women. The primary purpose of the study was to evaluate the accuracy of Gallagher’s classification in detecting overweightness and obesity on the basis of WHO gold standard cutoff points. Materials & Methods: In this cross sectional- descriptive study the sample consisted of 20163 adults. Body composition measures were obtained, using the Bioelectrical Impedance Analysis (BIA. The detection of obesity was done by computing sensitivity, specificity, Positive Predictive Power (PPV and Negative Predictive Power (NPV for various age and sex groups. Results: There were 14270 women and 5893 men, ranging in age from 18 to 85 years, who participated in the study between 2009 and 2014. On the basis of Gallagher’s classification, 2549 (43.2% men and 2992 (21% women were obese. The WHO gold standard cutoff points showed that 7126 (49.9% women and 3208 men (54.4% met the criteria for being classified as obese. The sensitivity ranged from 53.9% to 100% in males and 38% to 85% in females. The range of specificity among males was from 99.4% to 100%; it was 100% among females. The NPV ranged from 29.8% to 100% in males and 14.1% to 84.3% in females.The PPV ranged from 99.8% to 100 in males and it was 100% in females. Among females, the increase in age was associated with decrease in sensitivity and NPV. Conclusion: Gallagher’s classification is accurate in detecting overweightness and obesity among males between the ages of 18 and 40; however, it is questionable among females. (Sci J Hamadan Univ Med Sci 2015; 22 (1:48-54

  17. The threat of nuclear terrorism: Nuclear weapons or other nuclear explosive devices

    International Nuclear Information System (INIS)

    Maerli, Morten Bremer

    2001-01-01

    Full text: Conventional weaponry and tactics are likely to remain the primary terrorist means for a definitive majority of sub-national groups. No non-state actors have ever deployed or used a nuclear device. However, recent developments in international terrorism may point in the direction of future terrorist uses of weapons of mass destruction, including nuclear devices. Some terrorist groups with a high international profile have showed disturbing interests in acquiring nuclear weapon capabilities. As the 'terrorist nuclear weapon standards' are likely to be lower than the strict requirements for traditional state nuclear weapons, technical barriers should not be considered sufficient to avoid future nuclear terrorist violence. Preventing any extremist group from achieving their goals of large-scale nuclear killing is likely best done by preventing the access to fissile materials through state compliances to rigorous standards of Material Protection, Control and Accountability (MPC and A). (author)

  18. Comparisons between a new point kernel-based scheme and the infinite plane source assumption method for radiation calculation of deposited airborne radionuclides from nuclear power plants.

    Science.gov (United States)

    Zhang, Xiaole; Efthimiou, George; Wang, Yan; Huang, Meng

    2018-04-01

    Radiation from the deposited radionuclides is indispensable information for environmental impact assessment of nuclear power plants and emergency management during nuclear accidents. Ground shine estimation is related to multiple physical processes, including atmospheric dispersion, deposition, soil and air radiation shielding. It still remains unclear that whether the normally adopted "infinite plane" source assumption for the ground shine calculation is accurate enough, especially for the area with highly heterogeneous deposition distribution near the release point. In this study, a new ground shine calculation scheme, which accounts for both the spatial deposition distribution and the properties of air and soil layers, is developed based on point kernel method. Two sets of "detector-centered" grids are proposed and optimized for both the deposition and radiation calculations to better simulate the results measured by the detectors, which will be beneficial for the applications such as source term estimation. The evaluation against the available data of Monte Carlo methods in the literature indicates that the errors of the new scheme are within 5% for the key radionuclides in nuclear accidents. The comparisons between the new scheme and "infinite plane" assumption indicate that the assumption is tenable (relative errors within 20%) for the area located 1 km away from the release source. Within 1 km range, the assumption mainly causes errors for wet deposition and the errors are independent of rain intensities. The results suggest that the new scheme should be adopted if the detectors are within 1 km from the source under the stable atmosphere (classes E and F), or the detectors are within 500 m under slightly unstable (class C) or neutral (class D) atmosphere. Otherwise, the infinite plane assumption is reasonable since the relative errors induced by this assumption are within 20%. The results here are only based on theoretical investigations. They should

  19. Standard deviation of local tallies in global Monte Carlo calculation of nuclear reactor core

    International Nuclear Information System (INIS)

    Ueki, Taro

    2010-01-01

    Time series methodology has been studied to assess the feasibility of statistical error estimation in the continuous space and energy Monte Carlo calculation of the three-dimensional whole reactor core. The noise propagation was examined and the fluctuation of track length tallies for local fission rate and power has been formally shown to be represented by the autoregressive moving average process of orders p and p-1 [ARMA(p,p-1)], where p is an integer larger than or equal to two. Therefore, ARMA(p,p-1) fitting was applied to the real standard deviation estimation of the power of fuel assemblies at particular heights. Numerical results indicate that straightforward ARMA(3,2) fitting is promising, but a stability issue must be resolved toward the incorporation in the distributed version of production Monte Carlo codes. The same numerical results reveal that the average performance of ARMA(3,2) fitting is equivalent to that of the batch method with a batch size larger than 100 and smaller than 200 cycles for a 1,100 MWe pressurized water reactor. (author)

  20. Standardization of the WPS and Development of the Welding Process Management System for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Cho, Hong Seok; Lee, Jang Wook; Cho, Ki Hyun; Choi, Sang Hoon

    2010-01-01

    The purpose of this study is to integrate existing WPS(welding procedure specification) and PQR(procedure qualification records) which are kept by every branch office respectively and to develop a specialized program that will assist in the creation of WPS and PQR in accordance with the ASME Sec. IX, III, B31.1, etc. These research results make possible not only to ensure structural integrity by applying WPS and PQR correctly but also to cut down on expenses by managing the welding process efficiently. Moreover, as the specialized program will be linked with ERP system between KHNP and KPS, an administration action of welding process will be dealt with on-line. The backgrounds of this study are as follows; · Need to apply WPS correctly and promptly · Need to cut down on expenses due to overlapping development WPS · Need to manage welding resources efficiently · Need to standardize welding QA(quality assurance) documents · Need to improve efficiency of administrative welding process

  1. American National Standard administrative controls and quality assurance for the operational phase of nuclear power plants, revision of N18.7-1972

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    This Standard provides requirements and recommendations for an administrative controls and quality assurance program necessary to provide assurance that operational phase activities at nuclear power plants are carried out without undue risk to the health and safety of the public. The requirements of this Standard apply to all activities affecting the safety-related functions of nuclear power plant structures, systems, and components. It is not intended to apply to test mobile and experimental reactors nor reactors not subject to U. S. Nuclear Regulatory Commission licensing. However, applicable sections of this Standard should be used as they apply to related activities. Activities included are: design changes, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling and modifying

  2. Development of a standard data base for FBR core nuclear design. 10. Reevaluation of atomic number density of JOYO Mk-II core

    Energy Technology Data Exchange (ETDEWEB)

    Numata, Kazuyuki; Sato, Wakaei [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center; Ishikawa, Makoto; Arii, Yoshio [Nuclear Energy System Incorporation, Tokyo (Japan)

    1999-07-01

    The material composition of JOYO Mk-II core components in its initial core was reevaluated as a part of the effort for developing a standard data base for FBR core nuclear design. The special feature of the reevaluation is to treat the decay of Pu-241 isotope, so that the atomic number densities of Pu-241 and Am-241 in fuel assemblies can be exactly evaluated on the initial critical date, Nov. 22nd, 1982. Further, the atomic number densities of other core components were also evaluated to improve the analytical accuracy. Those include the control rods which were not so strictly evaluated in the past, and the dummy fuels and the neutron sources which were not treated in the analytical model so far. The results of the present reevaluation were as follows: (1) The changes of atomic number densities of the major nuclides such as Pu-239, U-235 and U-238 were about {+-}0.2 to 0.3%. On the other hand, the number density of Pu-241, which was the motivation of the present work, was reduced by 12%. From the fact, the number densities in the past analysis might be based on the isotope measurement of the manufacturing point of time without considering the decay of Pu-241. (2) As the other core components, the number densities of control rods and outer reflector-type A were largely improved. (author)

  3. Dynamic behavior structural response and capacity evaluation of the standardized WWER-1000 nuclear power plants subjected to severe loading conditions

    International Nuclear Information System (INIS)

    Ambriashvili, Y.K.; Krutzik, N.J.

    1993-01-01

    In order to verify the structural capacity of standardized WWER-1000 MW nuclear power plants, comprehensive static and dynamic analyses were performed in cooperation between Siemens and Atomenergoprojekt. The main goal of these investigations was to perform of a number of seismic analyses of standardized WWER-1000 reactor buildings on the basis of 13 given seismological inputs, taking into account the local soil conditions at 17 different sites defined by in-situ investigations. The analyses were based on appropriate mathematical models (equivalent beam models as well as detailed spatial surface element models) of the coupled vibrating structures (base structure, outer structure, containment, inner structure) and of the layered soil. The analyses were mainly performed using the indirect method (substructure method). Based on the results of the seismic analysis as well as the results of static analysis (pressure and temperature due to LOCA, dead weight, prestressing) an assessment was made of the seismic safety of the containment and the reactor building. Using a complex 3-dimensional model of the structure and the soil, the influence of the flexibility of the basement structure on the structural response was also studied. The structural analyses of the WWER-1000 reactor building led to the conclusion that its design accounts well for the main factors governing the dynamic behavior of the building. The assessment of the forces acting in the structures shows that the bearing capacity of the analyzed building structure corresponds to an earthquake intensity of about 0.2 g to 0.25 g

  4. Verification of surface contamination density standard using clearance automatic laser inspection system for objects from a nuclear power plant

    International Nuclear Information System (INIS)

    Sasaki, Michiya; Ogino, Haruyuki; Ichiji, Takeshi; Hattori, Takatoshi

    2008-01-01

    In the clearance level inspection in Japan, it is necessary to indicate that the activity level of the target object must be less than not only the clearance levels, but also the surface contamination density standards. The classification measurements for these two standards have been performed separately, and the GM survey meters based on beta-ray measurement have mainly been used for surface contamination density measurement so far. Recently the Clearance Automatic Laser Inspection System, named CLALIS, has been developed to estimate the low-level activity concentration. This system consists of 3-dimensional laser scanner for shape measurement and eight large NE102A plastic scintillation detectors for gamma-ray measurement, and it has been clarified that the CLALIS has adequate detection ability for clearance measurement of both metal scraps and concrete debris. In this study, we compared the surface contamination densities for a number of actual contaminated and non-contaminated objects generated inside from the radiation controlled area at the Kashiwazaki-Kariwa nuclear power station by using the CLALIS and the GM survey meter. As a result, since CLALIS could detect the surface contamination as well as the GM survey meter for all measurement targets, it was revealed that CLALIS can rationally achieve clearance level inspection in a single radiation measurement. The practicality of CLALIS in view of the detection limit and processing time was discussed by comparison with the usual radiation monitors for surface contamination measurement. (author)

  5. Nuclear. Getting out of the EPR deadlock: the EPR's evil star; Under the Flamanville vessel; United-Kingdom: Hinkley Point, stop or more? A nuclear which we will be able to finance

    International Nuclear Information System (INIS)

    Dupin, Ludovic

    2016-01-01

    A first article outlines and comments the difficulties faced in the development and construction of the EPR which seems to be born under an evil star, and which resulted in a loss of credibility for the French nuclear industry. The author evokes various steps in the design and test of various components which finally produced important delays and high costs. Moreover, the reactor high power seems not to be adapted to current market status and needs. The reorganisation of the French nuclear sector also produced an unfavourable environment (the dismantling of Areva into two companies is briefly evoked). Now, the objective for EDF is to try to optimize the reactor production and reduce costs by 25 to 30 per cent. A second article addresses the situation of the Flamanville EPR construction which is now six years late. The author proposes an overview of the differences between the various parts and components of the power station: the control room is operational whereas many parts and rooms are still under construction. A new management of construction organisation has been set up. The third article addresses the situation of the British Hinkley Point EPR project. Due to the difficulties met in Finland and in Flamanville, a new financial drift would be a catastrophe, and as many aspects of the project are already well defined, EDF keeps on stating that the decision to build these two EPRs is about to be taken, as it is in fact always delayed. The last article is an interview in which a manager of an important nuclear engineering company comments the role of the French nuclear reactor model in the world, the development of concepts of small modular reactors, and the impact of EPR construction difficulties on the image of the French nuclear industry in the world

  6. IEEE Std 383-1974: IEEE standard for type test of Class IE electric cables, field splices, and connections for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This standard provides direction for establishing type tests which may be used in qualifying Class 1E electric cables, field splices, and other connections for service in nuclear power generating stations. General guidelines for qualifications are given in IEEE Std 323-1974, Standard for Qualifying Class IE Electric Equipment for Nuclear Power Generating Stations. Categories of cables covered are those used for power control and instrumentation services. Though intended primarily to pertain to cable for field installation, this guide may also be used for the qualification of internal wiring of manufactured devices. This guide does not cover cables for service within the reactor vessel

  7. Determination of avermectins by the internal standard recovery correction - high performance liquid chromatography - quantitative Nuclear Magnetic Resonance method.

    Science.gov (United States)

    Zhang, Wei; Huang, Ting; Li, Hongmei; Dai, Xinhua; Quan, Can; He, Yajuan

    2017-09-01

    Quantitative Nuclear Magnetic Resonance (qNMR) is widely used to determine the purity of organic compounds. For the compounds with lower purity especially molecular weight more than 500, qNMR is at risk of error for the purity, because the impurity peaks are likely to be incompletely separated from the peak of major component. In this study, an offline ISRC-HPLC-qNMR (internal standard recovery correction - high performance liquid chromatography - qNMR) was developed to overcome this problem. It is accurate by excluding the influence of impurity; it is low-cost by using common mobile phase; and it extends the applicable scope of qNMR. In this method, a mix solution of the sample and an internal standard was separated by HPLC with common mobile phases, and only the eluents of the analyte and the internal standard were collected in the same tube. After evaporation and re-dissolution, it was determined by qNMR. A recovery correction factor was determined by comparison of the solutions before and after these procedures. After correction, the mass fraction of analyte was constant and it was accurate and precise, even though the sample loss varied during these procedures, or even in bad resolution of HPLC. Avermectin B 1 a with the purity of ~93% and the molecular weight of 873 was analyzed. Moreover, the homologues of avermectin B 1 a were determined based on the identification and quantitative analysis by tandem mass spectrometry and HPLC, and the results were consistent with the results of traditional mass balance method. The result showed that the method could be widely used for the organic compounds, and could further promote qNMR to become a primary method in the international metrological systems. Copyright © 2017 Elsevier B.V. All rights reserved.

  8. ASME N511-19XX, Standard for periodic in-service testing of nuclear air treatment, heating, ventilating and air conditioning systems

    International Nuclear Information System (INIS)

    1997-01-01

    A draft version of the Standard is presented in this document. The Standard covers the requirements for periodic in-service testing of nuclear safety-related air treatment, heating, ventilating, and air conditioning systems in nuclear facilities. The Standard provides a basis for the development of test programs and does not include acceptance criteria, except in cases where the results of one test influence the performance of other tests. The Standard covers general inspection and test requirements, reference values, inspection and test requirements, generic tests, acceptance criteria, in-service test requirements, testing following an abnormal incident, corrective action requirements, and quality assurance. Mandatory appendices provide a visual inspection checklist and four test procedures. Non-mandatory appendices provide additional information and guidance on mounting frame pressure leak test procedure, corrective action, challenge gas substitute selection criteria, and test program development. 8 refs., 10 tabs

  9. Training Standardization

    International Nuclear Information System (INIS)

    Agnihotri, Newal

    2003-01-01

    The article describes the benefits of and required process and recommendations for implementing the standardization of training in the nuclear power industry in the United States and abroad. Current Information and Communication Technologies (ICT) enable training standardization in the nuclear power industry. The delivery of training through the Internet, Intranet and video over IP will facilitate this standardization and bring multiple benefits to the nuclear power industry worldwide. As the amount of available qualified and experienced professionals decreases because of retirements and fewer nuclear engineering institutions, standardized training will help increase the number of available professionals in the industry. Technology will make it possible to use the experience of retired professionals who may be interested in working part-time from a remote location. Well-planned standardized training will prevent a fragmented approach among utilities, and it will save the industry considerable resources in the long run. It will also ensure cost-effective and safe nuclear power plant operation

  10. Comparison of Protein Value of Commercial Baby Food with Homemade Baby Food and Casein Standard in Rats as the Refference point

    Directory of Open Access Journals (Sweden)

    Z. Asemi

    2008-10-01

    Full Text Available Background and ObjectivesEvaluation of protein quality in food is of great importance due to the biological and economical impacts of food proteins. This study has been conducted with the aim of comparing the protein quality of homemade food (mixture of macaroni and soy bean with commercial baby food (Cerelac Wheat using Casein as the refference point.MethodsThis study was conducted on 64 twenty one day old male Wistar rats. The rats were divided into 8 groups, and each group was put on a different diet regiments. The diet regiments were as follow: 2 homemade food+Cerelac test diet, 1 Ccasein+Methionine standard diet, 1 protien-free basal diet, 2 test diet, 1 standard diet and 1 basal diet. The purpose of protien-free diet was to evaluate True Protien Digestability (TPD. Net Protein Ratio (NPR and Protien Efficiency Ratios (PER were investigated by the basal diet. Protein intake and increasing of weight were determined for NPR and PER calculating. Nitrogen intake and fecal Nitrogen were determined to calculate TPD. Comparison of TPD, NPR and PER among the groups were analyzed by ANOVA and Tukey methods.ResultsTPD values of Standard, Cerelac and homemade food diets were 92.8±4, 87±8 and 85.4±3.2; NPR values were 4.3±0.4, 4.3±0.9, 3.8±0.6; and PER values were 3±0.2, 2.5±0.4, 1.7±0.1 respectively. The statistical difference between TPD and PER values were significant (p 0.05. ConclusionThese results shows that TPD and PER of homemade foods are lower than Cerelac while their NPR are acceptable.Keywords: Protein; Cerelac; Macaroni; Soybeens.

  11. Analysed a defective of the machine for a cap-tube nuclear fuel element ME-27 from its electricity point of view

    International Nuclear Information System (INIS)

    Achmad Suntoro

    2009-01-01

    It has been analysed a defective of the machine for a cap-tube nuclear fuel element ME-27 from its electricity point of view. The machine uses magnetic force resistance welding technique. A short circuit was happened within the machine because the nut for tightening high voltage cable for welding transformer was broken so that the cable touched the machine body and produced the short circuit. This condition made both the primary circuit breaker in the building down and produced high voltage pulse induction to the electronic circuit within the machine so that one of its electronic components was defective. This case becomes warnings on how important of tightening a nut according to its strength specification (using wrench torque) and the necessity of voltage transient limitation circuit to be installed. Both of the warnings are necessary for any equipment consuming high electric current oriented such as the ME-27 machine. (author)

  12. Generation of the covariance matrix for a set of nuclear data produced by collapsing a larger parent set through the weighted averaging of equivalent data points

    International Nuclear Information System (INIS)

    Smith, D.L.

    1987-01-01

    A method is described for generating the covariance matrix of a set of experimental nuclear data which has been collapsed in size by the averaging of equivalent data points belonging to a larger parent data set. It is assumed that the data values and covariance matrix for the parent set are provided. The collapsed set is obtained by a proper weighted-averaging procedure based on the method of least squares. It is then shown by means of the law of error propagation that the elements of the covariance matrix for the collapsed set are linear combinations of elements from the parent set covariance matrix. The coefficients appearing in these combinations are binary products of the same coefficients which appear as weighting factors in the data collapsing procedure. As an example, the procedure is applied to a collection of recently-measured integral neutron-fission cross-section ratios. (orig.)

  13. Comparative evaluation of SUV, tumor-to-blood standard uptake ratio (SUR), and dual time point measurements for assessment of the metabolic uptake rate in FDG PET.

    Science.gov (United States)

    Hofheinz, Frank; Hoff, Jörg van den; Steffen, Ingo G; Lougovski, Alexandr; Ego, Kilian; Amthauer, Holger; Apostolova, Ivayla

    2016-12-01

    We have demonstrated recently that the tumor-to-blood standard uptake ratio (SUR) is superior to tumor standardized uptake value (SUV) as a surrogate of the metabolic uptake rate K m of fluorodeoxyglucose (FDG), overcoming several of the known shortcomings of the SUV approach: excellent linear correlation of SUR and K m from Patlak analysis was found using dynamic imaging of liver metastases. However, due to the perfectly standardized uptake period used for SUR determination and the comparatively short uptake period, these results are not automatically valid and applicable for clinical whole-body examinations in which the uptake periods (T) are distinctly longer and can vary considerably. Therefore, the aim of this work was to investigate the correlation between SUR derived from clinical static whole-body scans and K m-surrogate derived from dual time point (DTP) measurements. DTP (18)F-FDG PET/CT was performed in 90 consecutive patients with histologically proven non-small cell lung cancer (NSCLC). In the PET images, the primary tumor was delineated with an adaptive threshold method. For determination of the blood SUV, an aorta region of interest (ROI) was delineated manually in the attenuation CT and transferred to the PET image. Blood SUV was computed as the mean value of the aorta ROI. SUR values were computed as ratio of tumor SUV and blood SUV. SUR values from the early time point of each DTP measurement were scan time corrected to 75 min postinjection (SURtc). As surrogate of K m, we used the SUR(T) slope, K slope, derived from DTP measurements since it is proportional to the latter under the given circumstances. The correlation of SUV and SURtc with K slope was investigated. The prognostic value of SUV, SURtc, and K slope for overall survival (OS) and progression-free survival (PFS) was investigated with univariate Cox regression in a homogeneous subgroup (N=31) treated with primary chemoradiation. Correlation analysis revealed for both, SUV and SURtc, a

  14. Final environmental statement related to the proposed construction of Douglas Point Nuclear Generating Station, Units 1 and 2: (Docket Nos. 50-448 and 50-449)

    International Nuclear Information System (INIS)

    1976-03-01

    The proposed action is the issuance of construction permits to the Potomac Electric Power Company for the construction of the Douglas Point Nuclear Generating Station, Units 1 and 2, located in Charles County, Maryland. The exhaust steam will be cooled via a closed-cycle mode incorporating natural-draft wet cooling towers. The water used in the cooling system will be obtained from the Potomac River. Construction-related activities on the site will convert about 290 acres of the 1390 acres of forested land at the Douglas Point site to industrial use. In addition to acreage at the site, approximately 4.5 miles of transmission corridor will require about 211 acres of land for rights-of-way. This corridor will connect with 27 miles of existing rights-of-way over which a line connecting Possum Point to Burches Hill has already been approved. The installation of new transmission line, uniquely identified with Douglas Point, along the existing right-of-way will involve approximately 464 additional acres. As described in the application, the maximum river water intake will be about 97,200 gpm. Of this, a maximum of about 28,000 gpm will be lost in drift or evaporation from the cooling towers. About 700 gpm maximum of fresh well water will be consumed. It is conservatively assumed that all aquatic organisms entrained in the service water system will be killed due to thermal and mechanical shock. It is further estimated that at 97,200 gpm maximum total river water intake, the maximum impact on the striped bass fishery will be a reduction of <5%. The risk associated with accidental radiation exposure is very low. 32 figs., 59 tabs

  15. Socioeconomic impacts of nuclear generating stations: Nine Mile Point and Fitzpatrick case study. Technical report 1 Oct 78-4 Jan 82

    International Nuclear Information System (INIS)

    Branch, K.; Cochran, R.; Meale, R.

    1982-07-01

    The report documents a case study of the socioeconomic impacts of the construction and operation of the Nine Mile Point and Fitzpatrick nuclear power stations. It is part of a major post-licensing study of the socioeconomic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period, 1980-81. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socioeconomic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

  16. Analytical Evaluation of Preliminary Drop Tests Performed to Develop a Robust Design for the Standardized DOE Spent Nuclear Fuel Canister

    International Nuclear Information System (INIS)

    Ware, A.G.; Morton, D.K.; Smith, N.L.; Snow, S.D.; Rahl, T.E.

    1999-01-01

    The Department of Energy (DOE) has developed a design concept for a set of standard canisters for the handling, interim storage, transportation, and disposal in the national repository, of DOE spent nuclear fuel (SNF). The standardized DOE SNF canister has to be capable of handling virtually all of the DOE SNF in a variety of potential storage and transportation systems. It must also be acceptable to the repository, based on current and anticipated future requirements. This expected usage mandates a robust design. The canister design has four unique geometries, with lengths of approximately 10 feet or 15 feet, and an outside nominal diameter of 18 inches or 24 inches. The canister has been developed to withstand a drop from 30 feet onto a rigid (flat) surface, sustaining only minor damage - but no rupture - to the pressure (containment) boundary. The majority of the end drop-induced damage is confined to the skirt and lifting/stiffening ring components, which can be removed if de sired after an accidental drop. A canister, with its skirt and stiffening ring removed after an accidental drop, can continue to be used in service with appropriate operational steps being taken. Features of the design concept have been proven through drop testing and finite element analyses of smaller test specimens. Finite element analyses also validated the canister design for drops onto a rigid (flat) surface for a variety of canister orientations at impact, from vertical to 45 degrees off vertical. Actual 30-foot drop testing has also been performed to verify the final design, though limited to just two full-scale test canister drops. In each case, the analytical models accurately predicted the canister response

  17. Particle and nuclear physics

    CERN Document Server

    Faessler, Amand

    1971-01-01

    Progress in Particle and Nuclear Physics, Volume 26 covers the significant advances in understanding the fundamentals of particle and nuclear physics. This volume is divided into four chapters, and begins with a brief overview of the various possible ideas beyond the standard model, the problem they address and their experimental tests. The next chapter deals with the basic physics of neutrino mass based on from a gauge theoretic point of view. This chapter considers the various extensions of the standard electroweak theory, along with their implications for neutrino physics. The discussio

  18. Validation of k(0) standardization method in neutron activation analysis-The use of Kayzero for Windows programme at the nuclear physics institute, Rez

    Czech Academy of Sciences Publication Activity Database

    Kubešová, Marie; Kučera, Jan

    2010-01-01

    Roč. 622, č. 2 (2010), s. 403-406 ISSN 0168-9002 Institutional research plan: CEZ:AV0Z10480505 Keywords : neutron activation analysis * k(0) standardization * Validation Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 1.142, year: 2010

  19. The tsunami probabilistic risk assessment (PRA). Example of accident sequence analysis of tsunami PRA according to the standard for procedure of tsunami PRA for nuclear power plants

    International Nuclear Information System (INIS)

    Ohara, Norihiro; Hasegawa, Keiko; Kuroiwa, Katsuya

    2013-01-01

    After the Fukushima Daiichi nuclear power plant (NPP) accident, standard for procedure of tsunami PRA for NPP had been established by the Standardization Committee of AESJ. Industry group had been conducting analysis of Tsunami PRA for PWR based on the standard under the cooperation with electric utilities. This article introduced overview of the standard and examples of accident sequence analysis of Tsunami PRA studied by the industry group according to the standard. The standard consisted of (1) investigation of NPP's composition, characteristics and site information, (2) selection of relevant components for Tsunami PRA and initiating events and identification of accident sequence, (3) evaluation of Tsunami hazards, (4) fragility evaluation of building and components and (5) evaluation of accident sequence. Based on the evaluation, countermeasures for further improvement of safety against Tsunami could be identified by the sensitivity analysis. (T. Tanaka)

  20. The Environmental Protection Agency's Safety Standards for Disposal of Spent Nuclear Fuel: Potential Path Forward in Response to the Report of the Blue Ribbon Commission on America's Nuclear Future - 13388

    International Nuclear Information System (INIS)

    Forinash, Betsy; Schultheisz, Daniel; Peake, Tom

    2013-01-01

    Following the decision to withdraw the Yucca Mountain license application, the Department of Energy created a Blue Ribbon Commission (BRC) on America's Nuclear Future, tasked with recommending a national strategy to manage the back end of the nuclear fuel cycle. The BRC issued its final report in January 2012, with recommendations covering transportation, storage and disposal of spent nuclear fuel (SNF); potential reprocessing; and supporting institutional measures. The BRC recommendations on disposal of SNF and high-level waste (HLW) are relevant to the U.S. Environmental Protection Agency (EPA), which shares regulatory responsibility with the Nuclear Regulatory Commission (NRC): EPA issues 'generally applicable' performance standards for disposal repositories, which are then implemented in licensing. For disposal, the BRC endorses developing one or more geological repositories, with siting based on an approach that is adaptive, staged and consent-based. The BRC recommends that EPA and NRC work cooperatively to issue generic disposal standards-applying equally to all sites-early in any siting process. EPA previously issued generic disposal standards that apply to all sites other than Yucca Mountain. However, the BRC concluded that the existing regulations should be revisited and revised. The BRC proposes a number of general principles to guide the development of future regulations. EPA continues to review the BRC report and to assess the implications for Agency action, including potential regulatory issues and considerations if EPA develops new or revised generic disposal standards. This review also involves preparatory activities to define potential process and public engagement approaches. (authors)

  1. Electric spark discharges in water. Low-energy nuclear transmutations and light leptonic magnetic monopoles in an extended standard model

    Energy Technology Data Exchange (ETDEWEB)

    Stumpf, Harald [Tuebingen Univ. (Germany). Inst. of Theoretical Physics

    2017-11-01

    Light leptonic magnetic monopoles were predicted by Lochak [G. Lochak, Intern. J. Theor. Phys. 24, 1019 (1985).]. Experimental indications based on nuclear transmutations were announced by Urutskoiev et al. [L. I. Urutskoiev, V. I. Liksonov, V. G. Tsinoev, Ann. Fond. L. de Broglie 27, Nr.4, 791 (2002).] and Urutskoev [L. J. Urutskoev, Ann. Fond. L. de Broglie 29, 1149 (2004).]. A theoretical interpretation of these transmutations is proposed under the assumption that light leptonic magnetic monopoles are created during spark discharges in water. The latter should be excited neutrinos according to Lochak. This hypothesis enforces the introduction of an extended Standard Model described in previous papers. The most important results of this study are (i) that multiple proton captures are responsible for the variety of transmutations and that leptonic magnetic monopoles are involved in these processes (ii) that electromagnetic duality can be established for bound states of leptonic monopoles although massive monopoles are in general unstable (iii) that criteria for the emission of leptonic magnetic monopoles and for their catalytic effect on weak decays are set up and elaborated. The study can be considered as a contribution to the efforts of Urutskoiev and Lochak to understand the reasons for accidents in power plants.

  2. Electric Spark Discharges in Water. Low-energy Nuclear Transmutations and Light Leptonic Magnetic Monopoles in an Extended Standard Model

    Science.gov (United States)

    Stumpf, Harald

    2017-08-01

    Light leptonic magnetic monopoles were predicted by Lochak [G. Lochak, Intern. J. Theor. Phys. 24, 1019 (1985).]. Experimental indications based on nuclear transmutations were announced by Urutskoiev et al. [L. I. Urutskoiev, V. I. Liksonov, V. G. Tsinoev, Ann. Fond. L. de Broglie 27, Nr.4, 791 (2002).] and Urutskoev [L. J. Urutskoev, Ann. Fond. L. de Broglie 29, 1149 (2004).]. A theoretical interpretation of these transmutations is proposed under the assumption that light leptonic magnetic monopoles are created during spark discharges in water. The latter should be excited neutrinos according to Lochak. This hypothesis enforces the introduction of an extended Standard Model described in previous papers. The most important results of this study are (i) that multiple proton captures are responsible for the variety of transmutations and that leptonic magnetic monopoles are involved in these processes (ii) that electromagnetic duality can be established for bound states of leptonic monopoles although massive monopoles are in general unstable (iii) that criteria for the emission of leptonic magnetic monopoles and for their catalytic effect on weak decays are set up and elaborated. The study can be considered as a contribution to the efforts of Urutskoiev and Lochak to understand the reasons for accidents in power plants.

  3. Nuclear codes and standards

    International Nuclear Information System (INIS)

    Raisic, N.

    1980-01-01

    The present paper deals with quality assurance regulations and analysesthe difference between documents that can be used in every country and applied on any industrial organizations and documents some aspects of which are bound to the American organization. (orig./RW)

  4. Human reliability guidance - How to increase the synergies between human reliability, human factors, and system design and engineering. Phase 2: The American Point of View - Insights of how the US nuclear industry works with human reliability analysis

    International Nuclear Information System (INIS)

    Oxstrand, J.

    2010-12-01

    The main goal of this Nordic Nuclear Safety Research Council (NKS) project is to produce guidance for how to use human reliability analysis (HRA) to strengthen overall safety. The project consists of two substudies: The Nordic Point of View - A User Needs Analysis, and The American Point of View - Insights of How the US Nuclear Industry Works with HRA. The purpose of the Nordic Point of View study was a user needs analysis that aimed to survey current HRA practices in the Nordic nuclear industry, with the main focus being to connect HRA to system design. In this study, 26 Nordic (Swedish and Finnish) nuclear power plant specialists with research, practitioner, and regulatory expertise in HRA, PRA, HSI, and human performance were interviewed. This study was completed in 2009. This study concludes that HRA is an important tool when dealing with human factors in control room design or modernizations. The Nordic Point of View study showed areas where the use of HRA in the Nordic nuclear industry could be improved. To gain more knowledge about how these improvements could be made, and what improvements to focus on, the second study was conducted. The second study is focused on the American nuclear industry, which has many more years of experience with risk assessment and human reliability than the Nordic nuclear industry. Interviews were conducted to collect information to help the author understand the similarities and differences between the American and the Nordic nuclear industries, and to find data regarding the findings from the first study. The main focus of this report is to identify potential HRA improvements based on the data collected in the American Point of View survey. (Author)

  5. Human reliability guidance - How to increase the synergies between human reliability, human factors, and system design and engineering. Phase 2: The American Point of View - Insights of how the US nuclear industry works with human reliability analysis

    Energy Technology Data Exchange (ETDEWEB)

    Oxstrand, J. (Vattenfall Ringhals AB, Stockholm (Sweden))

    2010-12-15

    The main goal of this Nordic Nuclear Safety Research Council (NKS) project is to produce guidance for how to use human reliability analysis (HRA) to strengthen overall safety. The project consists of two substudies: The Nordic Point of View - A User Needs Analysis, and The American Point of View - Insights of How the US Nuclear Industry Works with HRA. The purpose of the Nordic Point of View study was a user needs analysis that aimed to survey current HRA practices in the Nordic nuclear industry, with the main focus being to connect HRA to system design. In this study, 26 Nordic (Swedish and Finnish) nuclear power plant specialists with research, practitioner, and regulatory expertise in HRA, PRA, HSI, and human performance were interviewed. This study was completed in 2009. This study concludes that HRA is an important tool when dealing with human factors in control room design or modernizations. The Nordic Point of View study showed areas where the use of HRA in the Nordic nuclear industry could be improved. To gain more knowledge about how these improvements could be made, and what improvements to focus on, the second study was conducted. The second study is focused on the American nuclear industry, which has many more years of experience with risk assessment and human reliability than the Nordic nuclear industry. Interviews were conducted to collect information to help the author understand the similarities and differences between the American and the Nordic nuclear industries, and to find data regarding the findings from the first study. The main focus of this report is to identify potential HRA improvements based on the data collected in the American Point of View survey. (Author)

  6. Bubble point measurement and high pressure distillation column design for the environmentally benign separation of zirconium from hafnium for nuclear power reactor

    International Nuclear Information System (INIS)

    Minh, Le Quang; Kim, Gyeongmin; Lee, Moonyong; Park, Jongki

    2015-01-01

    We examined the feasible separation of ZrCl 4 and HfCl 4 through high pressure distillation as environmentally benign separation for structural material of nuclear power reactor. The bubble point pressures of ZrCl 4 and HfCl 4 mixtures were determined experimentally by using an invariable volume equilibrium cell at high pressure and temperature condition range of 2.3-5..6MPa and 440-490 .deg. C. The experimental bubble point pressure data were correlated with Peng-Robinson equation of state with a good agreement. Based on the vapor-liquid equilibrium properties evaluated from the experimental data, the feasibility of high pressure distillation process for the separation of ZrCl 4 and HfCl 4 was investigated with its main design condition through rigorous simulation using a commercial process simulator, ASPEN Hysys. An enhanced distillation configuration was also proposed to improve energy efficiency in the distillation process. The result showed that a heat-pump assisted distillation with a partial bottom flash could be a promising option for commercial separation of ZrCl 4 and HfCl 4 by taking into account of both energy and environmental advantages

  7. An aerial radiological survey of the Point Beach Nuclear Power Plant and surrounding area. Final report, October 19, 1996 - October 24, 1996

    International Nuclear Information System (INIS)

    Feimster, E.L.

    1997-12-01

    Radioactivity surrounding the Point Beach Nuclear Power Plant was measured using aerial radiological surveying techniques. The purpose of this survey was to document exposure rates and identify radiation sources within the survey area. The surveyed area included a 25-square-mile (65-square-kilometer) area, which encompasses the plant site. Data were acquired using an airborne detection system that employed sodium iodide, thallium-activated detectors. Exposure rates at 1 meter above ground level were computed from these data and plotted on a U.S. Geological Survey topographic map of the survey area. Several ground-based exposure-rate measurements were made for comparison with the aerial survey results. Exposure rates in areas surrounding the plant site varied (a) from 10-14 microroentgens per hour (μR/h) in cultivated fields, (b) from 8-10 μR/h in adjacent areas and along roadways, and (c) below 6 μR/h over waterways and wetland areas. Man-made radiation (102-202 μR/h) was found at the plant site; cobalt-60 was the primary source of activity found at the Point Beach site. No other detectable sources of man-made radioactivity were found. The exposure rates measured during this survey agreed well with those measured during the 1970 survey even though the survey methodology and parameters were significantly different

  8. Final environmental statement related to operation of Indian Point Nuclear Generating Plant, Unit No. 3: (Docket No. 50-286): Volume 1

    International Nuclear Information System (INIS)

    1975-02-01

    The proposed action is the issuance of a license to consolidated Edison Company of New York, Inc., for the operation of the Indian Point Nuclear Generating Plant, Unit No. 3, located in the State of New York, Westchester County, Village of Buchanan, 24 miles north of the New York City boundary line. Although the present action is the issuance of an operating license for Unit No. 3, this Statement considers the environmental impacts from simultaneous operation of all three Units. A Final Environmental Statement has been issued for Unit No. 2. Furthermore, in view of the proximity to the Indian Point site of existing and presently proposed power plants on the Hudson River, the cumulative environmental benefits and impacts of the plants within a 30-mile reach of the river have been assessed. The proposed action is interreleated to other actions taken by other Federal agencies such as the Environmental Protection Agency, in regard to granting or denying application for discharge permits under the National Pollutant Discharge Elimination System (NPDES) instituted through the Federal Water Pollution Control Act Amendments of 1972, and the Federal Power Commission, in licensing of other facilities on the Hudson River. 128 figs., 210 tabs

  9. Point-of-care testing for coagulation function: CoaguChek®XS System versus standard laboratory testing in pediatric patients with normal and abnormal coagulation function.

    Science.gov (United States)

    Kako, Hiromi; Raman, Vidya T; Tumin, Dmitry; Rice, Julie; Tobias, Joseph D

    2017-06-01

    Intraoperative abnormalities of coagulation function may occur for various reasons. In most scenarios, treatment is directed by laboratory parameters. Unfortunately, standard laboratory testing may take 1-2 h. The purpose of the current study was to evaluate a point-of-care testing device (CoaguChek ® XS System) in pediatric patients. Patients ranging in age from 2 to 18 years, undergoing posterior spinal fusion (PSF) or cardiac surgery using cardiopulmonary bypass (CPB) were eligible for inclusion. After CPB and/or the surgical procedure, 2.8 ml of blood was obtained and simultaneously tested on both the standard laboratory apparatus and the CoaguChek ® XS System. The study cohort consisted of 100 patients (50 PSF and 50 cardiac cases) with 13 cases excluded, leaving 87 patients (49 PSF and 38 cardiac cases) for analysis. In PSF cases, reference laboratory international normalized ratio (INR) ranged from 0.98 to 1.77 while CoaguChek ® XS INR ranged from 1.0 to 1.3. The correlation coefficient was 0.69. The results of the Bland-Altman analysis showed a bias of 0.09, precision of 0.1, and 95% limits of agreement ranging from -0.11 to 0.28. In cardiac cases, reference INR ranged from 1.68 to 14.19, while CoaguChek ® XS INR ranged from 1.4 to 7.9. The correlation coefficient was 0.35. The results of the Bland-Altman analysis showed a bias of -1.8, precision of 2.1, and 95% limits of agreement ranging from -6.0 to 2.4. INR values obtained from CoaguChek ® XS showed a moderate correlation with reference laboratory values within the normal range. However, in the presence of coagulopathy, the discrepancy was significantly greater, thereby making the CoaguChek ® XS clinically unreliable.

  10. Comparison of Protein Value of Commercial Baby Food with Homemade Baby Food and Casein Standard in Rats as the Refference point

    Directory of Open Access Journals (Sweden)

    Z Asemi

    2012-05-01

    Full Text Available

    Background and Objectives

    Evaluation of protein quality in food is of great importance due to the  biological and economical impacts of food proteins. This study has been conducted with the aim of comparing the protein quality of  homemade food (mixture of macaroni and soy bean with commercial baby food (Cerelac Wheat using Casein as the refference point.

     

    Methods

    This study was conducted on 64 twenty one day old male Wistar rats. The rats were divided into 8 groups, and each group was put on a different diet regiments. The diet regiments were as follow: 2 homemade food+Cerelac test diet, 1 Ccasein+Methionine standard diet, 1 protien-free basal diet, 2 test diet, 1 standard diet and 1 basal diet. The purpose of protien-free diet was  to evaluate True Protien Digestability (TPD. Net Protein Ratio (NPR and Protien Efficiency Ratios (PER were investigated by the basal diet. Protein intake and increasing of weight were determined for NPR and PER calculating. Nitrogen intake and fecal Nitrogen were determined to calculate TPD. Comparison of TPD, NPR and PER among the groups were analyzed by ANOVA and Tukey methods.

     

    Results

    TPD values of Standard, Cerelac and homemade food diets were 92.8±4, 87±8 and 85.4±3.2; NPR values were 4.3±0.4, 4.3±0.9, 3.8±0.6; and PER values were 3±0.2, 2.5±0.4, 1.7±0.1 respectively. The statistical difference between TPD and PER values were significant (p < 0.05, whereas NPR differences were insignificant ( p > 0.05.

     

    Conclusion

    These results shows that TPD and PER of homemade foods are lower than Cerelac while their NPR are acceptable

  11. MONJU experimental data analysis and its feasibility evaluation to build up the standard data base for large FBR nuclear core design

    International Nuclear Information System (INIS)

    Sugino, K.; Iwai, T.

    2006-01-01

    MONJU experimental data analysis was performed by using the detailed calculation scheme for fast reactor cores developed in Japan. Subsequently, feasibility of the MONJU integral data was evaluated by the cross-section adjustment technique for the use of FBR nuclear core design. It is concluded that the MONJU integral data is quite valuable for building up the standard data base for large FBR nuclear core design. In addition, it is found that the application of the updated data base has a possibility to considerably improve the prediction accuracy of neutronic parameters for MONJU. (authors)

  12. Nuclear Energy -- Knowledge Base for Advanced Modeling and Simulation (NE-KAMS) Code Verification and Validation Data Standards and Requirements: Fluid Dynamics Version 1.0

    Energy Technology Data Exchange (ETDEWEB)

    Greg Weirs; Hyung Lee

    2011-09-01

    V&V and UQ are the primary means to assess the accuracy and reliability of M&S and, hence, to establish confidence in M&S. Though other industries are establishing standards and requirements for the performance of V&V and UQ, at present, the nuclear industry has not established such standards or requirements. However, the nuclear industry is beginning to recognize that such standards are needed and that the resources needed to support V&V and UQ will be very significant. In fact, no single organization has sufficient resources or expertise required to organize, conduct and maintain a comprehensive V&V and UQ program. What is needed is a systematic and standardized approach to establish and provide V&V and UQ resources at a national or even international level, with a consortium of partners from government, academia and industry. Specifically, what is needed is a structured and cost-effective knowledge base that collects, evaluates and stores verification and validation data, and shows how it can be used to perform V&V and UQ, leveraging collaboration and sharing of resources to support existing engineering and licensing procedures as well as science-based V&V and UQ processes. The Nuclear Energy Knowledge base for Advanced Modeling and Simulation (NE-KAMS) is being developed at the Idaho National Laboratory in conjunction with Bettis Laboratory, Sandia National Laboratories, Argonne National Laboratory, Utah State University and others with the objective of establishing a comprehensive and web-accessible knowledge base to provide V&V and UQ resources for M&S for nuclear reactor design, analysis and licensing. The knowledge base will serve as an important resource for technical exchange and collaboration that will enable credible and reliable computational models and simulations for application to nuclear power. NE-KAMS will serve as a valuable resource for the nuclear industry, academia, the national laboratories, the U.S. Nuclear Regulatory Commission (NRC) and

  13. Heart tissue of harlequin (hq)/Big Blue mice has elevated reactive oxygen species without significant impact on the frequency and nature of point mutations in nuclear DNA

    Energy Technology Data Exchange (ETDEWEB)

    Crabbe, Rory A. [Department of Biology, University of Western Ontario, London, Ontario, N6A 5B7 (Canada); Hill, Kathleen A., E-mail: khill22@uwo.ca [Department of Biology, University of Western Ontario, London, Ontario, N6A 5B7 (Canada)

    2010-09-10

    Age is a major risk factor for heart disease, and cardiac aging is characterized by elevated mitochondrial reactive oxygen species (ROS) with compromised mitochondrial and nuclear DNA integrity. To assess links between increased ROS levels and mutations, we examined in situ levels of ROS and cII mutation frequency, pattern and spectrum in the heart of harlequin (hq)/Big Blue mice. The hq mouse is a model of premature aging with mitochondrial dysfunction and increased risk of oxidative stress-induced heart disease with the means for in vivo mutation detection. The hq mutation produces a significant downregulation in the X-linked apoptosis-inducing factor gene (Aif) impairing both the antioxidant and oxidative phosphorylation functions of AIF. Brain and skin of hq disease mice have elevated frequencies of point mutations in nuclear DNA and histopathology characterized by cell loss. Reports of associated elevations in ROS in brain and skin have mixed results. Herein, heart in situ ROS levels were elevated in hq disease compared to AIF-proficient mice (p < 0.0001) yet, mutation frequency and pattern were similar in hq disease, hq carrier and AIF-proficient mice. Heart cII mutations were also assessed 15 days following an acute exposure to an exogenous ROS inducer (10 mg paraquat/kg). Acute paraquat exposure with a short mutant manifestation period was insufficient to elevate mutation frequency or alter mutation pattern in the post-mitotic heart tissue of AIF-proficient mice. Paraquat induction of ROS requires mitochondrial complex I and thus is likely compromised in hq mice. Results of this preliminary survey and the context of recent literature suggest that determining causal links between AIF deficiency and the premature aging phenotypes of specific tissues is better addressed with assay of mitochondrial ROS and large-scale changes in mitochondrial DNA in specific cell types.

  14. Heart tissue of harlequin (hq)/Big Blue mice has elevated reactive oxygen species without significant impact on the frequency and nature of point mutations in nuclear DNA

    International Nuclear Information System (INIS)

    Crabbe, Rory A.; Hill, Kathleen A.

    2010-01-01

    Age is a major risk factor for heart disease, and cardiac aging is characterized by elevated mitochondrial reactive oxygen species (ROS) with compromised mitochondrial and nuclear DNA integrity. To assess links between increased ROS levels and mutations, we examined in situ levels of ROS and cII mutation frequency, pattern and spectrum in the heart of harlequin (hq)/Big Blue mice. The hq mouse is a model of premature aging with mitochondrial dysfunction and increased risk of oxidative stress-induced heart disease with the means for in vivo mutation detection. The hq mutation produces a significant downregulation in the X-linked apoptosis-inducing factor gene (Aif) impairing both the antioxidant and oxidative phosphorylation functions of AIF. Brain and skin of hq disease mice have elevated frequencies of point mutations in nuclear DNA and histopathology characterized by cell loss. Reports of associated elevations in ROS in brain and skin have mixed results. Herein, heart in situ ROS levels were elevated in hq disease compared to AIF-proficient mice (p < 0.0001) yet, mutation frequency and pattern were similar in hq disease, hq carrier and AIF-proficient mice. Heart cII mutations were also assessed 15 days following an acute exposure to an exogenous ROS inducer (10 mg paraquat/kg). Acute paraquat exposure with a short mutant manifestation period was insufficient to elevate mutation frequency or alter mutation pattern in the post-mitotic heart tissue of AIF-proficient mice. Paraquat induction of ROS requires mitochondrial complex I and thus is likely compromised in hq mice. Results of this preliminary survey and the context of recent literature suggest that determining causal links between AIF deficiency and the premature aging phenotypes of specific tissues is better addressed with assay of mitochondrial ROS and large-scale changes in mitochondrial DNA in specific cell types.

  15. Standard specification for uranium oxides with a 235U content of less than 5 % for dissolution prior to conversion to nuclear-grade uranium dioxide

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2005-01-01

    1.1 This specification covers uranium oxides, including processed byproducts or scrap material (powder, pellets, or pieces), that are intended for dissolution into uranyl nitrate solution meeting the requirements of Specification C788 prior to conversion into nuclear grade UO2 powder with a 235U content of less than 5 %. This specification defines the impurity and uranium isotope limits for such urania powders that are to be dissolved prior to processing to nuclear grade UO2 as defined in Specification C753. 1.2 This specification provides the nuclear industry with a general standard for such uranium oxide powders. It recognizes the diversity of conversion processes and the processes to which such powders are subsequently to be subjected (for instance, by solvent extraction). It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between the buyer and seller. 1.3 The scope of this specification does not comprehensively cover all provisions for prevent...

  16. Nuclear technology in Germany in 1993

    International Nuclear Information System (INIS)

    1993-07-01

    On 28-29 January 1993, the Nuclear Safety Department of the Federal Office for Radiation Protection in co-operation with the Office of the Nuclear Safety Standards Commission organized a winter seminar on 'Nuclear technology in the Federal Republic in 1993 - tasks, problems, perspectives from the point of view of those concerned'. Main topics were the practical aspects of nuclear safety regulations and the application of the nuclear safety rules. This volume includes the welcome and opening addresses and the 12 papers presented; the views expressed remain, however the responsibility of the named authors and are not necessarily those of the editor. (orig.) [de

  17. Development and evaluation of Standard Operating Procedures (SOPs) for quality control tests and radiological protection activities in a Nuclear Medicine Service

    International Nuclear Information System (INIS)

    Krempser, Alexandre R.; Soares, Alexandre B.; Corbo, Rossana

    2011-01-01

    The quality management in Nuclear Medicine Services is a requirement of national and international standards. The Brazilian regulatory agency in health surveillance, the Agencia Nacional de Vigilancia Sanitaria (ANVISA), in its Resolucao de Diretoria Colegiada (Collegiate Directory Resolution) no. 38, requires the elaboration of documents describing the technical and clinical routine activities. This study aimed to elaborate, implement and evaluate Standard Operating Procedures (SOPs) for quality control tests and radiological protection activities in the Nuclear Medicine Service of a university hospital. Eighteen SOPs were developed, involving tasks related to dose calibrator, gamma camera, Geiger-Muller detectors and radiological protection activities. The performance of its application was evaluated for a period of six months. It was observed a reduction in 75% of reported operational errors and 42% of the number of reported incidents with contamination by radioactive material. The SOPs were adequate and successful in its application. New procedures involving clinical activities will also be developed and evaluated. (author)

  18. Standard test method for the determination of uranium by ignition and the oxygen to uranium (O/U) atomic ratio of nuclear grade uranium dioxide powders and pellets

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2000-01-01

    1.1 This test method covers the determination of uranium and the oxygen to uranium atomic ratio in nuclear grade uranium dioxide powder and pellets. 1.2 This test method does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this test method does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. 1.4 This test method also is applicable to UO3 and U3O8 powder.

  19. A dose point kernel database using GATE Monte Carlo simulation toolkit for nuclear medicine applications: comparison with other Monte Carlo codes.

    Science.gov (United States)

    Papadimitroulas, Panagiotis; Loudos, George; Nikiforidis, George C; Kagadis, George C

    2012-08-01

    GATE is a Monte Carlo simulation toolkit based on the Geant4 package, widely used for many medical physics applications, including SPECT and PET image simulation and more recently CT image simulation and patient dosimetry. The purpose of the current study was to calculate dose point kernels (DPKs) using GATE, compare them against reference data, and finally produce a complete dataset of the total DPKs for the most commonly used radionuclides in nuclear medicine. Patient-specific absorbed dose calculations can be carried out using Monte Carlo simulations. The latest version of GATE extends its applications to Radiotherapy and Dosimetry. Comparison of the proposed method for the generation of DPKs was performed for (a) monoenergetic electron sources, with energies ranging from 10 keV to 10 MeV, (b) beta emitting isotopes, e.g., (177)Lu, (90)Y, and (32)P, and (c) gamma emitting isotopes, e.g., (111)In, (131)I, (125)I, and (99m)Tc. Point isotropic sources were simulated at the center of a sphere phantom, and the absorbed dose was stored in concentric spherical shells around the source. Evaluation was performed with already published studies for different Monte Carlo codes namely MCNP, EGS, FLUKA, ETRAN, GEPTS, and PENELOPE. A complete dataset of total DPKs was generated for water (equivalent to soft tissue), bone, and lung. This dataset takes into account all the major components of radiation interactions for the selected isotopes, including the absorbed dose from emitted electrons, photons, and all secondary particles generated from the electromagnetic interactions. GATE comparison provided reliable results in all cases (monoenergetic electrons, beta emitting isotopes, and photon emitting isotopes). The observed differences between GATE and other codes are less than 10% and comparable to the discrepancies observed among other packages. The produced DPKs are in very good agreement with the already published data, which allowed us to produce a unique DPKs dataset using

  20. Creating symbiosis in research and education. Preserve nuclear competencies for Germany and provide highest safety standards to international markets

    International Nuclear Information System (INIS)

    Niessen, Stefan

    2015-01-01

    AREVA participates actively in networks of industry and science via university cooperation and gives new ideas born from practical experience for the academic training of future nuclear engineers. Thus, the company ensures both the availability of new talents for its export strategy and relevant expertise for nuclear safety in Germany. When it comes to education and science after the German nuclear phase-out decision, the efforts must focus on internationalization. Greater integration in international networks can contribute to keeping the nuclear know-how in Germany alive. This concerns both industry and science. By having foreign experts use German training facilities, participate in research projects and gather professional practice, they contribute to the safe operation here and experience first-hand our safety culture grown over decades. In this context, AREVA outlines its university cooperation in Germany and abroad.

  1. Determination of Kr-85 in environmental samples and gaseous effluents from nuclear industries using the standard method

    International Nuclear Information System (INIS)

    Heras Iniquez, M.C.; Perez Garcia, M.M.

    1983-01-01

    The determination of the Kr-85 activity in environmental samples and gaseous effluents from Spanish Nuclear Power Stations is described. The method employed has been published elsewhere. The determinations has been carried out in environmental samples token at JEN Laboratories (Madrid) and the Nuclear Power Stations, Jose Cabrera (Zorita), Garona and Vandellos. Also samples of gaseous effluents of the three plants has been analyzed. Values of the Kr-85 environmental background activity in the Almaraz Nuclear Power Stations, has been determined, before the beginning of its nuclear activity. In this paper the sampling equipment used is described and the values found of Kr-85 activity in all the samples in given. (Author) 29 refs

  2. Creating symbiosis in research and education. Preserve nuclear competencies for Germany and provide highest safety standards to international markets

    Energy Technology Data Exchange (ETDEWEB)

    Niessen, Stefan [AREVA GmbH, Erlangen (Germany). Research and Development, Innovations and Patent Management

    2015-06-15

    AREVA participates actively in networks of industry and science via university cooperation and gives new ideas born from practical experience for the academic training of future nuclear engineers. Thus, the company ensures both the availability of new talents for its export strategy and relevant expertise for nuclear safety in Germany. When it comes to education and science after the German nuclear phase-out decision, the efforts must focus on internationalization. Greater integration in international networks can contribute to keeping the nuclear know-how in Germany alive. This concerns both industry and science. By having foreign experts use German training facilities, participate in research projects and gather professional practice, they contribute to the safe operation here and experience first-hand our safety culture grown over decades. In this context, AREVA outlines its university cooperation in Germany and abroad.

  3. Evaluation of the Effect of Tumor Position on Standardized Uptake Value Using Time-of-Flight Reconstruction and Point Spread Function

    Directory of Open Access Journals (Sweden)

    Yasuharu Wakabayashi

    2016-01-01

    Full Text Available Objective(s: The present study was conducted to examine whether the standardized uptake value (SUV may be affected by the spatial position of a lesion in the radial direction on positron emission tomography (PET images, obtained via two methods based on time-of-flight (TOF reconstruction and point spread function (PSF. Methods: A cylinder phantom with the sphere (30mm diameter, located in the center was used in this study. Fluorine-18 fluorodeoxyglucose (18F-FDG concentrations of 5.3 kBq/ml and 21.2 kBq/ml were used for the background in the cylinder phantom and the central sphere respectively. By the use of TOF and PSF, SUVmax and SUVmean were determined while moving the phantom in a horizontal direction (X direction from the center of field of view (FOV: 0 mm at 50, 100, 150 and 200 mm positions, respectively. Furthermore, we examined 41 patients (23 male, 18 female, mean age: 68±11.2 years with lymph node tumors , who had undergone 18F-FDG PET examinations. The distance of each lymph node from FOV center was measured, based on the clinical images. Results: As the distance of a lesion from the FOV center exceeded 100 mm, the value of SUVmax, which was obtained with the cylinder phantom, was overestimated, while SUVmean by TOF and/or PSF was underestimated. Based on the clinical examinations, the average volume of interest was 8.5 cm3. Concomitant use of PSF increased SUVmax and SUVmean by 27.9% and 2.8%, respectively. However, size of VOI and distance from the FOV center did not affect SUVmax or SUVmean in clinical examinations. Conclusion: The reliability of SUV quantification by TOF and/or PSF decreased, when the tumor was located at a 100 mm distance (or farther from the center of FOV. In clinical examinations, if the lymph node was located within 100 mm distance from the center of FOV, SUV remained stable within a constantly increasing range by use of both TOF and PSF. We conclude that, use of both TOF and PSF may be helpful.

  4. BILATERAL KEY COMPARISON SIM.T-K6.5 ON HUMIDITY STANDARDS IN THE DEW/FROST-POINT TEMPERATURE RANGE FROM −30 °C TO +20 °C

    Science.gov (United States)

    Meyer, C.W.; Solano, A.

    2016-01-01

    A Regional Metrology Organization (RMO) Key Comparison of dew/frost point temperatures over the range −30 °C TO +20 °C was carried out by the National Institute of Standards and Technology (NIST, USA) and the Laboratorio Costarricense de Metrología (LACOMET, Costa Rica), between February 2015 and August 2015. The results of this comparison are reported here, along with descriptions of the humidity laboratory standards for NIST and LACOMET and the uncertainty budget for these standards. This report also describes the protocol for the comparison and presents the data acquired. The results are analyzed, determining the degree of equivalence between the dew/frost-point standards of NIST and LACOMET. PMID:28066029

  5. Nuclear security - New challenge to the safety of nuclear power plants

    International Nuclear Information System (INIS)

    Li Ganjie

    2008-01-01

    The safety of nuclear power plants involves two aspects: one is to prevent nuclear accidents resulted from systems and equipments failure or human errors; the other is to refrain nuclear accidents from external intended attack. From this point of view, nuclear security is an organic part of the nuclear safety of power plants since they have basically the same goals and concrete measures with each other. In order to prevent malicious attacks; the concept of physical protection of nuclear facilities has been put forward. In many years, a series of codes and regulations as well as technical standard systems on physical protection had been developed at international level. The United Nations passed No. 1540 resolution as well as 'Convention on the Suppression of Acts of Nuclear terrorism', and revised 'Convention on Physical Protection of Nuclear Materials', which has enhanced a higher level capacity of preparedness by international community to deal with security issues of nuclear facilities. In China, in order to improve the capability of nuclear power plants on preventing and suppressing the external attacks, the Chinese government consecutively developed the related codes and standards as well as technical documents based on the existing laws and regulations, including 'Guide for the Nuclear Security of Nuclear Power Plants' and 'Guide for the Physical Protection of Nuclear Materials', so as to upgrade the legislative requirements for nuclear security in power plants. The government also made greater efforts to support the scientific research and staff training on physical protection, and satisfying the physical protection standards for newly-built nuclear facilities such as large scale nuclear power plants to meet requirement at international level. At the same time old facilities were renovated and the Chinese government established a nuclear emergency preparedness coordination mechanism, developed corresponding emergency preparedness plans, intensified the

  6. Economics from a Different Point of View − Good Practice in Teacher Training: How to Handle, Use and Judge External Standardized Tests in Schools

    Directory of Open Access Journals (Sweden)

    Julia Claire Prieß-Buchheit

    2016-02-01

    Full Text Available The Economic Actions in Education training module (EAE teaches how to handle, use and judge external standardized tests in schools. The EAE programme was implemented in teacher training at the University of Kiel, because teachers are increasingly under external scrutiny and are being held accountable for student and school achievements. The EAE programme includes a reader (in English, through which prospective teachers understand and analyze core terms of the field. Furthermore, different didactical methods such as think-pair-share, role play and short lectures provide a group dynamic in which students gain an insight into standardized tests at a macro level. Students learn what is involved in standardized tests and they develop the ability to make a critical judgement about how they will use or refuse standardized tests in schools. EAE enables teachers to use standardized tests for curriculum and instruction improvement as well as refuse standardized tests to highlight autonomous teaching and decline governance from outside.

  7. Nuclear blackmail and nuclear balance

    International Nuclear Information System (INIS)

    Betts, R.K.

    1987-01-01

    This book raises pointed questions about nuclear saber rattling. More than a dozen cases since the bombing of Hiroshima and Magasaki in which some sort of nuclear threat was used as a sparring technique in tense confrontations are cited. Each incident is described and analyzed. Two theories offered to explain America's use of nuclear threats, the balance of interest theory and the balance of power theory, are contrasted throughout the book. This book helps to fill the gap in the understanding of nuclear weapons and their uses, while pointing out that nuclear bravado could lead to an unintended unleashing of these weapons

  8. The decision on the application to carry out a decommissioning project at Hinkley Point A Power Station under the Nuclear Reactors (Environmental Impact Assessment for Decommissioning) Regulations 1999

    International Nuclear Information System (INIS)

    2003-01-01

    European Council Directive 85/337/EEC, as amended by Council Directive 97/1 I/EC, sets out a framework on the assessment of the effects of certain public and private projects on the environment. The Directive is implemented in Great Britain for decommissioning nuclear reactor projects by the Nuclear Reactors (Environmental Impact Assessment for Decommissioning) Regulations 1999. The intention of the Directive and Regulations is to involve the public through consultation in considering the potential environmental impacts of a decommissioning project, and to make the decision-making process on granting consent open and transparent. The Regulations require the licensee to undertake an environmental impact assessment, prepare an environmental statement that summarises the environmental effects of the project, and apply to the Health and Safety Executive (HSE) for consent to carry out a decommissioning project. There is an optional stage where the licensee may request from HSE an opinion on what the environmental statement should contain (called a pre-application opinion). The licensee of Hinkley Point A Power Station, Magnox Electric pie, requested a pre-application opinion and provided information in a scoping report in December 2000. HSE undertook a public consultation on the scoping report and provided its pre- application opinion in April 2001. The licensee applied to HSE for consent to carry out a decommissioning project and provided an environmental statement in December 2001. Following a public consultation on the environmental statement, HSE requested further information that was subsequently provided by the licensee. A further public consultation was undertaken on the further information that ended in March 2003. All these public consultations involved around 60 organisations. HSE granted consent to carry out a decommissioning project at Hinkley Point A Power Station under the Regulations in July 2003, and attached conditions to the Consent. HSE took relevant

  9. The NEA takes stock of the nuclear wastes management; L`AEN fait le point sur la gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1996-07-01

    The Nuclear Energy Agency (NEA) from the OECD has published a report which brings together the balance sheets of all national programs of nuclear wastes management as they are applied in several countries having or having had a nuclear activity. About 12 countries are reviewed in this document. This short paper summarizes some elements of this report concerning Germany, Belgium, Canada, Spain, the USA, Italy, Switzerland, UK, Netherlands, Finland Sweden and Mexico. (J.S.).

  10. Towards standardized calculation tools for the Accelerator-Driven Systems and their application to various scenarios for nuclear waste transmutation

    International Nuclear Information System (INIS)

    Cometto, M.

    2003-01-01

    This thesis discusses the question of partitioning and transmutation of actinides and some long-lived fission products as a way of reducing the mass and radio-toxicity of wastes from nuclear power facilities. Numerical benchmarking and computational exercises carried out in related projects are discussed and the quantitative assessment of the advantages and drawbacks of various transmutation strategies are discussed, as is the role of Accelerator-Driven Systems (ADS) and Advanced Fast Reactors (FR) in advanced nuclear fuel cycles. According to the author, the study allows three main options in nuclear waste management - open cycle, plutonium recycling and the recycling of all actinides - to be compared. The last part of the dissertation is dedicated to two phase-out schemes employing either ASDs or critical reactors

  11. Standard test method for nondestructive assay of special nuclear material holdup using Gamma-Ray spectroscopic methods

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2007-01-01

    1.1 This test method describes gamma-ray methods used to nondestructively measure the quantity of 235U, or 239Pu remaining as holdup in nuclear facilities. Holdup occurs in all facilities where nuclear material is processed, in process equipment, in exhaust ventilation systems and in building walls and floors. 1.2 This test method includes information useful for management, planning, selection of equipment, consideration of interferences, measurement program definition, and the utilization of resources (1, 2, 3, 4). 1.3 The measurement of nuclear material hold up in process equipment requires a scientific knowledge of radiation sources and detectors, transmission of radiation, calibration, facility operations and error analysis. It is subject to the constraints of the facility, management, budget, and schedule; plus health and safety requirements; as well as the laws of physics. The measurement process includes defining measurement uncertainties and is sensitive to the form and distribution of the material...

  12. A comparative uncertainty study of the calibration of macrolide antibiotic reference standards using quantitative nuclear magnetic resonance and mass balance methods

    International Nuclear Information System (INIS)

    Liu Shuyu; Hu Changqin

    2007-01-01

    This study introduces the general method of quantitative nuclear magnetic resonance (qNMR) for the calibration of reference standards of macrolide antibiotics. Several qNMR experimental conditions were optimized including delay, which is an important parameter of quantification. Three kinds of macrolide antibiotics were used to validate the accuracy of the qNMR method by comparison with the results obtained by the high performance liquid chromatography (HPLC) method. The purities of five common reference standards of macrolide antibiotics were measured by the 1 H qNMR method and the mass balance method, respectively. The analysis results of the two methods were compared. The qNMR is quick and simple to use. In a new medicine research and development process, qNMR provides a new and reliable method for purity analysis of the reference standard

  13. The utility of system-level RAM analysis and standards for the US nuclear waste management system

    International Nuclear Information System (INIS)

    Rod, S.R.; Adickes, M.D.; Paul, B.K.

    1992-03-01

    The Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing a system to manage spent nuclear fuel and high-level radioactive waste in accordance with the Nuclear Waste Policy Act of 1982 and its subsequent amendments. Pacific Northwest Laboratory (PNL) is assisting OCRWM in its investigation of whether system-level reliability, availability, and maintainability (RAM) requirements are appropriate for the waste management system and, if they are, what appropriate form should be for such requirements. Results and recommendations are presented

  14. Standard test methods for chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade uranium dioxide powders and pellets

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1999-01-01

    1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade uranium dioxide powders and pellets to determine compliance with specifications. 1.2 This test method covers the determination of uranium and the oxygen to uranium atomic ratio in nuclear-grade uranium dioxide powder and pellets. 1.4 This test method covers the determination of chlorine and fluorine in nuclear-grade uranium dioxide. With a 1 to 10-g sample, concentrations of 5 to 200 g/g of chlorine and 1 to 200 μg/g of fluorine are determined without interference. 1.5 This test method covers the determination of moisture in uranium dioxide samples. Detection limits are as low as 10 μg. 1.6 This test method covers the determination of nitride nitrogen in uranium dioxide in the range from 10 to 250 μg. 1.7 This test method covers the spectrographic analysis of nuclear-grade UO2 for the 26 elements in the ranges indicated in Table 2. 1.8 For simultaneous determination of trace ele...

  15. ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data

    Science.gov (United States)

    Brown, D. A.; Chadwick, M. B.; Capote, R.; Kahler, A. C.; Trkov, A.; Herman, M. W.; Sonzogni, A. A.; Danon, Y.; Carlson, A. D.; Dunn, M.; Smith, D. L.; Hale, G. M.; Arbanas, G.; Arcilla, R.; Bates, C. R.; Beck, B.; Becker, B.; Brown, F.; Casperson, R. J.; Conlin, J.; Cullen, D. E.; Descalle, M.-A.; Firestone, R.; Gaines, T.; Guber, K. H.; Hawari, A. I.; Holmes, J.; Johnson, T. D.; Kawano, T.; Kiedrowski, B. C.; Koning, A. J.; Kopecky, S.; Leal, L.; Lestone, J. P.; Lubitz, C.; Márquez Damián, J. I.; Mattoon, C. M.; McCutchan, E. A.; Mughabghab, S.; Navratil, P.; Neudecker, D.; Nobre, G. P. A.; Noguere, G.; Paris, M.; Pigni, M. T.; Plompen, A. J.; Pritychenko, B.; Pronyaev, V. G.; Roubtsov, D.; Rochman, D.; Romano, P.; Schillebeeckx, P.; Simakov, S.; Sin, M.; Sirakov, I.; Sleaford, B.; Sobes, V.; Soukhovitskii, E. S.; Stetcu, I.; Talou, P.; Thompson, I.; van der Marck, S.; Welser-Sherrill, L.; Wiarda, D.; White, M.; Wormald, J. L.; Wright, R. Q.; Zerkle, M.; Žerovnik, G.; Zhu, Y.

    2018-02-01

    We describe the new ENDF/B-VIII.0 evaluated nuclear reaction data library. ENDF/B-VIII.0 fully incorporates the new IAEA standards, includes improved thermal neutron scattering data and uses new evaluated data from the CIELO project for neutron reactions on 1H, 16O, 56Fe, 235U, 238U and 239Pu described in companion papers in the present issue of Nuclear Data Sheets. The evaluations benefit from recent experimental data obtained in the U.S. and Europe, and improvements in theory and simulation. Notable advances include updated evaluated data for light nuclei, structural materials, actinides, fission energy release, prompt fission neutron and γ-ray spectra, thermal neutron scattering data, and charged-particle reactions. Integral validation testing is shown for a wide range of criticality, reaction rate, and neutron transmission benchmarks. In general, integral validation performance of the library is improved relative to the previous ENDF/B-VII.1 library.

  16. Technical evaluation report on the adequacy of station electric distribution system voltages for the Point Beach Nuclear Plant, Units 1 and 2. (Docket Nos. 50-266, 50-301)

    International Nuclear Information System (INIS)

    White, R.L.

    1983-01-01

    This report documents the technical evaluation of the adequacy of the station electric distribution system voltages for the Point Beach Nuclear Plant, Units 1 and 2. The evaluation is to determine if the onsite distribution system, in conjunction with the offsite power sources, has sufficient capacity to automatically start and operate all Class 1E loads within the equipment voltage ratings under certain conditions established by the Nuclear Regulatory Commission. For the worst case conditions study submitted by the licensee, it was shown that the station electric distribution system voltages would be adequate to start and operate 4160-volt and 480-volt Class 1E loads and their associated low voltage controls

  17. Response to the Point of View of Gregory B. Pauly, David M. Hillis, and David C. Cannatella, by the Anuran Subcommittee of the SSAR/HL/ASIH Scientific and Standard English Names List

    Science.gov (United States)

    Frost, Darrel R.; McDiarmid, Roy W.; Mendelson, Joseph R.

    2009-01-01

    The Point of View by Gregory Pauly, David Hillis, and David Cannatella misrepresents the motives and activities of the anuran subcommittee of the Scientific and Standard English Names Committee, contains a number of misleading statements, omits evidence and references to critical literature that have already rejected or superseded their positions, and cloaks the limitations of their nomenclatural approach in ambiguous language. Their Point of View is not about promoting transparency in the process of constructing the English Names list, assuring that its taxonomy is adequately reviewed, or promoting nomenclatural stability in any global sense. Rather, their Point of View focuses in large part on a single publication, The Amphibian Tree of Life, which is formally unrelated to the Standard English Names List, and promotes an approach to nomenclature mistakenly asserted by them to be compatible with both the International Code of Zoological Nomenclature and one of its competitors, the PhyloCode.

  18. Standard test methods for chemical and mass spectrometric analysis of nuclear-grade gadolinium oxide (Gd2O3) powder

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2006-01-01

    1.1 These test methods cover procedures for the chemical and mass spectrometric analysis of nuclear-grade gadolinium oxide powders to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Carbon by Direct CombustionThermal Conductivity C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method Total Chlorine and Fluorine by Pyrohydrolysis Ion Selective Electrode C1502 Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide Loss of Weight on Ignition 7-13 Sulfur by CombustionIodometric Titration Impurity Elements by a Spark-Source Mass Spectrographic C761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical,Nuclear, and Radiochemical Analysis of Uranium Hexafluoride C1287 Test Method for Determination of Impurities In Uranium Dioxide By Inductively Coupled Plasma Mass Spectrometry Gadolinium Content in Gadolinium Oxid...

  19. Environmental standards for management and disposal of spent nuclear fuel, high-level and transuranic radioactive wastes, 40 CFR part 191: draft environmental impact statement

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    The establishment of environmental standards for management and disposal of spent nuclear reactor fuel and high-level and transuranic radioactive wastes is proposed. The standards would require that maximum individual doses from all normal operations be limited to 25 millirem to the whole body, 75 millirem to the thyroid, and 25 millirem to any other organ. Regarding disposal of subject materials in geologic sites, the standards would include numerical containment requirements for the first 10,000 years following disposal, assurance requirements, and procedural requirements. The assurance requirements would provide seven principles necessary for developing confidence that long-term containment requirements would be upheld. The principles would call for well-designed, multiple-barrier disposal systems that would not rely on future generations for maintenance and would not be located near potential valuable resources. The principles would also require that future generations be provided with information about the location and dangers of the wastes and an option to recover the wastes if necessary. Procedural requirements would be developed to assure that the containment requirements were upheld. The implementation of the standards would protect public health and the environment against emissions of radioactivity. The maximum impact expected from a disposal system complying with the proposed standards would be less than 1000 premature cancer deaths over the first 10,000 years for disposal of high-level wastes produced by all currently operating reactors over their lifetime

  20. Determination of the details of technical standard concerning the transport of nuclear fuel materials outside the works or the enterprise

    International Nuclear Information System (INIS)

    1979-01-01

    The determination is defined under the regulations concerning the transport of nuclear fuel materials outside the works or the enterprise. The least dangerous nuclear fuel materials designated by the Director General of Science and Technology Agency include, besides such materials listed and corresponding to the particular terms, natural or depleted uranium, natural thorium and their compounds whose surface is covered by corrosion resistance metal. The permissible density of surface stipulated by the Director is 1/100,000 micro-curie per centi-meter 2 for radioactive substances not emitting alpha rays and 1/10,000 micro-curie per centi-meter 2 for radioactive substances emitting alpha rays. General test conditions of A, BM and BU type of loads are in detail provided for. The nuclear fuel materials defined by the Director not as fission materials are uranium 233 and 235, plutonium 238 or 241, whose quantity or combined quantity of such substances do not exceed 15 grams and natural or depleted uranium. The permissible accumulative dose specified for employees is the figure (unit rem) calculated by the formula D=5 (N-18), when D means the permissible accumulative dose and N number of the age. The permissible exposure dose shall be 3 rem for 3 months for employees and 1.5 rem for a year for persons other than employees. (Okada, K.)